Regulatory Technology Development Plan Sodium Fast Reactor. Mechanistic Source Term Development

Energy Technology Data Exchange (ETDEWEB)

Grabaskas, David S. [Argonne National Lab. (ANL), Argonne, IL (United States); Brunett, Acacia Joann [Argonne National Lab. (ANL), Argonne, IL (United States); Bucknor, Matthew D. [Argonne National Lab. (ANL), Argonne, IL (United States); Sienicki, James J. [Argonne National Lab. (ANL), Argonne, IL (United States); Sofu, Tanju [Argonne National Lab. (ANL), Argonne, IL (United States)

2015-02-28

Construction and operation of a nuclear power installation in the U.S. requires licensing by the U.S. Nuclear Regulatory Commission (NRC). A vital part of this licensing process and integrated safety assessment entails the analysis of a source term (or source terms) that represents the release of radionuclides during normal operation and accident sequences. Historically, nuclear plant source term analyses have utilized deterministic, bounding assessments of the radionuclides released to the environment. Significant advancements in technical capabilities and the knowledge state have enabled the development of more realistic analyses such that a mechanistic source term (MST) assessment is now expected to be a requirement of advanced reactor licensing. This report focuses on the state of development of an MST for a sodium fast reactor (SFR), with the intent of aiding in the process of MST definition by qualitatively identifying and characterizing the major sources and transport processes of radionuclides. Due to common design characteristics among current U.S. SFR vendor designs, a metal-fuel, pool-type SFR has been selected as the reference design for this work, with all phenomenological discussions geared toward this specific reactor configuration. This works also aims to identify the key gaps and uncertainties in the current knowledge state that must be addressed for SFR MST development. It is anticipated that this knowledge state assessment can enable the coordination of technology and analysis tool development discussions such that any knowledge gaps may be addressed. Sources of radionuclides considered in this report include releases originating both in-vessel and ex-vessel, including in-core fuel, primary sodium and cover gas cleanup systems, and spent fuel movement and handling. Transport phenomena affecting various release groups are identified and qualitatively discussed, including fuel pin and primary coolant retention, and behavior in the cover gas and

Development of dose calculation program (DBADOSE) incorporating alternative source term due to design basis accident

International Nuclear Information System (INIS)

Bae, Young Jig; Nam, Ki Mun; Lee, Yu Jong; Chung, Chan Young

2003-01-01

Source terms presented in TID-14844 and Regulatory Guide 1.4 have been used for radiological analysis of design basis accidents for licensing existing pressurized water reactor (PWR). However, more realistic and physically-based source term based on results of study and experiments for about 30 years after the publication of TID-14844 was developed and presented in NUREG-1465 published by U.S NRC in 1995. In addition, ICRP has revised dose concepts and criteria through the publication of ICRP-9, 26, 60 and recommended effective dose concepts rather than critical organ concept since the publication of ICRP-26. Accordingly, multipurpose computer program called DBADOSE incorporating alternative source terms in NUREG-1465 and effective dose concepts in ICRP-60 was developed. Comparison of results of DBADOSE with those of POSTDBA and STARDOSE was performed and verified and no significant difference and inaccuracy were found. DBADOSE will be used to evaluate accidental doses for licensing application according to the domestic laws that are expected to be revised in the near future

Guide for the preparation of applications for licenses for the use of sealed sources in portable gauging devices

International Nuclear Information System (INIS)

1985-01-01

The purpose of this regulatory guide is to provide assistance to applicants and licensees in preparing applications for new licenses, license amendments, and license renewals for the use of sealed sources in portable gauging devices. An example of a portable gauging device is a moisture-density gauge that contains a gamma-emitting sealed source, cesium-137, and a sealed neutron source, americium-242-beryllium

Categorisation of Practices and Sources- A Key Issue in Licensing Process

International Nuclear Information System (INIS)

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

2004-01-01

The analysis of a radioactive sources inventory in countries with a nuclear programme usually comprises nearly all possible man-made sources available today, from sources related to nuclear power plants to calibration sources used for educational purposes. The risk based licensing process of radiation sources and exposures is a demanding task which could be internationally harmonised by introducing sources and practice related categorisation. The detailed categorisation of radioisotopes, replacing [1], was recently published [2]. The activity ratio (A/D ratio) is used as a basic parameter which is proportional to a risk involved in a use of a radioisotope. Radioisotopes as well as related practices are categorised. No categorisation of ionising sources related to electrical apparatus producing ionising radiation without radioisotopes has been given in literature. In addition, licensees usually perform many different activities with a specific source, so the categorisation of practice should be done, based on a risk involved with a specific practice. The risk is related to the probability of a specific event as well as to the consequences of that event. It is strongly related to the categorisation of source. The main issues related to a licensing process of sources and practices are presented. The review of possible categorisation of radioisotopes and related practices is given and a proposal of a combined harmonised approach of categorisation of sources and practices, based on risk, is given. (Author) 19 refs

Licensing review process of the European Spallation Source (ESS) research facility

International Nuclear Information System (INIS)

Brewitz, Erica

2014-01-01

On 3 January 2012 a license application under the Radiation Protection Act (SFS, 1988b) for the European Spallation Source research facility was submitted to the Swedish Radiation Safety Authority. The European Spallation Source research facility will be the site of a new and quite unusual kind of neutron source, based on a large proton accelerator that bombards a heavy material with protons. The Swedish Radiation Safety Authority is now reviewing the application. (authors)

Single window for issuing licenses for export and import of ionizing radiation sources and transit of radioactive sources

International Nuclear Information System (INIS)

Sandev, T.; Stamenov, R.; Misevska, A.; Georgievska-Dimitrevski, B.; Angelovski, G.

2009-01-01

In this paper we present the electronic system for application and issuing licenses for export, import and transit of goods (EXIM), particularly for ionizing radiation sources, in the Republic of Macedonia. This system is a modern and helpful tool for simple issuing licenses, for establishing a unique database and it represents a harmonized system for exchanging information between the governmental, public and private legal persons in the Republic of Macedonia. (author)

Licensing of nuclear and radioactive installations in Peru

International Nuclear Information System (INIS)

Medina Gironzini, E.

1987-01-01

In Peru, the Regulation for Ionizing Radiation Sources is applied, which establishes the norms and procedures to follow in the nuclear and radioactive installations of the country in order to assure their correct operation as concerns to the nuclear safety and radiological protection, allowing the emission of the respective licenses. As for the nuclear facilities, this authorization includes the Previous License, the Construction License and the Operation License (provisional and definitive) and for radioactive facilities and equipment generating ionizing radiations: the Construction License and the Operation License. The personnel also require a license that can be an operator license (as for nuclear reactors) or a supervisor license (for nuclear and radioactive facilities). In spite of the above mentioned regulation and its long enforcement period, less than 10% of radioactive facilities in this country are licensed, due to different problems which will be solved in the medium term. (Author)

Perspectives on source terms based on early research and development

International Nuclear Information System (INIS)

Pressesky, A.J.

1985-07-01

This report presents an overview of the key documentation of the research and development programs relevant to the source term issue which were undertaken by the Atomic Energy Commission between 1950 and 1970. The source term is taken to be the amount, composition (physical and chemical), and timing of the projected release of radioactivity to the environment in the hypothetical event of a severe reactor accident in a light water reactor of the type currently being licensed, built and operated. The objective is to illuminate and provide perspectives on (a) the maturity of the technical data base and the analytical methodology, (b) the extent to which remaining conservatisms can be applied to compensate for uncertainties, (c) the purpose for which the technology and methodology will be used, and (d) the need to keep problems and uncertainties in proper perspective. Comments that can provide some context for the difficult programmatic choices to be made are included, and technical considerations that may be inadequately applied or neglected in some current source term calculations were studied. This review has not uncovered any significant technical considerations that have been omitted or are being inadequately treated in current source term analyses, except perhaps the contribution made to in-containment aerosols by coolant comminution upon escape at pressure from the reactor coolant system. 11 refs

Impact on future licensing

International Nuclear Information System (INIS)

Pasedag, W.F.; Postma, A.K.

1986-01-01

The TMI-2 accident has had a dramatic impact on the assessment of severe accidents, particularly on accident source term assumptions. TMI not only demonstrated that regulatory interest in severe accidents is appropriate, but also illustrated our limited understanding of fission product behaviour under degraded core conditions. The resulting reassessment of accident source terms has resulted in a concerted, world-wide research effort, which has produced a new source term estimation methodology. In order to assess the potential impact of the application of this methodology on regulatory requirements, a comparison with the approach used in licensing analyses is necessary. Such a comparison performed for the TMI-2 accident sequence, shows that differences in assumptions concerning accident progression far outweigh the differences in the methodology per se. In particular, the degree of conservatism incorporated into assumptions concerning operator action and containment response has over-riding influence on source term estimates. A major contribution to the impact of the new source term methodology on regulatory requirements, therefore, is its capability to provide the improved level of understanding necessary for reassessment of regulatory assumptions in this area

Evaluation of Terminated Nuclear Material Licenses

International Nuclear Information System (INIS)

Spencer, K.M.; Zeighami, E.A.

1999-01-01

This report presents the results of a six-year project that reviewed material licenses that had been terminated during the period from inception of licensing until approximately late-1994. The material licenses covered in the review project were Part 30, byproduct material licenses; Part 40, source material licenses; and Part 70, special nuclear material licenses. This report describes the methodology developed for the project, summarizes the findings of the license file inventory process, and describes the findings of the reviews or evaluations of the license files. The evaluation identified nuclear material use sites that need review of the licensing material or more direct follow-up of some type. The review process also identified licenses authorized to possess sealed sources for which there was incomplete or missing documentation of the fate of the sources

The licensing procedure under Atomic Energy Law

International Nuclear Information System (INIS)

Ronellenfitsch, M.

1983-01-01

This post-doctoral thesis of 1981 has been updated to include developments in this field up to the year 1983. The author discusses in detail all questions relating to the peaceful uses of nuclear energy in the Federal Republic of Germany, predominantly from the point of view of administrative law. He investigates nuclear energy and its contribution to electricity supplies with a view to other energy sources, renewable energy sources, alternative energy policies, nuclear fuel and the fuel cycle, development of the nuclear industry, nuclear power stations in operation, under construction, or in development. Following a survey of the nuclear controversy, both on the national and the international level, the author reviews the legal system and arising controversies in the Federal Republic of Germany, defining the purpose of this thesis to be the systematic analysis of the available legal instruments, in order to show structural deficiencies in the planning law relating to nuclear power stations, and thus reasons of ambiguities within the licensing procedure. The author studies the following terms and requirements: licensing requirements and licensability, the licensing method and scenario, the legal character of licences, their contents and effects within the stepwise procedure, and due publication. (HSCH) [de

Discovering Software License Constraints : Identifying a Binary’s Sources by Tracing Build Processes

NARCIS (Netherlands)

Van der Burg, S.; Davies, J.; Dolstra, E.; German, D.M.; Hemel, A.

2012-01-01

With the current proliferation of open source software components, intellectual property in general, and copyright law in particular, has become a critical non-functional requirement for software systems. A key problem in license compliance engineering is that the legal constraints on a product

Fission-product source terms

International Nuclear Information System (INIS)

Lorenz, R.A.

1981-01-01

This presentation consists of a review of fission-product source terms for light water reactor (LWR) fuel. A source term is the quantity of fission products released under specified conditions that can be used to calculate the consequences of the release. The source term usually defines release from breached fuel-rod cladding but could also describe release from the primary coolant system, the reactor containment shell, or the site boundary. The source term would be different for each locality, and the chemical and physical forms of the fission products could also differ

Shirley Basin Uranium Mill. Environmental report to accompany source material license application

International Nuclear Information System (INIS)

1975-12-01

This document summarizes all of the environmental monitoring conducted by Utah. This Environmental Report consequently supplements and updates the information presented in the Source Material License application of August 18, 1970 and the Final Environmental Statement (FES) of December 1974. Water and air quality, liquid waste management, soil/vegetation monitoring, and reclamation are covered

Systems engineering and the licensing of Small Modular Reactors

Energy Technology Data Exchange (ETDEWEB)

Kulesa, T., E-mail: tkulesa@us.ibm.com [IBM, Philidelphia, Pennsylvania (United States); Soderholm, K., E-mail: Kristiina.Soderholm@fortum.com [Fortum Power (Finland); Fechtelkotter, P., E-mail: pfech@us.ibm.com [IBM, Boston, Massacheusets (United States)

2014-07-01

Both global warming and the need for dependable sources of energy continue to make nuclear power generation an appealing option. But a history of cost overruns, project delays, and environmental disaster has pushed the industry to innovate and design a more flexible, scalable, and safe source of nuclear energy - the small modular reactor. Innovation in generation technology creates disruption in already complex licensing and regulatory processes. This paper discusses how the application of systems engineering and requirements management can help combat confusion, rework, and efficiency problems across the engineering and compliance life cycle. The paper is based on the PhD Dissertation 'Licensing Model Development for Small Modular Reactors (SMRs) - Focusing on Finnish Regulatory Framework', approved in 2013. The result of the study gives recommendations and tools to develop and optimize the licensing process for SMRs. The most important SMR-specific feature, in terms of licensing, is the modularity of the design. Here the modularity indicates multi-module SMR designs, which creates new challenges in the licensing process. Another feature impacting licensing feasibility is the plan to build many standardized power plants in series and use factory-fabricated modules to optimize the construction costs. SMR licensing challenges are under discussion in many international forums, such as World Nuclear Association Cooperation in Reactor Design Evaluation and Licensing Small Modular Reactor group (WNA CORDEL SMR) group and IAEA INPRO regulators' forum. This paper also presents an application of the new licensing process using Systems Engineering, Requirements Management, and Project Management practices and tools. (author)

Systems engineering and the licensing of Small Modular Reactors

International Nuclear Information System (INIS)

Kulesa, T.; Soderholm, K.; Fechtelkotter, P.

2014-01-01

Both global warming and the need for dependable sources of energy continue to make nuclear power generation an appealing option. But a history of cost overruns, project delays, and environmental disaster has pushed the industry to innovate and design a more flexible, scalable, and safe source of nuclear energy - the small modular reactor. Innovation in generation technology creates disruption in already complex licensing and regulatory processes. This paper discusses how the application of systems engineering and requirements management can help combat confusion, rework, and efficiency problems across the engineering and compliance life cycle. The paper is based on the PhD Dissertation 'Licensing Model Development for Small Modular Reactors (SMRs) - Focusing on Finnish Regulatory Framework', approved in 2013. The result of the study gives recommendations and tools to develop and optimize the licensing process for SMRs. The most important SMR-specific feature, in terms of licensing, is the modularity of the design. Here the modularity indicates multi-module SMR designs, which creates new challenges in the licensing process. Another feature impacting licensing feasibility is the plan to build many standardized power plants in series and use factory-fabricated modules to optimize the construction costs. SMR licensing challenges are under discussion in many international forums, such as World Nuclear Association Cooperation in Reactor Design Evaluation and Licensing Small Modular Reactor group (WNA CORDEL SMR) group and IAEA INPRO regulators' forum. This paper also presents an application of the new licensing process using Systems Engineering, Requirements Management, and Project Management practices and tools. (author)

A Mechanistic Source Term Calculation for a Metal Fuel Sodium Fast Reactor

Energy Technology Data Exchange (ETDEWEB)

Grabaskas, David; Bucknor, Matthew; Jerden, James

2017-06-26

A mechanistic source term (MST) calculation attempts to realistically assess the transport and release of radionuclides from a reactor system to the environment during a specific accident sequence. The U.S. Nuclear Regulatory Commission (NRC) has repeatedly stated its expectation that advanced reactor vendors will utilize an MST during the U.S. reactor licensing process. As part of a project to examine possible impediments to sodium fast reactor (SFR) licensing in the U.S., an analysis was conducted regarding the current capabilities to perform an MST for a metal fuel SFR. The purpose of the project was to identify and prioritize any gaps in current computational tools, and the associated database, for the accurate assessment of an MST. The results of the study demonstrate that an SFR MST is possible with current tools and data, but several gaps exist that may lead to possibly unacceptable levels of uncertainty, depending on the goals of the MST analysis.

Guide for the preparation of applications for licenses for the use of self-contained dry source-storage irradiators. Second proposed Revision 1

International Nuclear Information System (INIS)

Bassin, N.

1984-10-01

The purpose of this regulatory guide is to provide assistance to applicants and licensees in preparing applications for new licenses, license amendments, and license renewals for the use of self-contained dry source-storage irradiators. These irradiators are constructed so that the sealed sources and the material being irradiated are contained in a shielded volume and there is no external radiation beam during the use of the irradiator. The radioisotopes most commonly used for these irradiators are cobalt-60 and cesium-137

31 CFR 596.306 - License.

Science.gov (United States)

2010-07-01

... ASSETS CONTROL, DEPARTMENT OF THE TREASURY TERRORISM LIST GOVERNMENTS SANCTIONS REGULATIONS General Definitions § 596.306 License. Except as otherwise specified, the term license means any license or...

Design parameters and source terms: Volume 3, Source terms

International Nuclear Information System (INIS)

1987-10-01

The Design Parameters and Source Terms Document was prepared in accordance with DOE request and to provide data for the environmental impact study to be performed in the future for the Deaf Smith County, Texas site for a nuclear waste repository in salt. This document updates a previous unpublished report by Stearns Catalytic Corporation (SCC), entitled ''Design Parameters and Source Terms for a Two-Phase Repository in Salt,'' 1985, to the level of the Site Characterization Plan - Conceptual Design Report. The previous unpublished SCC Study identifies the data needs for the Environmental Assessment effort for seven possible Salt Repository sites. 11 refs., 9 tabs

Safety evaluation report related to the full-term operating license for San Onofre Nuclear Generating Station, Unit 1 (Docket No. 50-206)

International Nuclear Information System (INIS)

1991-07-01

The safety evaluation report for the full-term operating license application filed by the Southern California Edison Company and the San Diego Gas and Electric Company has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in San Diego County, California. The staff has evaluated the issues related to the conversion of the provisional operating license to a full-term operating license and concluded that the facility can continue to be operated without endangering the health and safety of the public following the license conversion. 43 refs., 3 figs., 3 tabs

License renewal

International Nuclear Information System (INIS)

Newberry, S.

1993-01-01

This article gives an overview of the process of license renewal for nuclear power plants. It explains what is meant by license renewal, the significance of license renewal, and goes over key elements involved in the process of license renewal. Those key elements are NRC requirements embodied in 10 CFR Part 54 (Reactor Safety) and 10 CFR Part 51 (Environmental Issues). In addition Industry Reports must be developed and reviewed. License renewal is essentially the process of applying for a 20 year extension to the original 40 year operating license granted for the plant. This is a very long term process, which involves a lot of preparation, and compliance with regulatory rules and guidelines. In general it is a process which is expected to begin when plants reach an operating lifetime of 20 years. It has provisions for allowing the public to become involved in the review process

76 FR 71082 - Strata Energy, Inc., Ross Uranium Recovery Project; New Source Material License Application...

Science.gov (United States)

2011-11-16

... NUCLEAR REGULATORY COMMISSION [Docket No. 40-9091; NRC-2011-0148] Strata Energy, Inc., Ross Uranium Recovery Project; New Source Material License Application; Notice of Intent To Prepare a... intent to prepare a supplemental environmental impact statement. SUMMARY: Strata Energy, Inc. (Strata...

Radiopharmaceutical licensing

International Nuclear Information System (INIS)

Mather, S.J.

1992-01-01

Recent health service legislation, and especially the loss of crown immunity has once again focussed attention on the arrangements for licensing of radiopharmaceuticals. The aim of the article is to describe in general terms the UK licensing system and in particular to provide guidance to those responsible for the supply of radiopharmaceuticals in hospitals. (author)

48 CFR 227.7203-4 - License rights.

Science.gov (United States)

2010-10-01

... Software and Computer Software Documentation 227.7203-4 License rights. (a) Grant of license. The... license, under an irrevocable license granted or obtained by the contractor which developed the software... granted to the Government. The scope of a computer software license is generally determined by the source...

NRC licensing requirements: DOD options

International Nuclear Information System (INIS)

Pike, W.J.; O'Reilly, P.D.

1982-09-01

This report describes the licensing process (both safety and environmental) that would apply if the Department of Defense (DOD) chooses to obtain licenses from the US Nuclear Regulatory Commission (NRC) for using nuclear energy for power and luminous sources. The specific nuclear energy sources being considered include: small or medium-size nuclear power reactors; radioisotopic thermoelectric generators with 90 Sr or 238 Pu; radioisotopic dynamic electric generators with 90 Sr or 238 Pu; and applications of radioisotopes for luminous sources (lights) with 3 H, 85 Kr, or 147 Pm. The steps of the licensing process are summarized in the following sections, with particular attention given to the schedule and level of effort necessary to support the process

31 CFR 596.309 - Specific license.

Science.gov (United States)

2010-07-01

... FOREIGN ASSETS CONTROL, DEPARTMENT OF THE TREASURY TERRORISM LIST GOVERNMENTS SANCTIONS REGULATIONS General Definitions § 596.309 Specific license. The term specific license means any license or...

31 CFR 596.305 - General license.

Science.gov (United States)

2010-07-01

... FOREIGN ASSETS CONTROL, DEPARTMENT OF THE TREASURY TERRORISM LIST GOVERNMENTS SANCTIONS REGULATIONS General Definitions § 596.305 General license. The term general license means any license or authorization...

FOSS License Selection and Code Management

OpenAIRE

Vescuso, Peter

2011-01-01

With nearly 2,000 free and open source software (FLOSS) licenses, software license proliferation¿ can be a major headache for software development organizations trying to speed development through software component reuse, as well as companies redistributing software packages as components of their products. Scope is one problem: from the Free Beer license to the GPL family of licenses to platform-specific licenses such as Apache and Eclipse, the number and variety of licenses make it difficu...

Toward a Mechanistic Source Term in Advanced Reactors: Characterization of Radionuclide Transport and Retention in a Sodium Cooled Fast Reactor

Energy Technology Data Exchange (ETDEWEB)

Brunett, Acacia J.; Bucknor, Matthew; Grabaskas, David

2016-04-17

A vital component of the U.S. reactor licensing process is an integrated safety analysis in which a source term representing the release of radionuclides during normal operation and accident sequences is analyzed. Historically, source term analyses have utilized bounding, deterministic assumptions regarding radionuclide release. However, advancements in technical capabilities and the knowledge state have enabled the development of more realistic and best-estimate retention and release models such that a mechanistic source term assessment can be expected to be a required component of future licensing of advanced reactors. Recently, as part of a Regulatory Technology Development Plan effort for sodium cooled fast reactors (SFRs), Argonne National Laboratory has investigated the current state of knowledge of potential source terms in an SFR via an extensive review of previous domestic experiments, accidents, and operation. As part of this work, the significant sources and transport processes of radionuclides in an SFR have been identified and characterized. This effort examines all stages of release and source term evolution, beginning with release from the fuel pin and ending with retention in containment. Radionuclide sources considered in this effort include releases originating both in-vessel (e.g. in-core fuel, primary sodium, cover gas cleanup system, etc.) and ex-vessel (e.g. spent fuel storage, handling, and movement). Releases resulting from a primary sodium fire are also considered as a potential source. For each release group, dominant transport phenomena are identified and qualitatively discussed. The key product of this effort was the development of concise, inclusive diagrams that illustrate the release and retention mechanisms at a high level, where unique schematics have been developed for in-vessel, ex-vessel and sodium fire releases. This review effort has also found that despite the substantial range of phenomena affecting radionuclide release, the

Design parameters and source terms: Volume 2, Source terms: Revision 0

International Nuclear Information System (INIS)

1987-09-01

The Design Parameters and Source Terms Document was prepared in accordance with DOE request and to provide data for the environmental impact study to be performed in the future for the Deaf Smith County, Texas site for a nuclear waste repository in salt. This document updates a previous unpublished report to the level of the Site Characterization Plan---Conceptual Design Report SCP-CDR. The previous study identifies the data needs for the Environmental Assessment effort for seven possible salt repository sites. Volume 2 contains tables of source terms

Design parameters and source terms: Volume 2, Source terms: Revision 0

International Nuclear Information System (INIS)

1987-10-01

The Design Parameters and Source Terms Document was prepared in accordance with DOE request and to provide data for the environmental impact study to be performed in the future for the Deaf Smith County, Texas site for a nuclear waste repository in salt. This document updates a previous unpublished report by Stearns Catalytic Corporation (SCC), entitled ''Design Parameters and Source Terms for a Two-Phase Repository Salt,'' 1985, to the level of the Site Characterization Plan - Conceptual Design Report. The previous unpublished SCC Study identifies the data needs for the Environmental Assessment effort for seven possible Salt Repository sites. 2 tabs

Long Term Operation R and D to Investigate the Technical Basis for Life Extension and License Renewal Decisions

International Nuclear Information System (INIS)

Gaertner, John

2012-01-01

Establishing an improved technical basis for long term operation of existing plants is a nuclear industry priority. The Electric Power Research Institute (EPRI) has responded with a comprehensive Long Term Operation (LTO) Program addressing this need for existing nuclear power plants world-wide. The program supports both the business decisions necessary to achieve high performance operation and the licensing requirements for operation beyond 60 years. The program selects its R and D priorities in a structured and objective way with much industry input to provide useful results for decisions in the 2014 to 2019 time frame. The program is highly collaborative with U.S. Department of Energy (DOE) and with EPRI-member utilities. The R and D portfolio includes materials aging (metals, concrete, and cables), modernization of information and control technology, enhanced safety analysis, advanced fuel design, demonstration plant activities, life cycle management, and identification of aging management program need for subsequent license renewal. The program has focussed stakeholders world-wide on the technical issues of long term operation, and it is on-track to provide practical results for life extension and license renewal decisions. (author)

Risk Assessment for Current and Projected Uses of Source Material Under a U.S. NRC General License and Exemption Request

International Nuclear Information System (INIS)

Smith, Michael A.; Napier, Bruce A.; Strom, Daniel J.; Short, Steven M.; Beatty, Cassandra V.; Stoker, Natasha F.; Newman, Teridee

2006-01-01

Source material is used under specific license, general license, and various exemptions from licensing requirements in 10 CFR Part 40. Because the Atomic Energy Act of 1946 focused on source material primarily in terms of its significance to the production of special nuclear material, the initial regulation of source material did not, apparently, give much emphasis to public health and safety. This emphasis on the production of special nuclear material continued in later modifications to the regulations. Because the last major update of these regulations was over 40 years ago (1961), the NRC is concerned that the current regulations for source materials may not be consistent with current health and safety regulations. Current industrial trends indicate a general decline in the use of thorium and uranium. Thorium was traditionally used in ceramics for refractory purposes but now is primarily used in scientific research, in a few electrical applications, as a chemical catalyst, and in optical lenses. Uranium, once popular in pigments and glazes, is now almost entirely limited to military applications that require special licensure and in scientific research. Due to high-disposal costs, increasingly stringent regulations, and public concerns related to the natural radioactivity of source material, industry is rapidly developing substitutes and alternate processes that do not involve the use of uranium and thorium. For these reasons, the downward trend in the use of source material is expected to continue. Researchers at Pacific Northwest National Laboratory (PNNL) identified how source materials meeting the exemption and general license requirements of 10 CFR 40.13(a), 40.13(b), and 40.22 are currently being used in industry and by the public. Based on the results of an extensive literature and internet search, few ?truly? new uses of source material were discovered that were not already considered in or represented by previous NRC analyses. Exceptions were (1) the

Current status of construction license of PEFP

International Nuclear Information System (INIS)

Kim, J. Y.; Cho, J. S.; Min, Y. S.; Nam, J. M.; Jeon, G. P.; Park, S. S.; Jo, J. H.; Song, I. T.

2012-01-01

Since 2010 August, PEFP(Proton Engineering Frontier Project)'s Proton Accelerator Research Center has been under construction so far. Generally, in advance of construction startup, many kinds of licenses should be acquired along with the types of construction works. To acquire a license in time, each item should meet the standard by the related regulation, including not only procedural but also content aspect. In the advent of internet era, electronic government system has been adopted in many governmental functions: So is the national construction license acquisition system. Owing to the system, both approval and documentation functions in licensing are integrated in online computer network which provide us simplification in process and easy accessibility to license data. However, aside from these construction licenses, other types of licenses still remain separately managed: Machinery, electric facilities, and so on. Moreover, all the licenses have the priority order and take legal term in processing. So, to avoid any time delay in license acquisition, we organized license hierarchy and found out the priority among them. Thereafter, according to their legal term in approval and acquisition, whole license acquisition schedule was arranged and we completed all the necessary licenses acquisition in time In this study, we summarize the current status of license acquisition on Proton Accelerator Research Center Construction, and manifest how they have been and will be managed systematically

Current status of construction license of PEFP

Energy Technology Data Exchange (ETDEWEB)

Kim, J. Y.; Cho, J. S.; Min, Y. S.; Nam, J. M.; Jeon, G. P.; Park, S. S.; Jo, J. H.; Song, I. T. [KAERI, Daejeon (Korea, Republic of)

2012-10-15

Since 2010 August, PEFP(Proton Engineering Frontier Project)'s Proton Accelerator Research Center has been under construction so far. Generally, in advance of construction startup, many kinds of licenses should be acquired along with the types of construction works. To acquire a license in time, each item should meet the standard by the related regulation, including not only procedural but also content aspect. In the advent of internet era, electronic government system has been adopted in many governmental functions: So is the national construction license acquisition system. Owing to the system, both approval and documentation functions in licensing are integrated in online computer network which provide us simplification in process and easy accessibility to license data. However, aside from these construction licenses, other types of licenses still remain separately managed: Machinery, electric facilities, and so on. Moreover, all the licenses have the priority order and take legal term in processing. So, to avoid any time delay in license acquisition, we organized license hierarchy and found out the priority among them. Thereafter, according to their legal term in approval and acquisition, whole license acquisition schedule was arranged and we completed all the necessary licenses acquisition in time In this study, we summarize the current status of license acquisition on Proton Accelerator Research Center Construction, and manifest how they have been and will be managed systematically.

Open Source Software: critical review of scientific literature and other sources

OpenAIRE

Querol del Amo, Marc

2007-01-01

This thesis presents the results of a survey of Open Source Licensing literature. It aims to assist the reader in choosing the best license for his/her business. For this reason, the content of this thesis can be divided into: (i) an open source licensing overview, (ii) the explication of the main features of the most popular open source licenses, (iii) the consequences of using one or another and (iv) the critical or controversial issues related to Open Source Licensing. Furthermore, at the ...

SOURCE TERMS FOR HLW GLASS CANISTERS

International Nuclear Information System (INIS)

J.S. Tang

2000-01-01

This calculation is prepared by the Monitored Geologic Repository (MGR) Waste Package Design Section. The objective of this calculation is to determine the source terms that include radionuclide inventory, decay heat, and radiation sources due to gamma rays and neutrons for the high-level radioactive waste (HLW) from the, West Valley Demonstration Project (WVDP), Savannah River Site (SRS), Hanford Site (HS), and Idaho National Engineering and Environmental Laboratory (INEEL). This calculation also determines the source terms of the canister containing the SRS HLW glass and immobilized plutonium. The scope of this calculation is limited to source terms for a time period out to one million years. The results of this calculation may be used to carry out performance assessment of the potential repository and to evaluate radiation environments surrounding the waste packages (WPs). This calculation was performed in accordance with the Development Plan ''Source Terms for HLW Glass Canisters'' (Ref. 7.24)

Freely Licensed and Open Source Pipelines for Art Based Film and Media Production

Directory of Open Access Journals (Sweden)

Anthony Whitehead

2009-08-01

Full Text Available Given the number of free/libre and open source licensed tools, and the number of "no cost" applications at the fingertips of the artist/animator/film developer today, the ability to "create what you will" is now an option for everyone. The advent of affordable media development tools has opened up the world of media production to those who were previously locked out of the Hollywood studio system. Proprietary software including Adobe Creative Suite, Autodesk?s Maya, Nuke, After Effects, Final Draft, and a litany of other necessary tools creates a financial wall so high that ?will? cannot overcome it alone. In this article, we examine a standard pipeline from a birds-eye-view for anyone with a will to create an Indie film. Without breaking the bank, the entire pipeline is achievable using F/LOSS tools and content that is available under a creative commons license. This allows high quality media development for all. In many cases, these same tools are being used by the Hollywood elite.

License renewal in the United States

International Nuclear Information System (INIS)

Brons, Jack

2002-01-01

Full text: Nuclear plants in the United States are licensed for 40 years, a length specified in the Atomic Energy Act of 1954, which laid out much of the regulatory basis for the commercial nuclear industry. The Act, however, made provision for license renewal. The original 40-year license period was chosen arbitrarily by the U.S. Congress because it was the typical period over which utilities recovered their investment in electricity generating plants. Nuclear plants, however, are subject to a rigorous program of Nuclear Regulatory Commission oversight, maintenance and equipment replacement. In effect, they must be in the same operating condition on the last day of their licenses as they were on the first. As the industry matured, it became apparent that there was no physical limitation on the continued operation of nuclear plants past 40 years. The industry turned its attention toward license renewal. When the issue was first raised, the NRC considered stringent process equivalent to seeking a new operating license for each plant. The complexity, length and cost of the process made it unlikely that many nuclear plants would seek license renewal. The nuclear industry worked successfully with NRC on the application of generic principles to license renewal, however, and in 1995, the NRC issued an efficient, tightly-focused rule that made license renewal a safe, viable option. To extend the operating license for a reactor, a company must demonstrate to the NRC that aging effects will be adequately managed during the renewal terms, thus ensuring equipment functionality. The rule allows licensees to apply for extensions of up to 20 years. The first license renewal application was filed in 1998 by the owner of the two-unit Calvert Cliffs plant. Shortly thereafter, an application was filed for the three-unit Oconee Nuclear Station. The NRC renewed the licenses for all five units in 2000, and since then, five more licenses have been renewed. The NRC has received 37

Interim report of the DOE [Department of Energy] Type B Investigation Group: Appendix D, Licensing correspondence

International Nuclear Information System (INIS)

Hultgren, R.O.

1990-07-01

Sometime between April 28, 1988 and June 5, 1988, a 22-inch long by 2.625-in. diameter doubly encapsulated cesium-137 irradiation source began leaking in the RSI-Decatur, Georgia, irradiation facility. By November 1988 when the source was isolated, between 7 and 8 curies (0.4 grams) leaked. This source was one of 1576 produced at Hanford to isolate the highly radioactive elements of wastes stored in single-walled tanks there. The capsule was designed for long term storage in a benign controlled pool environment on the Hanford reservation. An investigation was conducted to evaluate the cause of the incident, the management and administrative matters including leasing and licensing, the capsule design and manufacture, and the capsule qualification process. This appendix presents licensing correspondence

Calculation of source terms for NUREG-1150

International Nuclear Information System (INIS)

Breeding, R.J.; Williams, D.C.; Murfin, W.B.; Amos, C.N.; Helton, J.C.

1987-10-01

The source terms estimated for NUREG-1150 are generally based on the Source Term Code Package (STCP), but the actual source term calculations used in computing risk are performed by much smaller codes which are specific to each plant. This was done because the method of estimating the uncertainty in risk for NUREG-1150 requires hundreds of source term calculations for each accident sequence. This is clearly impossible with a large, detailed code like the STCP. The small plant-specific codes are based on simple algorithms and utilize adjustable parameters. The values of the parameters appearing in these codes are derived from the available STCP results. To determine the uncertainty in the estimation of the source terms, these parameters were varied as specified by an expert review group. This method was used to account for the uncertainties in the STCP results and the uncertainties in phenomena not considered by the STCP

47 CFR 97.5 - Station license required.

Science.gov (United States)

2010-10-01

.... (3) A military recreation station license grant. A military recreation station license grant may be... States military recreational premises where the station is situated. The person must not be a... the balance of the license term and the suspension is still in effect, suspended for the balance of...

The Situation in the Sphere of Consortia and Licensing of Information Sources in the Czech Republic

Directory of Open Access Journals (Sweden)

Jindrich Pilar

2001-07-01

Full Text Available The primary reason for founding „consortia“ (open associations of information services in the Czech Republic seems to be the possibility of obtaining access to extensive and highly expensive information sources under more convenient conditions than if each of the participating institutions had to organise this access separately.Licensing the access to information sources within special purpose association of information services is a relatively recent innovation in the Czech republic practice. It has started at the end of the nineties (except for the CrossFire and Chemical Abstracts system users. Therefore, there has not been created any methodology of selecting „suitable“ members for forming a consortium nor for selection of partners, information source producers yet.

License renewal process

International Nuclear Information System (INIS)

Fable, D.; Prah, M.; Vrankic, K.; Lebegner, J.

2004-01-01

The purpose of this paper is to provide information about license renewal process, as defined by Nuclear Regulatory Commission (NRC). The Atomic Energy Act and NRC regulations limit commercial power reactor licenses to an initial 40 years but also permit such licenses to be renewed. This original 40-year term for reactor licenses was based on economic and antitrust considerations not on limitations of nuclear technology. Due to this selected time period; however, some structures and components may have been engineered on the basis of an expected 40-year service life. The NRC has established a timely license renewal process and clear requirements codified in 10 CFR Part 51 and 10 CFR Part 54, that are needed to assure safe plant operation for extended plant life. The timely renewal of licenses for an additional 20 years, where appropriate to renew them, may be important to ensuring an adequate energy supply during the first half of the 21st Century. License renewal rests on the determination that currently operating plants continue to maintain adequate levels of safety, and over the plant's life, this level has been enhanced through maintenance of the licensing bases, with appropriate adjustments to address new information from industry operating experience. Additionally, NRC activities have provided ongoing assurance that the licensing bases will continue to provide an acceptable level of safety. This paper provides additional discussion of license renewal costs, as one of key elements in evaluation of license renewal justifiability. Including structure of costs, approximately value and two different approaches, conservative and typical. Current status and position of Nuclear Power Plant Krsko, related to license renewal process, will be briefly presented in this paper. NPP Krsko is designed based on NRC Regulations, so requirements from 10 CFR 51, and 10 CFR 54, are applicable to NPP Krsko, as well. Finally, this paper will give an overview of current status of

Subsurface Shielding Source Term Specification Calculation

International Nuclear Information System (INIS)

S.Su

2001-01-01

The purpose of this calculation is to establish appropriate and defensible waste-package radiation source terms for use in repository subsurface shielding design. This calculation supports the shielding design for the waste emplacement and retrieval system, and subsurface facility system. The objective is to identify the limiting waste package and specify its associated source terms including source strengths and energy spectra. Consistent with the Technical Work Plan for Subsurface Design Section FY 01 Work Activities (CRWMS M and O 2001, p. 15), the scope of work includes the following: (1) Review source terms generated by the Waste Package Department (WPD) for various waste forms and waste package types, and compile them for shielding-specific applications. (2) Determine acceptable waste package specific source terms for use in subsurface shielding design, using a reasonable and defensible methodology that is not unduly conservative. This calculation is associated with the engineering and design activity for the waste emplacement and retrieval system, and subsurface facility system. The technical work plan for this calculation is provided in CRWMS M and O 2001. Development and performance of this calculation conforms to the procedure, AP-3.12Q, Calculations

Benchmarking the New RESRAD-OFFSITE Source Term Model with DUST-MS and GoldSim - 13377

Energy Technology Data Exchange (ETDEWEB)

Cheng, J.J.; Kamboj, S.; Gnanapragasam, E.; Yu, C. [Argonne National Laboratory, Argonne, IL 60439 (United States)

2013-07-01

RESRAD-OFFSITE is a computer code developed by Argonne National Laboratory under the sponsorship of U.S. Department of Energy (DOE) and U.S. Nuclear Regulatory Commission (NRC). It is designed on the basis of RESRAD (onsite) code, a computer code designated by DOE and NRC for evaluating soil-contaminated sites for compliance with human health protection requirements pertaining to license termination or environmental remediation. RESRAD-OFFSITE has enhanced capabilities of modeling radionuclide transport to offsite locations and calculating potential radiation exposure to offsite receptors. Recently, a new source term model was incorporated into RESRAD-OFFSITE to enhance its capability further. This new source term model allows simulation of radionuclide releases from different waste forms, in addition to the soil sources originally considered in RESRAD (onsite) and RESRAD-OFFSITE codes. With this new source term model, a variety of applications can be achieved by using RESRAD-OFFSITE, including but not limited to, assessing the performance of radioactive waste disposal facilities. This paper presents the comparison of radionuclide release rates calculated by the new source term model of RESRAD-OFFSITE versus those calculated by DUST-MS and GoldSim, respectively. The focus of comparison is on the release rates of radionuclides from the bottom of the contaminated zone that was assumed to contain radioactive source materials buried in soil. The transport of released contaminants outside of the primary contaminated zone is beyond the scope of this paper. Overall, the agreement between the RESRAD-OFFSITE results and the DUST-MS and GoldSim results is fairly good, with all three codes predicting identical or similar radionuclide release profiles over time. Numerical dispersion in the DUST-MS and GoldSim results was identified as potentially contributing to the disagreement in the release rates. In general, greater discrepancy in the release rates was found for short

Benchmarking the New RESRAD-OFFSITE Source Term Model with DUST-MS and GoldSim - 13377

International Nuclear Information System (INIS)

Cheng, J.J.; Kamboj, S.; Gnanapragasam, E.; Yu, C.

2013-01-01

RESRAD-OFFSITE is a computer code developed by Argonne National Laboratory under the sponsorship of U.S. Department of Energy (DOE) and U.S. Nuclear Regulatory Commission (NRC). It is designed on the basis of RESRAD (onsite) code, a computer code designated by DOE and NRC for evaluating soil-contaminated sites for compliance with human health protection requirements pertaining to license termination or environmental remediation. RESRAD-OFFSITE has enhanced capabilities of modeling radionuclide transport to offsite locations and calculating potential radiation exposure to offsite receptors. Recently, a new source term model was incorporated into RESRAD-OFFSITE to enhance its capability further. This new source term model allows simulation of radionuclide releases from different waste forms, in addition to the soil sources originally considered in RESRAD (onsite) and RESRAD-OFFSITE codes. With this new source term model, a variety of applications can be achieved by using RESRAD-OFFSITE, including but not limited to, assessing the performance of radioactive waste disposal facilities. This paper presents the comparison of radionuclide release rates calculated by the new source term model of RESRAD-OFFSITE versus those calculated by DUST-MS and GoldSim, respectively. The focus of comparison is on the release rates of radionuclides from the bottom of the contaminated zone that was assumed to contain radioactive source materials buried in soil. The transport of released contaminants outside of the primary contaminated zone is beyond the scope of this paper. Overall, the agreement between the RESRAD-OFFSITE results and the DUST-MS and GoldSim results is fairly good, with all three codes predicting identical or similar radionuclide release profiles over time. Numerical dispersion in the DUST-MS and GoldSim results was identified as potentially contributing to the disagreement in the release rates. In general, greater discrepancy in the release rates was found for short

ITER Safety Task NID-5A, Subtask 1-1: Source terms and energies - initial tritium source terms. Final report

International Nuclear Information System (INIS)

Fong, C.; Kalyanam, K.M.; Tanaka, M.R.; Sood, S.; Natalizio, A.; Delisle, M.

1995-02-01

The overall objective of the Early Safety and Environmental Characterization Study (ESECS) is to assess the environmental impact of tritium using appropriate assumptions on a hypothetical site for ITER, having the r eference s ite characteristics as proposed by the JCT. The objective of this work under the above subtask 1-1, NID-5a, is to determine environmental source terms (i.e., process source term x containment release fraction) for the fuel cycle and cooling systems. The work is based on inventories and process source terms (i.e., inventory x mobilization fraction), provided by others (under Task NID 3b). The results of this work form the basis for the determination, by others, of the off-site dose (i.e., environmental source term x dose/release ratio). For the determination of the environmental source terms, the TMAP4 code has been utilized (ref 1). This code is approved by ITER for safety assessment. Volume 3 is a compilation of appendices giving detailed results of the study

ITER Safety Task NID-5A, Subtask 1-1: Source terms and energies - initial tritium source terms. Final report

International Nuclear Information System (INIS)

Fong, C.; Kalyanam, K.M.; Tanaka, M.R.; Sood, S.; Natalizio, A.; Delisle, M.

1995-02-01

The overall objective of the Early Safety and Environmental Characterization Study (ESECS) is to assess the environmental impact of tritium using appropriate assumptions on a hypothetical site for ITER, having the r eference s ite characteristics as proposed by the JCT. The objective of this work under the above subtask 1-1, NID-5a, is to determine environmental source terms (i.e., process source term x containment release fraction) for the fuel cycle and cooling systems. The work is based on inventories and process source terms (i.e., inventory x mobilization fraction), provided by others (under Task NID 3b). The results of this work form the basis for the determination, by others, of the off-site dose (i.e., environmental source term x dose/release ratio). For the determination of the environmental source terms, the TMAP4 code has been utilized (ref 1). This code is approved by ITER for safety assessment. 6 refs

78 FR 16876 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

Science.gov (United States)

2013-03-19

... intervene shall be filed in accordance with the Commission's ``Rules of Practice for Domestic Licensing... proposes to replace the VHS with an onsite diesel generator as the AAC power source providing this... power source (the VHS) with an additional onsite AAC power source (diesel generator). This equipment can...

A comparison of licensed and un-licensed artisanal and small-scale gold miners (ASGM) in terms of socio-demographics, work profiles, and injury rates.

Science.gov (United States)

Calys-Tagoe, Benedict N L; Clarke, Edith; Robins, Thomas; Basu, Niladri

2017-11-06

Artisanal and small-scale gold mining (ASGM) represents one of the most hazardous work environments. While formalization of this sector has been suggested (e.g., Minamata Convention) as a means to improve working conditions, we are unaware of empirical evidence that supports this notion. This study aimed to compare sociodemographic profiles, work profiles, and injury rates among miners working in licensed versus un-licensed ASGM sites. In the Tarkwa mining region of Ghana, 404 small-scale miners were recruited in 2014 and interviewed regarding their occupational injury experiences over the preceding 10 years. Workers were drawn from 9 mining sites, of which 5 were licensed and 4 were not licensed. Sociodemographic characteristics of miners from the two groups were relatively similar. Those currently working in an un-licensed mine have spent more time in the ASGM sector than those currently working in a licensed mine (94 vs. 70 months). Miners working in an un-licensed site tended to experience more injury episodes (e.g., 26% vs. 8% had 3 or more injury events) and not use personal protective equipment during the time of an injury (92% indicated to not using vs. 73%) when compared to miners working in a licensed site. A total of 121 injury episodes were recorded for 2245 person years of ASGM work. The injury rate for those working in un-licensed mines was 5.9 per 100 person years (59 injuries in 995 person years) versus 5.0 (62 injuries in 1250 person-years) in the licensed mines. When focusing on the male miners, there was a significant difference in injury rates between those working in a licensed mine (4.2 per 100 person years) versus an un-licensed mine (6.1 per 100 person years). These findings advance our understanding of injuries amongst ASGM workers, and help identify important differences in socio-demographics, work profiles, and injury rates between miners working in a licensed versus and un-licensed site. The findings suggest that certain working

ITER Safety Task NID-5A, Subtask 1-1: Source terms and energies - initial tritium source terms. Final report

International Nuclear Information System (INIS)

Fong, C.; Kalyanam, K.M.; Tanaka, M.R.; Sood, S.; Natalizio, A.; Delisle, M.

1995-02-01

The overall objective of the Early Safety and Environmental Characterization Study (ESECS) is to assess the environmental impact of tritium using appropriate assumptions on a hypothetical site for ITER, having the r eference s ite characteristics as proposed by the JCT. The objective of this work under the above subtask 1-1, NID-5a, is to determine environmental source terms (i.e., process source term x containment release fraction) for the fuel cycle and cooling systems. The work is based on inventories and process source terms (i.e., inventory x mobilization fraction), provided by others (under Task NID 3b). The results of this work form the basis for the determination, by others, of the off-site dose (i.e., environmental source term x dose/release ratio). For the determination of the environmental source terms, the TMAP4 code has been utilized (ref 1). This code is approved by ITER for safety assessment. Volume 2 is a compilation of appendices giving detailed results of the study. 5 figs

Aerosol behavior and light water reactor source terms

International Nuclear Information System (INIS)

Abbey, F.; Schikarski, W.O.

1988-01-01

The major developments in nuclear aerosol modeling following the accident to pressurized water reactor Unit 2 at Three Mile Island are briefly reviewed and the state of the art summarized. The importance and implications of these developments for severe accident source terms for light water reactors are then discussed in general terms. The treatment is not aimed at identifying specific source term values but is intended rather to illustrate trends, to assess the adequacy of the understanding of major aspects of aerosol behavior for source term prediction, and demonstrate in qualitative terms the effect of various aspects of reactor design. Areas where improved understanding of aerosol behavior might lead to further reductions in current source terms predictions are also considered

Licensing experience of the HTR-10 test reactor

International Nuclear Information System (INIS)

Sun, Y.; Xu, Y.

1996-01-01

A 10MW high temperature gas-cooled test reactor (HTR-10) is now being projected by the Institute of Nuclear Energy Technology within China's National High Technology Programme. The Construction Permit of HTR-10 was issued by the Chinese nuclear licensing authority around the end of 1994 after a period of about one year of safety review of the reactor design. HTR-10 is the first high temperature gas-cooled reactor (HTGR) to be constructed in China. The purpose of this test reactor project is to test and demonstrate the technology and safety features of the advanced modular high temperature reactor design. The reactor uses spherical fuel elements with coated fuel particles. The reactor unit and the steam generator unit are arranged in a ''side-by-side'' way. Maximum fuel temperature under the accident condition of a complete loss of coolant is limited to values much lower than the safety limit set for the fuel element. Since the philosophy of the technical and safety design of HTR-10 comes from the high temperature modular reactor design, the reactor is also called the Test Module. HTR-10 represents among others also a licensing challenge. On the one side, it is the first helium reactor in China, and there are less licensing experiences both for the regulator and for the designer. On the other side, the reactor design incorporates many advanced design features in the direction of passive or inherent safety, and it is presently a world-wide issue how to treat properly the passive or inherent safety design features in the licensing safety review. In this presentation, the licensing criteria of HTR-10 are discussed. The organization and activities of the safety review for the construction permit licensing are described. Some of the main safety issues in the licensing procedure are addressed. Among these are, for example, fuel element behaviour, source term, safety classification of systems and components, containment design. The licensing experiences of HTR-10 are of

A comparison of licensed and un-licensed artisanal and small-scale gold miners (ASGM in terms of socio-demographics, work profiles, and injury rates

Directory of Open Access Journals (Sweden)

Benedict N. L. Calys-Tagoe

2017-11-01

Full Text Available Abstract Background Artisanal and small-scale gold mining (ASGM represents one of the most hazardous work environments. While formalization of this sector has been suggested (e.g., Minamata Convention as a means to improve working conditions, we are unaware of empirical evidence that supports this notion. This study aimed to compare sociodemographic profiles, work profiles, and injury rates among miners working in licensed versus un-licensed ASGM sites. Methods In the Tarkwa mining region of Ghana, 404 small-scale miners were recruited in 2014 and interviewed regarding their occupational injury experiences over the preceding 10 years. Workers were drawn from 9 mining sites, of which 5 were licensed and 4 were not licensed. Results Sociodemographic characteristics of miners from the two groups were relatively similar. Those currently working in an un-licensed mine have spent more time in the ASGM sector than those currently working in a licensed mine (94 vs. 70 months. Miners working in an un-licensed site tended to experience more injury episodes (e.g., 26% vs. 8% had 3 or more injury events and not use personal protective equipment during the time of an injury (92% indicated to not using vs. 73% when compared to miners working in a licensed site. A total of 121 injury episodes were recorded for 2245 person years of ASGM work. The injury rate for those working in un-licensed mines was 5.9 per 100 person years (59 injuries in 995 person years versus 5.0 (62 injuries in 1250 person-years in the licensed mines. When focusing on the male miners, there was a significant difference in injury rates between those working in a licensed mine (4.2 per 100 person years versus an un-licensed mine (6.1 per 100 person years. Conclusions These findings advance our understanding of injuries amongst ASGM workers, and help identify important differences in socio-demographics, work profiles, and injury rates between miners working in a licensed versus and un-licensed

Practical issues in structuring seismic licensing and acquisition agreements

International Nuclear Information System (INIS)

Lawrence, M.A.

1999-01-01

Some issues facing the geophysical industry in the area of licensing and acquisition agreements are discussed, focusing on a very large business segment of the industry called 'non-exclusive' seismic data (commonly referred to as SPEC data). A historical perspective of the industry in the Gulf of Mexico is presented, highlighting some important aspects of data licenses. The benefits of licensing three-dimensional data to the exploration industry include: (1) economy of scale, (2) 3-D is more affordable, (3) reduced barriers to entry by independents, and (4) improved success rates and reduced risk. A list of 'SPEC' companies in the Gulf of Mexico is provided and the data licensing process is outlined. There are two basic types of seismic data use licenses. The first is for a single, one-time transaction, and the other (which is more prevalent), covers multiple use licenses contemplated over a period of time. This paper briefly outlined the meaning of some important terms usually found in a license agreement, among them ownership, rights of licensee, term, disclosure to third parties, and transfer. International 'SPEC' programs and the requirements for a successful 'SPEC' program are described. The requirements include: a stable host government, reliable, competitive system of concession offerings, long term scheduled offerings, clear, consistent, and acceptable concession terms to oil and gas companies, and consistent, fair and timely method of evaluating bids and awarding concessions. 001CA9901758

36 CFR 264.3 - Licensing for commercial use.

Science.gov (United States)

2010-07-01

... 36 Parks, Forests, and Public Property 2 2010-07-01 2010-07-01 false Licensing for commercial use... PROPERTY MANAGEMENT Official Forest Service Insignia § 264.3 Licensing for commercial use. (a) Each commercial license granted for the use of the insignia or likeness thereof shall contain the following terms...

The USNCR license renewal process

International Nuclear Information System (INIS)

Kuo, Pao-Tsin

2002-01-01

The US Congress promulgated a law in 1954, entitled 'Atomic Energy Act'. This Act states that operating licenses for commercial nuclear power plants are limited to a fixed term of 40 years, but they may be renewed for a period not to exceed 20 years. The terms were established mainly for economic considerations, not based on technical limitations. The U.S. Nuclear Regulatory Commission (USNRC) published the license renewal rule, Title 10 of the Code of Federal Regulations, Part 54 (10 CFR Part 54), in December, 1991. The rule has since been amended in May, 1995. The underlying principle of the rule is that the regulatory process is adequate for ensuring safety of operating plants. The regulatory process includes NRC's issuance of Orders, Bulletins, Generic Letters, and Information Notices, as well as a number of special inspections in addition to the continuous oversight and routine inspection activities performed by on-site inspectors. Because of this comprehensive regulatory process, compilation of the current license basis or re-verification of the current licensing basis is not considered necessary for a license renewal review. The USNRC also determined on the basis of the findings of its research programs that active structures and components are well maintained by the existing programs. Therefore, the focus of the license renewal review is on passive, long-lived structures and components and on time-limited ageing analyses. The time-limited ageing analyses are for those structures and components which were originally designed to a 40 year service life

Source Term Analysis for the Nuclear Power Station Goesgen-Daeniken; Quelltermanalysen fuer das Kernkraftwerk Goesgen-Daeniken

Energy Technology Data Exchange (ETDEWEB)

Hosemann, J.P.; Megaritis, G.; Guentay, S.; Hirschmann, H.; Luebbesmeyer, D.; Lieber, K.; Jaeckel, B.; Birchley, J.; Duijvestijn, G

2001-08-01

Analyses are performed for three accident scenarios postulated to occur in the Goesgen Nuclear Power Plant, a 900 MWe Pressurised Water Reactor of Siemens design. The scenarios investigated comprise a Station Blackout and two separate cases of small break loss-of-coolant accident which lead, respectively, to high, intermediate and low pressure conditions in the reactor system. In each case the accident assumptions are highly pessimistic, so that the sequences span a large range of plant states and a damage phenomena. Thus the plant is evaluated for a diversity of potential safety challenges. A suite of analysis tools are used to examine the reactor coolant system response, the core heat-up, melting, fission product release from the reactor system, the transport and chemical behaviour of those fission products in the containment building, and the release of radioactivity (source term) to the environment. Comparison with reference values used by the licensing authority shows that the use of modern analysis tools and current knowledge can provide substantial reduction in the estimated source term. Of particular interest are insights gained from the analyses which indicate opportunities for operators to reduce or forestall the release. (author)

Mechanistic facility safety and source term analysis

International Nuclear Information System (INIS)

PLYS, M.G.

1999-01-01

A PC-based computer program was created for facility safety and source term analysis at Hanford The program has been successfully applied to mechanistic prediction of source terms from chemical reactions in underground storage tanks, hydrogen combustion in double contained receiver tanks, and proccss evaluation including the potential for runaway reactions in spent nuclear fuel processing. Model features include user-defined facility room, flow path geometry, and heat conductors, user-defined non-ideal vapor and aerosol species, pressure- and density-driven gas flows, aerosol transport and deposition, and structure to accommodate facility-specific source terms. Example applications are presented here

Some practical implications of source term reassessment

International Nuclear Information System (INIS)

1988-03-01

This report provides a brief summary of the current knowledge of severe accident source terms and suggests how this knowledge might be applied to a number of specific aspects of reactor safety. In preparing the report, consideration has been restricted to source term issues relating to light water reactors (LWRs). Consideration has also generally been restricted to the consequences of hypothetical severe accidents rather than their probability of occurrence, although it is recognized that, in the practical application of source term research, it is necessary to take account of probability as well as consequences. The specific areas identified were as follows: Exploration of the new insights that are available into the management of severe accidents; Investigating the impact of source term research on emergency planning and response; Assessing the possibilities which exist in present reactor designs for preventing or mitigating the consequences of severe accidents and how these might be used effectively; Exploring the need for backfitting and assessing the implications of source term research for future designs; and Improving the quantification of the radiological consequences of hypothetical severe accidents for probabilistic safety assessments (PSAs) and informing the public about the realistic risks associated with nuclear power plants. 7 refs

License - Gclust Server | LSDB Archive [Life Science Database Archive metadata

Lifescience Database Archive (English)

Full Text Available List Contact us Gclust Server License License to Use This Database Last updated : 2009/09/14 You may use this database...scribed below. The Standard License specifies the license terms regarding the use of this database and the r...equirements you must follow in using this database. The Additional License specif...icense. Standard License The Standard License for this database is the license specified in the Creative Com...mons Attribution-Share Alike 2.1 Japan . If you use data from this database, plea

Current regulatory and licensing status for byproduct sources, facilities and applications

International Nuclear Information System (INIS)

Tingey, G.L.; Jensen, G.A.; Hazelton, R.F.

1985-02-01

Public use of nuclear byproducts, especially radioactive isotopes, will require approval by various regulatory agencies. Use of cesium-137 as an irradiation source for sterilizing medical products will require US Nuclear Regulatory Commission (NRC) approval. Two applications have been filed with NRC, and approval is expected soon. Widespread use of irradiation for food products depends on a favorable ruling by the Food and Drug Administration (FDA). A ruling is pending that would permit irradiation of fruits and vegetables up to 100 krad. NRC also controls the use of isotopes in remote power generators, but little regulatory action has been required in recent years. Recent development of radioluminescent (RL) lighting for runway lights has led to interest by commercial manufacturers. At the present time, a license has been issued to at least one manufacturer for sale of tritium-powered runway lights. 28 refs., 1 fig

Revised accident source terms and control room habitability

International Nuclear Information System (INIS)

Lahti, G.P.; Hubner, R.S.; Johnson, W.J.; Schwartz, B.C.

1993-01-01

In April 1992, the NRC staff presented to the Commissioners the draft NUREG open-quotes Revised Accident Source Terms for Light-Water Nuclear Power Plants.close quotes This document is the culmination of more than ten years of NRC-sponsored research and represents the first change in the NRC's position on source terms since TID-14844 was issued in 1962. The purpose of this paper is to investigate the impact of the revised source terms on the current approach to analyzing control room habitability as required by 10 CFR 50. Sample calculations are presented that identify aspects of the model requiring clarification before the implementation of the revised source terms. 6 refs., 4 tabs

10 CFR 81.32 - Terms of exclusive license grant.

Science.gov (United States)

2010-01-01

... Commission a written notice of the Commission's intention to modify or revoke the license, and the licensee... other books, documents, papers, and records pertaining to such suit. If, as a result of any such...

Analýza licencí typu open source a jejich použití v praxi

OpenAIRE

Neumann, Martin

2010-01-01

The aim of this bachelor thesis is to analyse the most commonly used open source/free software licenses. After brief introduction to the history and defining related terms, there is a classification of licenses by the method of distribution. An analysis of the most common licenses is brought in, followed by presentation of the main points of licensing conditions in the Czech language. The main purpose of this work is to create a transparent methodology for selecting the proper licenses accord...

Some problems in the categorization of source terms

International Nuclear Information System (INIS)

Abbey, F.; Dunbar, I.H.; Hayns, M.R.; Nixon, W.

1985-01-01

In recent years techniques for calculating source terms have been considerably improved. It would be unfortunate if the new information were to be blurred by the use of old schemes for the categorization of source terms. In the past categorization schemes have been devised without the question of the general principles of categorization and the available options being addressed explicitly. In this paper these principles are set out, providing a framework within which categorization schemes used in past probabilistic risk assessments and possible future improvements are discussed. In particular the use of input from scoping consequence calculations in deciding how to group source terms, and the question of how modelling uncertainties may be expressed as uncertainties in a final category source terms are considered

18 CFR 4.106 - Standard terms and conditions of case-specific exemption from licensing.

Science.gov (United States)

2010-04-01

... LICENSES, PERMITS, EXEMPTIONS, AND DETERMINATION OF PROJECT COSTS Exemption of Small Hydroelectric Power... licensing. Any case-specific exemption from licensing granted for a small hydroelectric power project is... falsehoods were made by or on behalf of the applicant. (h) Article 8. Any exempted small hydroelectric power...

Regulatory Technology Development Plan - Sodium Fast Reactor. Mechanistic Source Term - Metal Fuel Radionuclide Release

International Nuclear Information System (INIS)

Grabaskas, David; Bucknor, Matthew; Jerden, James

2016-01-01

The development of an accurate and defensible mechanistic source term will be vital for the future licensing efforts of metal fuel, pool-type sodium fast reactors. To assist in the creation of a comprehensive mechanistic source term, the current effort sought to estimate the release fraction of radionuclides from metal fuel pins to the primary sodium coolant during fuel pin failures at a variety of temperature conditions. These release estimates were based on the findings of an extensive literature search, which reviewed past experimentation and reactor fuel damage accidents. Data sources for each radionuclide of interest were reviewed to establish release fractions, along with possible release dependencies, and the corresponding uncertainty levels. Although the current knowledge base is substantial, and radionuclide release fractions were established for the elements deemed important for the determination of offsite consequences following a reactor accident, gaps were found pertaining to several radionuclides. First, there is uncertainty regarding the transport behavior of several radionuclides (iodine, barium, strontium, tellurium, and europium) during metal fuel irradiation to high burnup levels. The migration of these radionuclides within the fuel matrix and bond sodium region can greatly affect their release during pin failure incidents. Post-irradiation examination of existing high burnup metal fuel can likely resolve this knowledge gap. Second, data regarding the radionuclide release from molten high burnup metal fuel in sodium is sparse, which makes the assessment of radionuclide release from fuel melting accidents at high fuel burnup levels difficult. This gap could be addressed through fuel melting experimentation with samples from the existing high burnup metal fuel inventory.

Regulatory Technology Development Plan - Sodium Fast Reactor. Mechanistic Source Term - Metal Fuel Radionuclide Release

Energy Technology Data Exchange (ETDEWEB)

Grabaskas, David [Argonne National Lab. (ANL), Argonne, IL (United States); Bucknor, Matthew [Argonne National Lab. (ANL), Argonne, IL (United States); Jerden, James [Argonne National Lab. (ANL), Argonne, IL (United States)

2016-02-01

The development of an accurate and defensible mechanistic source term will be vital for the future licensing efforts of metal fuel, pool-type sodium fast reactors. To assist in the creation of a comprehensive mechanistic source term, the current effort sought to estimate the release fraction of radionuclides from metal fuel pins to the primary sodium coolant during fuel pin failures at a variety of temperature conditions. These release estimates were based on the findings of an extensive literature search, which reviewed past experimentation and reactor fuel damage accidents. Data sources for each radionuclide of interest were reviewed to establish release fractions, along with possible release dependencies, and the corresponding uncertainty levels. Although the current knowledge base is substantial, and radionuclide release fractions were established for the elements deemed important for the determination of offsite consequences following a reactor accident, gaps were found pertaining to several radionuclides. First, there is uncertainty regarding the transport behavior of several radionuclides (iodine, barium, strontium, tellurium, and europium) during metal fuel irradiation to high burnup levels. The migration of these radionuclides within the fuel matrix and bond sodium region can greatly affect their release during pin failure incidents. Post-irradiation examination of existing high burnup metal fuel can likely resolve this knowledge gap. Second, data regarding the radionuclide release from molten high burnup metal fuel in sodium is sparse, which makes the assessment of radionuclide release from fuel melting accidents at high fuel burnup levels difficult. This gap could be addressed through fuel melting experimentation with samples from the existing high burnup metal fuel inventory.

License - AcEST | LSDB Archive [Life Science Database Archive metadata

Lifescience Database Archive (English)

Full Text Available List Contact us AcEST License to Use This Database Last updated : 2010/02/15 You may use this database in co...he Standard License specifies the license terms regarding the use of this database and the requirements you ...must follow in using this database. The Additional License specifies those items ... License The Standard License for this database is the license specified in the Creative Commons Attribution...-Share Alike 2.1 Japan . If you use data from this database, please be sure attribute this database

Regulatory Technology Development Plan - Sodium Fast Reactor. Mechanistic Source Term - Trial Calculation. Work Plan

International Nuclear Information System (INIS)

Grabaskas, David; Bucknor, Matthew; Jerden, James; Brunett, Acacia J.

2016-01-01

The overall objective of the SFR Regulatory Technology Development Plan (RTDP) effort is to identify and address potential impediments to the SFR regulatory licensing process. In FY14, an analysis by Argonne identified the development of an SFR-specific MST methodology as an existing licensing gap with high regulatory importance and a potentially long lead-time to closure. This work was followed by an initial examination of the current state-of-knowledge regarding SFR source term development (ANLART-3), which reported several potential gaps. Among these were the potential inadequacies of current computational tools to properly model and assess the transport and retention of radionuclides during a metal fuel pool-type SFR core damage incident. The objective of the current work is to determine the adequacy of existing computational tools, and the associated knowledge database, for the calculation of an SFR MST. To accomplish this task, a trial MST calculation will be performed using available computational tools to establish their limitations with regard to relevant radionuclide release/retention/transport phenomena. The application of existing modeling tools will provide a definitive test to assess their suitability for an SFR MST calculation, while also identifying potential gaps in the current knowledge base and providing insight into open issues regarding regulatory criteria/requirements. The findings of this analysis will assist in determining future research and development needs.

NUMARC view of license renewal criteria

International Nuclear Information System (INIS)

Edwards, D.W.

1989-01-01

The Atomic Energy Act and the implementing regulations of the US Nuclear Regulatory Commission (NRC) permit the renewal of nuclear plant operating licenses upon expiration of their 40-year license term. However, the regulatory process by which license renewal may be accomplished and the requirements for the scope and content of renewal applications are yet to be established. On August 29, 1988, the NRC published an Advanced Notice of Proposed Rulemaking regarding the subject of license renewal. This Advanced Notice and the NUREG which it references, NUREG-1317, Regulatory Options for Nuclear Plant License Renewal, provide the most recent regulatory thought on this issue. The basic issue addressed by NUREG-1317 is the definition of an adequate licensing basis for the renewal of a plant license. The report contemplates three alternatives in this regard. This paper discusses each of these three proposals. The NUMARC NUPLEX Working Group endorses a license renewal process based on a plant's current licensing basis along with an evaluation of the pertinent components, systems, and structures affected by age-related degradation. The NUMARC NUPLEX Working group believes that an appropriate scope for NRC review of the license renewal application should focus on those safety-significant structures systems, and components subject to significant age-related degradation that are not subject to existing recognized effective replacement, refurbishment, or inspection programs. The paper also briefly discusses NUMARC's view of the role of the Backfit Rule in the license renewal process

License - Open TG-GATEs | LSDB Archive [Life Science Database Archive metadata

Lifescience Database Archive (English)

Full Text Available List Contact us Open TG-GATEs License License to Use This Database Last updated : 2012/05/24 You may use this database...scribed below. The Standard License specifies the license terms regarding the use of this database and the r...equirements you must follow in using this database. The Additional License specif...icense. Standard License The Standard License for this database is the license specified in the Creative Com...mons Attribution-Share Alike 2.1 Japan . If you use data from this database, plea

License - TMFunction | LSDB Archive [Life Science Database Archive metadata

Lifescience Database Archive (English)

Full Text Available List Contact us TMFunction License License to Use This Database Last updated : 2017/01/23 You may use this database...e license terms regarding the use of this database and the requirements you must follow in using this database.... The license for this database is specified in the Creative Commons Attributio...n-Share Alike 4.0 International . If you use data from this database, please be sure attribute this database...ion-Share Alike 4.0 International is found here . With regard to this database, you are licensed to: freely

Effect of an Education Presentation On the Knowledge and Awareness of Urinary Tract Infection among Non-Licensed and Licensed Health Care Workers in Long-Term Care Facilities.

Science.gov (United States)

Freeman-Jobson, Jennifer H; Rogers, Jamie L; Ward-Smith, Peggy

2016-01-01

This article presents the findings of a pre-test, post-test quality improvement project that describes the change in knowledge from prior to and following an evidence-based education presentation. The presentation addressed the clinical symptoms, diagnostic processes, interventions, and responsibilities of licensed and unlicensed health care workers employed in long-term care facilities related to prevention and detection of non-catheter-related urinary tract infections. Results indicate that the education presentation improved knowledge in specific.

Chernobyl source term estimation

International Nuclear Information System (INIS)

Gudiksen, P.H.; Harvey, T.F.; Lange, R.

1990-09-01

The Chernobyl source term available for long-range transport was estimated by integration of radiological measurements with atmospheric dispersion modeling and by reactor core radionuclide inventory estimation in conjunction with WASH-1400 release fractions associated with specific chemical groups. The model simulations revealed that the radioactive cloud became segmented during the first day, with the lower section heading toward Scandinavia and the upper part heading in a southeasterly direction with subsequent transport across Asia to Japan, the North Pacific, and the west coast of North America. By optimizing the agreement between the observed cloud arrival times and duration of peak concentrations measured over Europe, Japan, Kuwait, and the US with the model predicted concentrations, it was possible to derive source term estimates for those radionuclides measured in airborne radioactivity. This was extended to radionuclides that were largely unmeasured in the environment by performing a reactor core radionuclide inventory analysis to obtain release fractions for the various chemical transport groups. These analyses indicated that essentially all of the noble gases, 60% of the radioiodines, 40% of the radiocesium, 10% of the tellurium and about 1% or less of the more refractory elements were released. These estimates are in excellent agreement with those obtained on the basis of worldwide deposition measurements. The Chernobyl source term was several orders of magnitude greater than those associated with the Windscale and TMI reactor accidents. However, the 137 Cs from the Chernobyl event is about 6% of that released by the US and USSR atmospheric nuclear weapon tests, while the 131 I and 90 Sr released by the Chernobyl accident was only about 0.1% of that released by the weapon tests. 13 refs., 2 figs., 7 tabs

Four Essays on Technology Licensing and Firm Innovation

DEFF Research Database (Denmark)

Moreira, Solon

&D strategies. On the supply side, the existing literature has been focused on understanding how technology licensing can be used by firms as a mechanism to recover investments in innovative activities and to foster learning opportunities. On the demand side, it has been shown that licensing is an important...... source that firms can tap into to feed their internal needs for innovative knowledge. While several studies have examined technology licensing through the lens of the licensor, research on how firms rely on licensing contracts to acquire knowledge and improve their innovation performance still leaves......Licensing contracts represent one of the most widely used mechanisms to exchange technologies and transfer know-how between firms. Due to the opportunities that licensing creates for firms operating on both sides of the markets for technology, it has increasingly become an integral part of firms’ R...

Determination of the in-containment source term for a Large-Break Loss of Coolant Accident

International Nuclear Information System (INIS)

2001-04-01

This is the report of a project that focused on one of the most important design basis accidents: the Large Break Loss Of Coolant Accident (LBLOCA) (for pressurised water reactors). The first step in the calculation of the radiological consequences of this accident is the determination of the source term inside the containment. This work deals with this part of the calculation of the LBLOCA radiological consequences for which a previous benchmark (1988) has shown wide variations in the licensing practices adopted by European countries. The calculation of this source term may naturally be split in several steps (see chapter II), corresponding to several physical stages in the release of fission products: fraction of core failure, release from the damaged fuel, airborne part of the release and the release into the reactor coolant system and the sumps, chemical behaviour of iodine in the aqueous and gas phases, natural and spray removal in the containment atmosphere. A chapter is devoted to each of these topics. In addition, two other chapters deal with the basic assumptions to define the accidental sequence and the nuclides to be considered when computing doses associated with the LBLOCA. The report describes where there is agreement between the partner organisations and where there are still differences in approach. For example, there is agreement concerning the percentage of failed fuel which could be used in future licensing assessments (however this subject is still under discussion in France, a lower value is thinkable). For existing plants, AVN (Belgium) wishes to keep the initial licensing assumptions. For the release from damaged fuel, there is not complete agreement: AVN (Belgium) wishes to maintain its present approach. IPSN (France), GRS (Germany) and NNC (UK) prefer to use their own methodologies that result in slightly different values to the proposed values for a common position. There are presently no recommendations of the release of fuel particulates

Source term and radiological consequences of the Chernobyl accident

International Nuclear Information System (INIS)

Mourad, R.

1987-09-01

This report presents the results of a study of the source term and radiological consequences of the Chernobyl accident. The results two parts. The first part was performed during the first 2 months following the accident and dealt with the evaluation of the source term and an estimate of individual doses in the European countries outside the Soviet Union. The second part was performed after August 25-29, 1986 when the Soviets presented in a IAEA Conference in Vienna detailed information about the accident, including source term and radiological consequences in the Soviet Union. The second part of the study reconfirms the source term evaluated in the first part and in addition deals with the radiological consequences in the Soviet Union. Source term and individual doses are calculated from measured post-accident data, reported by the Soviet Union and European countries, microcomputer program PEAR (Public Exposure from Accident Releases). 22 refs

Phase 1 immobilized low-activity waste operational source term

International Nuclear Information System (INIS)

Burbank, D.A.

1998-01-01

This report presents an engineering analysis of the Phase 1 privatization feeds to establish an operational source term for storage and disposal of immobilized low-activity waste packages at the Hanford Site. The source term information is needed to establish a preliminary estimate of the numbers of remote-handled and contact-handled waste packages. A discussion of the uncertainties and their impact on the source term and waste package distribution is also presented. It should be noted that this study is concerned with operational impacts only. Source terms used for accident scenarios would differ due to alpha and beta radiation which were not significant in this study

Free software, Open source software, licenses. A short presentation including a procedure for research software and data dissemination

OpenAIRE

Gomez-Diaz , Teresa

2014-01-01

4 pages. Spanish version: Software libre, software de código abierto, licencias. Donde se propone un procedimiento de distribución de software y datos de investigación; The main goal of this document is to help the research community to understand the basic concepts of software distribution: Free software, Open source software, licenses. This document also includes a procedure for research software and data dissemination.

Source term analyses under severe accidents for KNGR

Energy Technology Data Exchange (ETDEWEB)

Song, Yong Mann; Park, Soo Yong

2001-03-01

In this study, in-containment source term for LOFW (Loss of Feed Water), which has appeared the most frequent core melt accident, is calculated and compared with NUREG-1465 source term. This study provides not only new source term data using MELCOR1.8.4 and its state-of-the-art models but also evaluating basis of KNGR design and its mitigation capability under severe accidents. As the selected accident is identical with LOFW-S17, which has been analyzed using MAAP by KEPCO with only difference of 2 SITs, mutual comparison of the results is especially expected.

Requests for licensing of new nuclear sources. New nuclear power source in Slovakia

International Nuclear Information System (INIS)

Vidlicka, R.

2010-01-01

Presentation indicates a new NPP licensing process in the Slovak Republic from the point of the Preparatory Stage - Siting, Design Stage and Construction. The presentation lists individual main criteria and legislation requirements. A part of the presentation covers the estimated new NPP construction schedule and the comparison to proceeding in several foreign countries. (author)

Guide to request license for industrial X-rays practices

International Nuclear Information System (INIS)

2000-05-01

In this work the instructions it plows described to request license for practices it of industrial x-ray it continued. The instructions but important: they plows license type, purpose of the application, source and equipment, location of local the, program of radiological protection and security

License - Dicty_cDB | LSDB Archive [Life Science Database Archive metadata

Lifescience Database Archive (English)

Full Text Available List Contact us Dicty_cDB License to Use This Database Last updated : 2010/02/15 You may use this database i...w. The Standard License specifies the license terms regarding the use of this database and the requirements ...you must follow in using this database. The Additional License specifies those it...dard License The Standard License for this database is the license specified in the Creative Commons Attribu...tion-Share Alike 2.1 Japan . If you use data from this database, please be sure attribute this database

A simplified approach to evaluating severe accident source term for PWR

International Nuclear Information System (INIS)

Huang, Gaofeng; Tong, Lili; Cao, Xuewu

2014-01-01

Highlights: • Traditional source term evaluation approaches have been studied. • A simplified approach of source term evaluation for 600 MW PWR is studied. • Five release categories are established. - Abstract: For early design of NPPs, no specific severe accident source term evaluation was considered. Some general source terms have been used for some NPPs. In order to implement a best estimate, a special source term evaluation should be implemented for an NPP. Traditional source term evaluation approaches (mechanism approach and parametric approach) have some difficulties associated with their implementation. The traditional approaches are not consistent with cost-benefit assessment. A simplified approach for evaluating severe accident source term for PWR is studied. For the simplified approach, a simplified containment event tree is established. According to representative cases selection, weighted coefficient evaluation, computation of representative source term cases and weighted computation, five containment release categories are established, including containment bypass, containment isolation failure, containment early failure, containment late failure and intact containment

Radiological and chemical source terms for Solid Waste Operations Complex

International Nuclear Information System (INIS)

Boothe, G.F.

1994-01-01

The purpose of this document is to describe the radiological and chemical source terms for the major projects of the Solid Waste Operations Complex (SWOC), including Project W-112, Project W-133 and Project W-100 (WRAP 2A). For purposes of this document, the term ''source term'' means the design basis inventory. All of the SWOC source terms involve the estimation of the radiological and chemical contents of various waste packages from different waste streams, and the inventories of these packages within facilities or within a scope of operations. The composition of some of the waste is not known precisely; consequently, conservative assumptions were made to ensure that the source term represents a bounding case (i.e., it is expected that the source term would not be exceeded). As better information is obtained on the radiological and chemical contents of waste packages and more accurate facility specific models are developed, this document should be revised as appropriate. Radiological source terms are needed to perform shielding and external dose calculations, to estimate routine airborne releases, to perform release calculations and dose estimates for safety documentation, to calculate the maximum possible fire loss and specific source terms for individual fire areas, etc. Chemical source terms (i.e., inventories of combustible, flammable, explosive or hazardous chemicals) are used to determine combustible loading, fire protection requirements, personnel exposures to hazardous chemicals from routine and accident conditions, and a wide variety of other safety and environmental requirements

License - Yeast Interacting Proteins Database | LSDB Archive [Life Science Database Archive metadata

Lifescience Database Archive (English)

Full Text Available List Contact us Yeast Interacting Proteins Database License to Use This Database Last updated : 2010/02/15 You may use this database...nal License described below. The Standard License specifies the license terms regarding the use of this database... and the requirements you must follow in using this database. The Additional ...the Standard License. Standard License The Standard License for this database is the license specified in th...e Creative Commons Attribution-Share Alike 2.1 Japan . If you use data from this database

Effect of source term composition on offsite doses

International Nuclear Information System (INIS)

Karahalios, P.; Gardner, R.

1985-01-01

The development of new realistic accident source terms has identified the need to establish a basis for comparing the impact of such source terms. This paper attempts to develop a generalized basis of comparison by investigating contributions to offsite acute whole body doses from each group of radionuclides being released to the atmosphere, using CRAC2. The paper also investigates the effect of important parameters such as regional meteorology, sheltering, and duration of release. Finally, the paper focuses on significant changes in the relative importance of individual radionuclide groups in PWR2, SST1, and a revision of the Stone and Webster proposed interim source term

Design parameters and source terms: Volume 3, Source terms: Revision 0

International Nuclear Information System (INIS)

1987-09-01

The Design Parameters and Source Terms Document was prepared in accordance with DOE request and to provide data for the environmental impact study to be performed in the future for the Deaf Smith County, Texas site for a nuclear waste repository in salt. This document updates a previous unpublished report to the level of the Site Characterization Plan /endash/ Conceptual Design Report, SCP-CDR. The previous unpublished SCC Study identifies the data needs for the Environmental Assessment effort for seven possible salt repository sites

Foundation for the adequacy of the licensing bases

International Nuclear Information System (INIS)

1991-12-01

The objective of this report is to describe the regulatory processes that assures that any plant-specific licensing bases will provide reasonable assurance that the operation of nuclear power plants will not be inimical to the public health and safety to the end of the renewal period. It is on the adequacy of this process that the Commission has determined that a formal renewal licensing review against the full range of current safety requirements would not add significantly to safety and is not needed to assure that continued operation throughout the renewal term is not inimical to the public health and safety or common defense and security. This document illustrates in general terms how the regulatory process has evolved in major safety issue areas. It also provides examples illustrating why it is unnecessary to re-review an operating plant's basis, except for age-related degradation unique to license renewal, at the time of license renewal. The report is a supplement to the Statement of Considerations for the Nuclear Regulatory Commission's rule (10 CFR Part 54) that established the criteria and standards governing nuclear power plant license renewal

Bayesian source term determination with unknown covariance of measurements

Science.gov (United States)

Belal, Alkomiet; Tichý, Ondřej; Šmídl, Václav

2017-04-01

Determination of a source term of release of a hazardous material into the atmosphere is a very important task for emergency response. We are concerned with the problem of estimation of the source term in the conventional linear inverse problem, y = Mx, where the relationship between the vector of observations y is described using the source-receptor-sensitivity (SRS) matrix M and the unknown source term x. Since the system is typically ill-conditioned, the problem is recast as an optimization problem minR,B(y - Mx)TR-1(y - Mx) + xTB-1x. The first term minimizes the error of the measurements with covariance matrix R, and the second term is a regularization of the source term. There are different types of regularization arising for different choices of matrices R and B, for example, Tikhonov regularization assumes covariance matrix B as the identity matrix multiplied by scalar parameter. In this contribution, we adopt a Bayesian approach to make inference on the unknown source term x as well as unknown R and B. We assume prior on x to be a Gaussian with zero mean and unknown diagonal covariance matrix B. The covariance matrix of the likelihood R is also unknown. We consider two potential choices of the structure of the matrix R. First is the diagonal matrix and the second is a locally correlated structure using information on topology of the measuring network. Since the inference of the model is intractable, iterative variational Bayes algorithm is used for simultaneous estimation of all model parameters. The practical usefulness of our contribution is demonstrated on an application of the resulting algorithm to real data from the European Tracer Experiment (ETEX). This research is supported by EEA/Norwegian Financial Mechanism under project MSMT-28477/2014 Source-Term Determination of Radionuclide Releases by Inverse Atmospheric Dispersion Modelling (STRADI).

A comparison of world-wide uses of severe reactor accident source terms

International Nuclear Information System (INIS)

Ang, M.L.; Frid, W.; Kersting, E.J.; Friederichs, H.G.; Lee, R.Y.; Meyer-Heine, A.; Powers, D.A.; Soda, K.; Sweet, D.

1994-09-01

The definitions of source terms to reactor containments and source terms to the environment are discussed. A comparison is made between the TID-14844 example source term and the alternative source term described in NUREG-1465. Comparisons of these source terms to the containments and those used in France, Germany, Japan, Sweden, and the United Kingdom are made. Source terms to the environment calculated in NUREG-1500 and WASH-1400 are discussed. Again, these source terms are compared to those now being used in France, Germany, Japan, Sweden, and the United Kingdom. It is concluded that source terms to the containment suggested in NUREG-1465 are not greatly more conservative than those used in other countries. Technical bases for the source terms are similar. The regulatory use of the current understanding of radionuclide behavior varies among countries

License - CREATE portal | LSDB Archive [Life Science Database Archive metadata

Lifescience Database Archive (English)

Full Text Available List Contact us CREATE portal License License to Use This Database Last updated : 2016/03/16 You may use this database... the license terms regarding the use of this database and the requirements you must follow in using this database.... The license for this database is specified in the Creative Commons Attribu...tion-Share Alike 4.0 International . If you use data from this database, please be sure attribute this database...hare Alike 4.0 International is found here . With regard to this database, you are licensed to: freely acces

Consolidated guidance about materials licenses: Program-specific guidance about portable gauge licenses. Final report; Volume 1

Energy Technology Data Exchange (ETDEWEB)

Vacca, P.C.; Whitten, J.E.; Pelchat, J.M.; Arredondo, S.A.; Matson, E.R.; Lewis, S.H.; Collins, D.J.; Santiago, P.A. [Nuclear Regulatory Commission, Washington, DC (United States). Div. of Industrial and Medical Nuclear Safety; Tingle, W. [Dept. of Environment, Health, and Natural Resources, Raleigh, NC (United States). Div. of Radiation Protection

1997-05-01

As part of its redesign of the materials licensing process, NRC is consolidating and updating numerous guidance documents into a single comprehensive repository as described in NUREG-1539 and draft NUREG-1541. NUREG-1556, Vol. 1, is the first program-specific guidance developed for the new process and will serve as a template for subsequent program-specific guidance. This document is intended for use by applicants, licensees, and NRC staff and will also be available to Agreement States. This document supersedes the guidance previously found in draft Regulatory Guide DG-0008, ``Applications for the Use of Sealed Sources in Portable Gauging Devices,`` and in NMSs Policy and guidance Directive 2-07, ``Standard Review Plan for Applications for Use of Sealed Sources in Portable Gauging Devices.`` This final report takes a more risk-informed, performance-based approach to licensing portable gauges, and reduces the information(amount and level of detail) needed to support an application to use these devices. It incorporates many suggests submitted during the comment period on draft NUREG-1556, Volume 1. When published, this final report should be used in preparing portable gauge license applications. NRC staff will use this final report in reviewing these applications.

Consolidated guidance about materials licenses: Program-specific guidance about portable gauge licenses. Final report; Volume 1

International Nuclear Information System (INIS)

Vacca, P.C.; Whitten, J.E.; Pelchat, J.M.; Arredondo, S.A.; Matson, E.R.; Lewis, S.H.; Collins, D.J.; Santiago, P.A.; Tingle, W.

1997-05-01

As part of its redesign of the materials licensing process, NRC is consolidating and updating numerous guidance documents into a single comprehensive repository as described in NUREG-1539 and draft NUREG-1541. NUREG-1556, Vol. 1, is the first program-specific guidance developed for the new process and will serve as a template for subsequent program-specific guidance. This document is intended for use by applicants, licensees, and NRC staff and will also be available to Agreement States. This document supersedes the guidance previously found in draft Regulatory Guide DG-0008, ''Applications for the Use of Sealed Sources in Portable Gauging Devices,'' and in NMSs Policy and guidance Directive 2-07, ''Standard Review Plan for Applications for Use of Sealed Sources in Portable Gauging Devices.'' This final report takes a more risk-informed, performance-based approach to licensing portable gauges, and reduces the information(amount and level of detail) needed to support an application to use these devices. It incorporates many suggests submitted during the comment period on draft NUREG-1556, Volume 1. When published, this final report should be used in preparing portable gauge license applications. NRC staff will use this final report in reviewing these applications

Public licenses and public domain as alternatives to copyright

OpenAIRE

Köppel, Petr

2012-01-01

The work first introduces the area of public licenses as a space between the copyright law and public domain. After that, consecutively for proprietary software, free and open source software, open hardware and open content, it maps particular types of public licenses and the accompanying social and cultural movements, puts them in mutual as well as historical context, examines their characteristics and compares them to each other, shows how the public licenses are defined by various accompan...

Quantification of severe accident source terms of a Westinghouse 3-loop plant

International Nuclear Information System (INIS)

Lee Min; Ko, Y.-C.

2008-01-01

Integrated severe accident analysis codes are used to quantify the source terms of the representative sequences identified in PSA study. The characteristics of these source terms depend on the detail design of the plant and the accident scenario. A historical perspective of radioactive source term is provided. The grouping of radionuclides in different source terms or source term quantification tools based on TID-14844, NUREG-1465, and WASH-1400 is compared. The radionuclides release phenomena and models adopted in the integrated severe accident analysis codes of STCP and MAAP4 are described. In the present study, the severe accident source terms for risk quantification of Maanshan Nuclear Power Plant of Taiwan Power Company are quantified using MAAP 4.0.4 code. A methodology is developed to quantify the source terms of each source term category (STC) identified in the Level II PSA analysis of the plant. The characteristics of source terms obtained are compared with other source terms. The plant analyzed employs a Westinghouse designed 3-loop pressurized water reactor (PWR) with large dry containment

License - Metabolonote | LSDB Archive [Life Science Database Archive metadata

Lifescience Database Archive (English)

Full Text Available List Contact us Metabolonote License License to Use This Database Last updated : 2016/06/22 You may use this database...the license terms regarding the use of this database and the requirements you must follow in using this database.... The license for this database is specified in the Creative Commons Attribut...ion-Share Alike 4.0 International . If you use data from this database, please be sure attribute this database...e Creative Commons Attribution-Share Alike 4.0 International is found here . With regard to this database

Relationship between licensing, registration, and other gun sales laws and the source state of crime guns.

Science.gov (United States)

Webster, D W; Vernick, J S; Hepburn, L M

2001-09-01

To determine the association between licensing and registration of firearm sales and an indicator of gun availability to criminals. Tracing data on all crime guns recovered in 25 cities in the United States were used to estimate the relationship between state gun law categories and the proportion of crime guns first sold by in-state gun dealers. In cities located in states with both mandatory registration and licensing systems (five cities), a mean of 33.7% of crime guns were first sold by in-state gun dealers, compared with 72.7% in cities that had either registration or licensing but not both (seven cities), and 84.2% in cities without registration or licensing (13 cites). Little of the difference between cities with both licensing and registration and cities with neither licensing nor registration was explained by potential confounders. The share of the population near a city that resides in a neighboring state without licensing or registration laws was negatively associated with the outcome. States with registration and licensing systems appear to do a better job than other states of keeping guns initially sold within the state from being recovered in crimes. Proximity to states without these laws, however, may limit their impact.

Assessment and improvement on system of licensing for work with ionizing radiation in China

International Nuclear Information System (INIS)

Sun Xiaobo

1998-01-01

The article outlined regulations, authorities and responsibilities for licensing in China. The health departments at provincial level issue the license certificates to the units engaging in the production, use or sale of radioisotopes or apparatus equipped with radiation source or radiation-emitting apparatus, and have the duty of supervising and monitoring the security about radiation work. For the particular dangers of radiation sources, there is deficiency and shortage of the current licensing system, such as ignorance of the importance of keeping detail records about sources, poor communications among every health department, poor actions to prevent illegal and secret radiation work such as secret use and sale. We are going to improve our licensing system by hardware (computer technology) and software (management). (author)

License - Society Catalog | LSDB Archive [Life Science Database Archive metadata

Lifescience Database Archive (English)

Full Text Available List Contact us Society Catalog License License to Use This Database Last updated : 2012/01/17 You may use this database...es the license terms regarding the use of this database and the requirements you must follow in using this database.... The license for this database is specified in the Creative Commons Attri...bution-Share Alike 2.1 Japan . If you use data from this database, please be sure attribute this database as...is found here . With regard to this database, you are licensed to: freely access part or whole of this database

Estimation of Source Term Behaviors in SBO Sequence in a Typical 1000MWth PWR and Comparison with Other Source Term Results

Energy Technology Data Exchange (ETDEWEB)

Kim, Tae Woon; Han, Seok Jung; Ahn, Kwang Il; Fynan, Douglas; Jung, Yong Hoon [KAERI, Daejeon (Korea, Republic of)

2016-05-15

Since the Three Mile Island (TMI) (1979), Chernobyl (1986), Fukushima Daiichi (2011) accidents, the assessment of radiological source term effects on the environment has been a key concern of nuclear safety. In the Fukushima Daiichi accident, the long-term SBO (station blackout) accident occurs. Using the worst case assumptions like in Fukushima accident on the accident sequences and on the availability of safety systems, the thermal hydraulic behaviors, core relocation and environmental source terms behaviors are estimated for long-term SBO accident for OPR-1000 reactor. MELCOR code version 1.8.6 is used in this analysis. Source term results estimated in this study is compared with other previous studies and estimated results in Fukushima accidents in UNSCEAR-2013 report. This study estimated that 11 % of iodine can be released to environment and 2% of cesium can be released to environment. UNSCEAR-2013 report estimated that 2 - 8 % of iodine have been released to environment and 1 - 3 % of cesium have been released to the environment. They have similar results in the aspect of release fractions of iodine and cesium to environment.

Licensing decisions and safety research related to LMFBR accidents

International Nuclear Information System (INIS)

Denise, R.P.; Speis, T.P.; Kelber, C.N.; Curtis, R.T.

1977-01-01

The licensing approach which ensures adequate protection of the public health and safety against serious accidents is described. This paper describes the role of core melt and core disruptive accidents in the design, safety research, and licensing processes, using the Clinch River Breeder Reactor (CRBR) as a focal point. Major design attention is placed on the prevention of these accidents so that the probability of core melt accidents is reduced to a sufficiently low level that they are not treated as design basis accidents. Additional requirements are placed upon the design to further reduce residual risk. This licensing process is supported by a confirmatory research program designed to provide an independent basis for licensing judgements. It has as a goal the resolution of generic safety issues prior to the establishment of a commercial LMFBR industry. The program includes accident analysis, experiments in materials interactions, aerosol transport and system integrity and planning for new safety test facilities. The problems are approached in a multi-disciplinary functional manner that identifies key safety issues and centralizes efforts to resolve them. The near term objectives of the program support the licensing of the Clinch River Breeder Reactor (CRBR) and the proposed Prototype Large Breeder Reactor (PLBR). The long term objectives of the program support the licensing of commercial LMFBRs during the late 1980's and beyond. This safety research is designed to provide an independent basis for the licensing judgements which must be made by the Nuclear Regulatory Commission

Selection of models to calculate the LLW source term

International Nuclear Information System (INIS)

Sullivan, T.M.

1991-10-01

Performance assessment of a LLW disposal facility begins with an estimation of the rate at which radionuclides migrate out of the facility (i.e., the source term). The focus of this work is to develop a methodology for calculating the source term. In general, the source term is influenced by the radionuclide inventory, the wasteforms and containers used to dispose of the inventory, and the physical processes that lead to release from the facility (fluid flow, container degradation, wasteform leaching, and radionuclide transport). In turn, many of these physical processes are influenced by the design of the disposal facility (e.g., infiltration of water). The complexity of the problem and the absence of appropriate data prevent development of an entirely mechanistic representation of radionuclide release from a disposal facility. Typically, a number of assumptions, based on knowledge of the disposal system, are used to simplify the problem. This document provides a brief overview of disposal practices and reviews existing source term models as background for selecting appropriate models for estimating the source term. The selection rationale and the mathematical details of the models are presented. Finally, guidance is presented for combining the inventory data with appropriate mechanisms describing release from the disposal facility. 44 refs., 6 figs., 1 tab

Review of SFR In-Vessel Radiological Source Term Studies

International Nuclear Information System (INIS)

Suk, Soo Dong; Lee, Yong Bum

2008-10-01

An effort has been made in this study to search for and review the literatures in public domain on the studies of the phenomena related to the release of radionuclides and aerosols to the reactor containment of the sodium fast reactor (SFR) plants (i.e., in-vessel source term), made in Japan and Europe including France, Germany and UK over the last few decades. Review work is focused on the experimental programs to investigate the phenomena related to determining the source terms, with a brief review on supporting analytical models and computer programs. In this report, the research programs conducted to investigate the CDA (core disruptive accident) bubble behavior in the sodium pool for determining 'primary' or 'instantaneous' source term are first introduced. The studies performed to determine 'delayed source term' are then described, including the various stages of phenomena and processes: fission product (FP) release from fuel , evaporation release from the surface of the pool, iodine mass transfer from fission gas bubble, FP deposition , and aerosol release from core-concrete interaction. The research programs to investigate the release and transport of FPs and aerosols in the reactor containment (i.e., in-containment source term) are not described in this report

License - PGDBj - Ortholog DB | LSDB Archive [Life Science Database Archive metadata

Lifescience Database Archive (English)

Full Text Available List Contact us PGDBj - Ortholog DB License License to Use This Database Last updated : 2017/03/07 You may use this database...cifies the license terms regarding the use of this database and the requirements you must follow in using this database.... The license for this database is specified in the Creative Commons A...ttribution-Share Alike 4.0 International . If you use data from this database, please be sure attribute this database...hare Alike 4.0 International is found here . With regard to this database, you are licensed to: freely acces

Utility view of the source term and air cleaning

International Nuclear Information System (INIS)

Littlefield, P.S.

1985-01-01

The utility view of the source term and air cleaning is discussed. The source term is made up of: (1) noble gases, which there has been a tendency to ignore in the past because it was thought there was nothing that could be done with them anyway, (2) the halogens, which have been dealt with in Air Cleaning Conferences in the past in terms of charcoal and other systems for removing them, and (3) the solid components of the source term which particulate filters are designed to handle. Air cleaning systems consist of filters, adsorbers, containment sprays, suppression pools in boiling water reactors and ice beds in ice condenser-equipped plants. The feasibility and cost of air cleaning systems are discussed

77 FR 3273 - Government-Owned Inventions; Availability for Licensing

Science.gov (United States)

2012-01-23

... Technology: Available for licensing is a novel method using short-term treatment with a glucocorticoid...: Licensing information and copies of the U.S. patent applications listed below may be obtained by writing to... into memory cells and terminally differentiated plasma cells. Moreover, IL-21 has anti-tumor activity...

77 FR 63343 - Biweekly Notice: Applications and Amendments to Facility Operating Licenses and Combined Licenses...

Science.gov (United States)

2012-10-16

... in accordance with the Commission's ``Rules of Practice for Domestic Licensing Proceedings'' in 10... for an inoperable diesel generator (DG). A commensurate change is also proposed to extend the maximum... alternating current power source (i.e., a supplemental diesel generator) with the capability to power any E...

Renewal of operating licenses: the U.S. model

International Nuclear Information System (INIS)

Petroll, M.; Tveiten, B.

2006-01-01

Nearly half of the American nuclear power plants by now have been granted permits allowing them to be operated for twenty years more than originally planned. Procedures to this effect are under way for one quarter of U.S. nuclear power plants. For the operators, plant life extension, as a rule, is economically preferable to building new baseload plants or buying electricity from other sources. In the licensing procedures, the U.S. regulatory authority examines both environmental aspects and safety aspects of extended operation. The technical basis of assessment is the GALL report (Generic Aging Lessons Learnt) which by now has become the consolidated yardstick used by the authorities for safety assessment. In these procedures, the licensee is required to present updated design documents and, if applicable, extend or create from scratch programs of aging management. The case of the oldest nuclear power plant in operation in the United States is described to show the steps of an American licensing and administrative court procedure. Granting renewed operating permits began before President Bush's term and will continue independent of the change in government in 2008. (orig.)

Low-level radioactive waste performance assessments: Source term modeling

International Nuclear Information System (INIS)

Icenhour, A.S.; Godbee, H.W.; Miller, L.F.

1995-01-01

Low-level radioactive wastes (LLW) generated by government and commercial operations need to be isolated from the environment for at least 300 to 500 yr. Most existing sites for the storage or disposal of LLW employ the shallow-land burial approach. However, the U.S. Department of Energy currently emphasizes the use of engineered systems (e.g., packaging, concrete and metal barriers, and water collection systems). Future commercial LLW disposal sites may include such systems to mitigate radionuclide transport through the biosphere. Performance assessments must be conducted for LUW disposal facilities. These studies include comprehensive evaluations of radionuclide migration from the waste package, through the vadose zone, and within the water table. Atmospheric transport mechanisms are also studied. Figure I illustrates the performance assessment process. Estimates of the release of radionuclides from the waste packages (i.e., source terms) are used for subsequent hydrogeologic calculations required by a performance assessment. Computer models are typically used to describe the complex interactions of water with LLW and to determine the transport of radionuclides. Several commonly used computer programs for evaluating source terms include GWSCREEN, BLT (Breach-Leach-Transport), DUST (Disposal Unit Source Term), BARRIER (Ref. 5), as well as SOURCE1 and SOURCE2 (which are used in this study). The SOURCE1 and SOURCE2 codes were prepared by Rogers and Associates Engineering Corporation for the Oak Ridge National Laboratory (ORNL). SOURCE1 is designed for tumulus-type facilities, and SOURCE2 is tailored for silo, well-in-silo, and trench-type disposal facilities. This paper focuses on the source term for ORNL disposal facilities, and it describes improved computational methods for determining radionuclide transport from waste packages

Literature study of source term research for PWRs

Energy Technology Data Exchange (ETDEWEB)

Sponton, L.L.; NiIsson, Lars

2001-04-01

A literature survey has been carried out in support of ongoing source term calculations with the MELCOR code of some severe accident scenarios for the Swedish Ringhals 2 pressurised water reactor (PWR). The research in the field of severe accidents in power reactors and the source term for subsequent release of radioisotopes was intensified after the Harrisburg accident and has produced a large amount of reports and papers. This survey was therefore limited to research concerning PWR type of reactors and with emphasis on papers related to MELCOR code development. A background is given, relating to some historic documents, and then more recent research after 1990 is reviewed. Of special interest is the ongoing PMbus-programme which is creating new and important results of benefit to the code development and validation of, among others, the MELCOR code. It is concluded that source term calculations involve simulation of many interacting complex physical phenomena, which result in large uncertainties The research has, however, over the years led to considerable improvements Thus has the uncertainty in source term predictions been reduced one to two orders of magnitude from the simpler codes in the early 1980-s to the more realistic codes of today, like MELCOR.

Literature study of source term research for PWRs

International Nuclear Information System (INIS)

Sponton, L.L.; NiIsson, Lars

2001-04-01

A literature survey has been carried out in support of ongoing source term calculations with the MELCOR code of some severe accident scenarios for the Swedish Ringhals 2 pressurised water reactor (PWR). The research in the field of severe accidents in power reactors and the source term for subsequent release of radioisotopes was intensified after the Harrisburg accident and has produced a large amount of reports and papers. This survey was therefore limited to research concerning PWR type of reactors and with emphasis on papers related to MELCOR code development. A background is given, relating to some historic documents, and then more recent research after 1990 is reviewed. Of special interest is the ongoing PMbus-programme which is creating new and important results of benefit to the code development and validation of, among others, the MELCOR code. It is concluded that source term calculations involve simulation of many interacting complex physical phenomena, which result in large uncertainties The research has, however, over the years led to considerable improvements Thus has the uncertainty in source term predictions been reduced one to two orders of magnitude from the simpler codes in the early 1980-s to the more realistic codes of today, like MELCOR

License - Taxonomy Icon | LSDB Archive [Life Science Database Archive metadata

Lifescience Database Archive (English)

Full Text Available List Contact us Taxonomy Icon License License to Use This Database Last updated : 2013/3/21 You may use this database...the license terms regarding the use of this database and the requirements you must follow in using this database.... The license for this database is specified in the Creative Commons Attribut...ion 2.1 Japan . If you use data from this database, please be sure attribute this database as follows: Taxon...ative Commons Attribution 2.1 Japan is found here . With regard to this database,

Reassessment of the technical bases for estimating source terms. Final report

International Nuclear Information System (INIS)

Silberberg, M.; Mitchell, J.A.; Meyer, R.O.; Ryder, C.P.

1986-07-01

This document describes a major advance in the technology for calculating source terms from postulated accidents at US light-water reactors. The improved technology consists of (1) an extensive data base from severe accident research programs initiated following the TMI accident, (2) a set of coupled and integrated computer codes (the Source Term Code Package), which models key aspects of fission product behavior under severe accident conditions, and (3) a number of detailed mechanistic codes that bridge the gap between the data base and the Source Term Code Package. The improved understanding of severe accident phenonmena has also allowed an identification of significant sources of uncertainty, which should be considered in estimating source terms. These sources of uncertainty are also described in this document. The current technology provides a significant improvement in evaluating source terms over that available at the time of the Reactor Safety Study (WASH-1400) and, because of this significance, the Nuclear Regulatory Commission staff is recommending its use

Partner Selection in Technological Licensing Agreements

DEFF Research Database (Denmark)

Laursen, Keld; Trombini, Giulia

This paper investigates the matching of seller and buyer firms in the market for technology licensing. By combining organizational learning theory with the industrial organization approach, we propose a matching model in which technological similarities in terms of relatedness and familiarity work...... that is technologically unrelated, ex ante familiarity with the licensors’ technology is required. We contend also that there is interdependence between technological learning and market competition: if partners are in the same product markets, the likelihood of technology license contractual partnerships decreases...

License - PLACE | LSDB Archive [Life Science Database Archive metadata

Lifescience Database Archive (English)

Full Text Available List Contact us PLACE License License to Use This Database Last updated : 2014/07/17 You may use this database...ense terms regarding the use of this database and the requirements you must follow in using this database. The license for this datab...re Alike 2.1 Japan. If you use data from this database, please be sure attribute this database as follows: ... ...re . With regard to this database, you are licensed to: freely access part or whole of this database, and ac...quire data; freely redistribute part or whole of the data from this database; and freely create and distribute database

License - RMG | LSDB Archive [Life Science Database Archive metadata

Lifescience Database Archive (English)

Full Text Available List Contact us RMG License License to Use This Database Last updated : 2013/08/07 You may use this database...se terms regarding the use of this database and the requirements you must follow in using this database. The license for this databas... Alike 2.1 Japan. If you use data from this database, please be sure attribute this database as follows: Ric...Japan is found here . With regard to this database, you are licensed to: freely access part or whole of this database..., and acquire data; freely redistribute part or whole of the data from this database; and freely create and distribute datab

Licensing biotech intellectual property in university-industry partnerships.

Science.gov (United States)

Drozdoff, Vladimir; Fairbairn, Daryl

2015-01-20

Appropriate negotiation and drafting of license agreements are critical to successfully establishing and managing the expansive and complex relationships that are becoming more common between industry and universities. More often than not, the resulting licensing agreements become quite lengthy and complex, and the key principles become difficult to discern among all the details. This summary provides a short, nonexhaustive introduction to some of the essential components of these licenses with the intent of providing the non-licensing professional a better appreciation of some of the key commercial and legal terms from both an academic and company perspective, keeping in mind some of the considerations that particularly apply to biotechnology deals. Copyright © 2015 Cold Spring Harbor Laboratory Press; all rights reserved.

ITER licensing

International Nuclear Information System (INIS)

Gordon, C.W.

2005-01-01

ITER was fortunate to have four countries interested in ITER siting to the point where licensing discussions were initiated. This experience uncovered the challenges of licensing a first of a kind, fusion machine under different licensing regimes and helped prepare the way for the site specific licensing process. These initial steps in licensing ITER have allowed for refining the safety case and provide confidence that the design and safety approach will be licensable. With site-specific licensing underway, the necessary regulatory submissions have been defined and are well on the way to being completed. Of course, there is still work to be done and details to be sorted out. However, the informal international discussions to bring both the proponent and regulatory authority up to a common level of understanding have laid the foundation for a licensing process that should proceed smoothly. This paper provides observations from the perspective of the International Team. (author)

THE SOCIAL OPERATING LICENSE OF CORPORATIONS: MINING COMPANIES AND THEIR CONSTITUENTS

OpenAIRE

Dumitru Borțun; Camelia Crişan

2012-01-01

Several authors from the CSR literature have proposed the term “license to operate” when referring to companies and their activities in the relevant communities (Visser, 2008, Post, Preston & Sachs, 2002). Others have implied this term when referring to the types of responsibilities a company needs to have in order to be able to exercise its activity in the society (Blair [1994] 2004, Clarke [1998] 2004 and Philips 2003). Consultancy companies have already coined the term: social license to o...

Relevant aspects in licensing of radioactive installations at petroleum and gas well logging

International Nuclear Information System (INIS)

Miranda, Marcia Valeria da E. Sa

2002-01-01

The importance of the various factors considered during the process of licensing of radioactive installation for petroleum and gas well logging. This process involves the issuing of some public power acts, the co called Administrative Acts. For the radioactive installations the Administrative Acts are related to the Norm CNEN-NE-6.02 'Licensing of Radioactive Installation'. In the conduction of the licensing of radioactive installation of mobile nuclear measurement devices the safety evaluation of radioactive installation and equipment containing incorporated radiation source are included; certification of radioprotection supervisors; programing and evaluation of the radioprotection inspections; and the conduction of conformal inspection according to the project, safety analysis and audits. An evaluation of the impact of the importance grade attributed to each factor in the optimization of licensing process is related. Finally, the prediction of implantation of a control system for the displacement of radioactive sources in the installation is approached comprehending the up-to-date localization of each source at different work front of the Basis

Hazardous constituent source term. Revision 2

International Nuclear Information System (INIS)

1994-01-01

The Department of Energy (DOE) has several facilities that either generate and/or store transuranic (TRU)-waste from weapons program research and production. Much of this waste also contains hazardous waste constituents as regulated under Subtitle C of the Resource Conservation and Recovery Act (RCRA). Toxicity characteristic metals in the waste principally include lead, occurring in leaded rubber gloves and shielding. Other RCRA metals may occur as contaminants in pyrochemical salt, soil, debris, and sludge and solidified liquids, as well as in equipment resulting from decontamination and decommissioning activities. Volatile organic compounds (VOCS) contaminate many waste forms as a residue adsorbed on surfaces or occur in sludge and solidified liquids. Due to the presence of these hazardous constituents, applicable disposal regulations include land disposal restrictions established by Hazardous and Solid Waste Amendments (HSWA). The DOE plans to dispose of TRU-mixed waste from the weapons program in the Waste Isolation Pilot Plant (WIPP) by demonstrating no-migration of hazardous constituents. This paper documents the current technical basis for methodologies proposed to develop a post-closure RCRA hazardous constituent source term. For the purposes of demonstrating no-migration, the hazardous constituent source term is defined as the quantities of hazardous constituents that are available for transport after repository closure. Development of the source term is only one of several activities that will be involved in the no-migration demonstration. The demonstration will also include uncertainty and sensitivity analyses of contaminant transport

License - RGP gmap98 | LSDB Archive [Life Science Database Archive metadata

Lifescience Database Archive (English)

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License - ChIP-Atlas | LSDB Archive [Life Science Database Archive metadata

Lifescience Database Archive (English)

Full Text Available List Contact us ChIP-Atlas License License to Use This Database Last updated : 2016/06/24 You may use this database...e license terms regarding the use of this database and the requirements you must follow in using this database.... The license for this database is specified in the Creative Commons Attributio...n-Share Alike 4.0 International . If you use data from this database, please be sure attribute this database...national is found here . With regard to this database, you are licensed to: freely access part or whole of this database

Real time source term and dose assessment

International Nuclear Information System (INIS)

Breznik, B.; Kovac, A.; Mlakar, P.

2001-01-01

The Dose Projection Programme is a tool for decision making in case of nuclear emergency. The essential input data for quick emergency evaluation in the case of hypothetical pressurised water reactor accident are following: source term, core damage assessment, fission product radioactivity, release source term and critical exposure pathways for an early phase of the release. A reduced number of radio-nuclides and simplified calculations can be used in dose calculation algorithm. Simple expert system personal computer programme has been developed for the Krsko Nuclear Power Plant for dose projection within the radius of few kilometers from the pressurised water reactor in early phase of an accident. The input data are instantaneous data of core activity, core damage indicators, release fractions, reduction factor of the release pathways, spray operation, release timing, and dispersion coefficient. Main dose projection steps are: accurate in-core radioactivity determination using reactor power input; core damage and in-containment source term assessment based on quick indications of instrumentation or on activity analysis data; user defines release pathway for typical PWR accident scenarius; dose calculation is performed only for exposure pathway critical for decision about evacuation or sheltering in early phase of an accident.(author)

License - Budding yeast cDNA sequencing project | LSDB Archive [Life Science Database Archive metadata

Lifescience Database Archive (English)

Full Text Available List Contact us Budding yeast cDNA sequencing project License to Use This Database Last updated : 2010/02/15 You may use this databas...ional License described below. The Standard License specifies the license terms regarding the use of this database... and the requirements you must follow in using this database. The Additiona...n the Standard License. Standard License The Standard License for this database is the license specified in ...the Creative Commons Attribution-Share Alike 2.1 Japan . If you use data from this database

Application of the source term code package to obtain a specific source term for the Laguna Verde Nuclear Power Plant

International Nuclear Information System (INIS)

Souto, F.J.

1991-06-01

The main objective of the project was to use the Source Term Code Package (STCP) to obtain a specific source term for those accident sequences deemed dominant as a result of probabilistic safety analyses (PSA) for the Laguna Verde Nuclear Power Plant (CNLV). The following programme has been carried out to meet this objective: (a) implementation of the STCP, (b) acquisition of specific data for CNLV to execute the STCP, and (c) calculations of specific source terms for accident sequences at CNLV. The STCP has been implemented and validated on CDC 170/815 and CDC 180/860 main frames as well as on a Micro VAX 3800 system. In order to get a plant-specific source term, data on the CNLV including initial core inventory, burn-up, primary containment structures, and materials used for the calculations have been obtained. Because STCP does not explicitly model containment failure, dry well failure in the form of a catastrophic rupture has been assumed. One of the most significant sequences from the point of view of possible off-site risk is the loss of off-site power with failure of the diesel generators and simultaneous loss of high pressure core spray and reactor core isolation cooling systems. The probability for that event is approximately 4.5 x 10 -6 . This sequence has been analysed in detail and the release fractions of radioisotope groups are given in the full report. 18 refs, 4 figs, 3 tabs

Work Life Stress and Career Resilience of Licensed Nursing Facility Administrators.

Science.gov (United States)

Myers, Dennis R; Rogers, Rob; LeCrone, Harold H; Kelley, Katherine; Scott, Joel H

2018-04-01

Career resilience provided a frame for understanding how Licensed Nursing Facility Administrators (LNFAs) sustain role performance and even thrive in stressful skilled nursing facility work environments. Quantitative and qualitative analyses of in-depth interviews with18 LNFAs, averaging 24 years of experience were conducted by a five-member research team. Analysis was informed by evidence-based frameworks for career resilience in the health professions as well as the National Association of Long-Term Care Administrator Boards' (NAB) five domains of competent administrative practice. Findings included six sources of work stressors and six sources of professional satisfaction. Also, participants identified seven strategic principles and 10 administrative practices for addressing major sources of stress. Recommendations are provided for research and evidence-based application of the career resilience perspective to LNFA practice aimed at reducing role abandonment and energizing the delivery of the quality of care that each resident deserves.

Source Term Model for Fine Particle Resuspension from Indoor Surfaces

National Research Council Canada - National Science Library

Kim, Yoojeong; Gidwani, Ashok; Sippola, Mark; Sohn, Chang W

2008-01-01

This Phase I effort developed a source term model for particle resuspension from indoor surfaces to be used as a source term boundary condition for CFD simulation of particle transport and dispersion in a building...

Analysis of license renewal at U.S. Nuclear Power Plants

International Nuclear Information System (INIS)

Nagayama, Munehiro

2017-01-01

The U.S. NRC had implemented the rules for LR (License Renewal) of NPPs (Nuclear Power Plants) and the LR rules allow plus 20-year operation of NPPs adding to initial 40-year term for reactor license. The U.S. NRC has already issued ROL (Renewed Operating License) for over forty NPPs. The Atomic Energy Act do not limit the number of LR, so the fleet of U.S. Nuclear, including agency, industry and academy, is continuing efforts to develop rules for SLR (Subsequent License Renewal). The framework of SLR rules has been developed and there is a plan of implementation of SLR for a pilot plant on FY 2018. The total operating term of a SLR plant is 80-year. The LR/SLR of NPPs is effective for stable power supply, greenhouse gas suppression, maintenance of technology, and securing employment. These profits will return to society. It is important to maintain required function of SSCs (Structure, System, and Components) for period of long term operation of NPPs. The U.S. fleet has established integrated ageing management strategy and each NPPs is developing their maintenance plans for long term operation. These adequate maintenance plans may enable to achieve good capacity factor of LR applied NPPs. In this report, domestic LR position will be considered by referring the good performance of U.S. NPPs which entered long term operation beyond 40-year and some conditions such as energy security. (author)

Improving the Business Trade Licensing Reform Environment

OpenAIRE

Gamser, Matthew

2003-01-01

This case study of Kenyan business trade licensing shows that red-tape costs can be cut if reform is championed strongly and there is a strong case in terms of costs and benefits. The reform of business registration, trade licensing and other business entry procedures is a cost effective and progressive way to promote indigenous private sector development. But, reform needs more than good cost-benefit analysis and legal drafting; it also requires building constituencies and continuous advocacy.

Scoping Analysis of Source Term and Functional Containment Attenuation Factors

Energy Technology Data Exchange (ETDEWEB)

Pete Lowry

2012-10-01

In order to meet future regulatory requirements, the Next Generation Nuclear Plant (NGNP) Project must fully establish and validate the mechanistic modular high temperature gas-cooled reactor (HTGR) source term. This is not possible at this stage in the project, as significant uncertainties in the final design remain unresolved. In the interim, however, there is a need to establish an approximate characterization of the source term. The NGNP team developed a simplified parametric model to establish mechanistic source term estimates for a set of proposed HTGR configurations.

Scoping Analysis of Source Term and Functional Containment Attenuation Factors

Energy Technology Data Exchange (ETDEWEB)

Pete Lowry

2012-02-01

In order to meet future regulatory requirements, the Next Generation Nuclear Plant (NGNP) Project must fully establish and validate the mechanistic modular high temperature gas-cooled reactor (HTGR) source term. This is not possible at this stage in the project, as significant uncertainties in the final design remain unresolved. In the interim, however, there is a need to establish an approximate characterization of the source term. The NGNP team developed a simplified parametric model to establish mechanistic source term estimates for a set of proposed HTGR configurations.

Scoping Analysis of Source Term and Functional Containment Attenuation Factors

Energy Technology Data Exchange (ETDEWEB)

Pete Lowry

2012-01-01

In order to meet future regulatory requirements, the Next Generation Nuclear Plant (NGNP) Project must fully establish and validate the mechanistic modular high temperature gas-cooled reactor (HTGR) source term. This is not possible at this stage in the project, as significant uncertainties in the final design remain unresolved. In the interim, however, there is a need to establish an approximate characterization of the source term. The NGNP team developed a simplified parametric model to establish mechanistic source term estimates for a set of proposed HTGR configurations.

License - TMBETA-GENOME | LSDB Archive [Life Science Database Archive metadata

Lifescience Database Archive (English)

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License - KAIKOcDNA | LSDB Archive [Life Science Database Archive metadata

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Myanmar exploration hitting stride on 1989-90 licensing round blocks

International Nuclear Information System (INIS)

Khin, J.A.; Johnston, D.

1992-01-01

This paper reports that following licensing efforts in 1989-90, Myanmar has been gearing up with activity both onshore and offshore. The industry gave a strong response to the first round of exploration licensing. The license awards in the first round carried fairly aggressive work commitments in terms of both dollars and timing. Work commitments on each of the first nine blocks ranged from $12 million to $70 million for each block. Most companies committed to spudding their first wells within the first 12-14 months. The drilling results are starting to come in. Although no significant oil discovery has been made yet, the country expects to speed up its exploration activities in the next few years. Following the first round of licensing onshore, Myanmar Oil and Gas Enterprise (MOGE), the national oil company, is negotiating terms for offshore blocks as well as additional onshore blocks for improved oil recovery (IOR) and rehabilitation/redevelopment rights for existing fields

Review of radionuclide source terms used for performance-assessment analyses

International Nuclear Information System (INIS)

Barnard, R.W.

1993-06-01

Two aspects of the radionuclide source terms used for total-system performance assessment (TSPA) analyses have been reviewed. First, a detailed radionuclide inventory (i.e., one in which the reactor type, decay, and burnup are specified) is compared with the standard source-term inventory used in prior analyses. The latter assumes a fixed ratio of pressurized-water reactor (PWR) to boiling-water reactor (BWR) spent fuel, at specific amounts of burnup and at 10-year decay. TSPA analyses have been used to compare the simplified source term with the detailed one. The TSPA-91 analyses did not show a significant difference between the source terms. Second, the radionuclides used in source terms for TSPA aqueous-transport analyses have been reviewed to select ones that are representative of the entire inventory. It is recommended that two actinide decay chains be included (the 4n+2 ''uranium'' and 4n+3 ''actinium'' decay series), since these include several radionuclides that have potentially important release and dose characteristics. In addition, several fission products are recommended for the same reason. The choice of radionuclides should be influenced by other parameter assumptions, such as the solubility and retardation of the radionuclides

Actinide Source Term Program, position paper. Revision 1

International Nuclear Information System (INIS)

Novak, C.F.; Papenguth, H.W.; Crafts, C.C.; Dhooge, N.J.

1994-01-01

The Actinide Source Term represents the quantity of actinides that could be mobilized within WIPP brines and could migrate with the brines away from the disposal room vicinity. This document presents the various proposed methods for estimating this source term, with a particular focus on defining these methods and evaluating the defensibility of the models for mobile actinide concentrations. The conclusions reached in this document are: the 92 PA open-quotes expert panelclose quotes model for mobile actinide concentrations is not defensible; and, although it is extremely conservative, the open-quotes inventory limitsclose quotes model is the only existing defensible model for the actinide source term. The model effort in progress, open-quotes chemical modeling of mobile actinide concentrationsclose quotes, supported by a laboratory effort that is also in progress, is designed to provide a reasonable description of the system and be scientifically realistic and supplant the open-quotes Inventory limitsclose quotes model

Development of source term PIRT of Fukushima Daiichi NPPs accident

International Nuclear Information System (INIS)

Suehiro, S.; Okamoto, K.

2017-01-01

The severe accident evaluation committee of AESJ (Atomic Energy Society of Japan) developed the thermal hydraulic PIRT (Phenomena Identification and Ranking Table) and the source term PIRT based on findings during the Fukushima Daiichi NPPs accident. These PIRTs aimed to explore the debris distribution and the current condition in the NPPs with high accuracy and to extract higher priority from the aspect of the sophistication of the analytical technology to predict the severe accident phenomena by the code. The source term PIRT was divided into 3 phases for the time domain and 9 categories for the spatial domain. The 68 phenomena were extracted and the importance from viewpoint of the source term was ranked through brainstorming and discussion. This paper describes the developed source term PIRT list and summarized the high ranked phenomena in each phase. (author)

The latest results from source term research. Overview and outlook

Energy Technology Data Exchange (ETDEWEB)

Herranz, Luis E. [Centro de Investigaciones Energeticas Medio Ambientales y Tecnologica (CIEMAT), Madrid (Spain); Haste, Tim [Centre d' Etudes de Cadarache, Paul-Lez-Durance (France). Institut de Radioprotection et de Surete Nucleaire (IRSN); Kaerkelae, Teemu [VTT Technical Research Centre of Finland Ltd, Espoo (Finland)

2016-12-15

Source term research has continued internationally for more than 30 years, increasing confidence in calculations of the potential radioactive release to the environment after a severe reactor accident. Important experimental data have been obtained, mainly under international frameworks such as OECD/NEA and EURATOM. Specifically, Phebus FP provides major insights into fission product release and transport. Results are included in severe accident analysis codes. Data from international projects are being interpreted with a view to further improvements in these codes. This paper synthesizes the recent main outcomes from source term research on these topics, and on source term mitigation. It highlights knowledge gaps remaining and discusses ways to proceed. Aside from this further knowledge-driven research, there is consensus on the need to assess the source term predictive ability of current system codes, taking account of scale-up from experiment to reactor conditions.

Mushu, a free- and open source BCI signal acquisition, written in Python.

Science.gov (United States)

Venthur, Bastian; Blankertz, Benjamin

2012-01-01

The following paper describes Mushu, a signal acquisition software for retrieval and online streaming of Electroencephalography (EEG) data. It is written, but not limited, to the needs of Brain Computer Interfacing (BCI). It's main goal is to provide a unified interface to EEG data regardless of the amplifiers used. It runs under all major operating systems, like Windows, Mac OS and Linux, is written in Python and is free- and open source software licensed under the terms of the GNU General Public License.

Source terms derived from analyses of hypothetical accidents, 1950-1986

International Nuclear Information System (INIS)

Stratton, W.R.

1987-01-01

This paper reviews the history of reactor accident source term assumptions. After the Three Mile Island accident, a number of theoretical and experimental studies re-examined possible accident sequences and source terms. Some of these results are summarized in this paper

Glosario de términos utilizados en las licencias de revistas electrónicas Glossary of terms used for electronic journals licenses

Directory of Open Access Journals (Sweden)

Susana Romanos de Tiratel

2006-12-01

Full Text Available Se presentan dos listados del vocabulario utilizado en la redacción de licencias para acceder a revistas electrónicas: 1 los términos en español con sus equivalencias en inglés seguidas de sus definiciones y 2 los términos en inglés con sus equivalencias en español.Two lists of the vocabulary use for the writing of a license to access electronic journals are presented: 1 terms in both Spanish and English followed by their corresponding definition; 2 terms in English followed by their equivalent terms in Spanish.

Open licenses and their compliance with the new private law (new civil code)

OpenAIRE

Kráľ, Štefan

2013-01-01

Computer programs are widely licensed under open (public, open source, free) licenses. This thesis examines whether the open license (especially GNU GPL) is in compliance with the Czech law and which business models are used to generate profit distributing open computer programs. On the basis of analysis of legislation, case law and doctrinal literature the author assesses whether open licenses are admissible under the new Civil Code. The thesis also provides an overview of commonly used busi...

Spent fuel assembly source term parameters

International Nuclear Information System (INIS)

Barrett, P.R.; Foadian, H.; Rashid, Y.R.; Seager, K.D.; Gianoulakis, S.E.

1993-01-01

Containment of cask contents by a transport cask is a function of the cask body, one or more closure lids, and various bolting hardware, and seals associated with the cavity closure and other containment penetrations. In addition, characteristics of cask contents that impede the ability of radionuclides to move from an origin to the external environment also provide containment. In essence, multiple release barriers exist in series in transport casks, and the magnitude of the releasable activity in the cask is considerably lower than the total activity of its contents. A source term approach accounts for the magnitude of the releasable activity available in the cask by assessing the degree of barrier resistance to release provided by material characteristics and inherent barriers that impede the release of radioactive contents. Standardized methodologies for defining the spent-fuel transport packages with specified regulations have recently been developed. An essential part of applying the source term methodology involves characterizing the response of the spent fuel under regulatory conditions of transport. Thermal and structural models of the cask and fuel are analyzed and used to predict fuel rod failure probabilities. Input to these analyses and failure evaluations cover a wide range of geometrical and material properties. An important issue in the development of these models is the sensitivity of the radioactive source term generated during transport to individual parameters such as temperature and fluence level. This paper provides a summary of sensitivity analyses concentrating on the structural response and failure predictions of the spent fuel assemblies

“Terms and conditions of use” for journal articles and scholarly journals : A survey on the licensing processes associated with electronic scholarly materials

Science.gov (United States)

Hidaka, Masako

Copyright policies and terms directly affect the approach taken by journal editors, authors and readers regarding dealing with of articles and/or copyrighted materials. However Japanese academic society publishers have some trouble in licensing processes for copyrighted materials as previous studies pointed out. In 2011 we conducted a survey on “terms and conditions of use” of electronic journal and the licensing practices associated with electronic scholarly materials. The survey showed commercial publishers have enough announcements on reuse of copyrighted materials for readers. On the other hand Japanese academic societies' cares for readers tend to not enough. They publish journals both in Japanese and in English. Subsequently, English and Japanese templates of “terms and conditions of use” for Japanese academic society publishers were proposed. The templates were developed based on an understanding of the International Association of Scientific, Technical and Medical Publishers' “STM Permissions Guidelines,” which were designed to establish a standard and reasonable approach to granting permission for republication to all signatory publishers.The survey showed that Japanese academic society publishers and commercial publishers are facing the same issues regarding acceptable use of electronic supplemental materials for journal articles. This issue remains to be solved.

License - MicrobeDB.jp | LSDB Archive [Life Science Database Archive metadata

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License - Arabidopsis Phenome Database | LSDB Archive [Life Science Database Archive metadata

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License - Togo Picture Gallery | LSDB Archive [Life Science Database Archive metadata

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Licensing of HTGRs in the United States

International Nuclear Information System (INIS)

Fisher, C.R.; Orvis, D.D.

1981-01-01

The licensing history of the high-temperature gas-cooled reactor (HTGR) in the United States is given historical perspective. The experience began with the licensing of the Peach Bottom Atomic Power Station and extends to the continuing experience at the Fort St. Vrain Nuclear Generating Station. Additional experience was obtained from the licensing reviews in the mid-1970s of the large HTGR plants that were to be built by Philadelphia Electric Company and Delmarva Power and Light. Also, information was provided by the licensing review of the General Atomic standard plant by the U.S. Nuclear Regulatory Commission (NRC) at about the same time. These experiences are summarized in terms of the principal design criteria that were required by the regulatory authority for each project. These criteria include specification of the design basis accidents that were postulated for the plant safety analysis. Several technical issues raised by the NRC during their review of the large HTGR are presented. (author)

Licensing of HTGRs in the United States

Energy Technology Data Exchange (ETDEWEB)

Fisher, C. R.; Orvis, D. D. [General Atomic Co., San Diego, CA (USA)

1981-01-15

The licensing history of the high-temperature gas-cooled reactor (HTGR) in the United States is given historical perspective. The experience began with the licensing of the Peach Bottom Atomic Power Station and extends to the continuing experience at the Fort St. Vrain Nuclear Generating Station. Additional experience was obtained from the licensing reviews in the mid-1970s of the large HTGR plants that were to be built by Philadelphia Electric Company and Delmarva Power and Light. Also, information was provided by the licensing review of the General Atomic standard plant by the U.S. Nuclear Regulatory Commission (NRC) at about the same time. These experiences are summarized in terms of the principal design criteria that were required by the regulatory authority for each project. These criteria include specification of the design basis accidents that were postulated for the plant safety analysis. Several technical issues raised by the NRC during their review of the large HTGR are presented.

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License - ConfC | LSDB Archive [Life Science Database Archive metadata

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License - BodyParts3D | LSDB Archive [Life Science Database Archive metadata

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The Role of License Renewal in PLiM for U.S. Nuclear Power Plants

International Nuclear Information System (INIS)

Young, G.G.

2012-01-01

At the 2nd International Symposium on Nuclear Power Plant Life Management (PLiM) in 2007, it was reported that the NRC had approved renewal of operating licenses for 48 nuclear units, which would allow operation for up to 60 years (i.e., an additional 20 years from the original 40-year license term). Of the 104 operating nuclear units in the U.S. in 2007, it was anticipated that almost 100% would eventually pursue license renewal. At that time, it was also concluded that the regulatory process was stable and predictable for license renewal, and that successful PLiM activities were helping to ensure the safety, economic, and political factors in the U.S. remained favorable for continued success with license renewal. The status of license renewal in 2012 is even better than it was in 2007. As of April 2012, the NRC has approved renewal of the operating licenses for 71 nuclear units and has applications under review for 15 more units. In addition, nuclear plant owners of at least 14 more units have announced plans to submit license renewal applications over the next few years. This brings the total of renewed licenses and announced plans for license renewal to 96% of the 104 currently operating nuclear units in the U.S. The prediction that almost 100% would eventually pursue license renewal is assured. This positive trend for long term operation of nuclear power plants in the U.S. is attributed to: (1) the success of PLiM activities in achieving an excellent safety record for the nuclear power industry and in ensuring on-going positive economics for nuclear plant operation, and (2) the stable and predictable regulatory process for license renewal. U.S. efforts are now underway to consider long term operation for more than 60 years and the process of preparing a second round of license renewals for up to 80 years of operation is likely to begin within the next few years. (author)

Establishing control over nuclear materials and radiation sources in Georgia

International Nuclear Information System (INIS)

Basilia, G.

2010-01-01

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

Spallation Neutron Source Accident Terms for Environmental Impact Statement Input

Energy Technology Data Exchange (ETDEWEB)

Devore, J.R.; Harrington, R.M.

1998-08-01

This report is about accidents with the potential to release radioactive materials into the environment surrounding the Spallation Neutron Source (SNS). As shown in Chap. 2, the inventories of radioactivity at the SNS are dominated by the target facility. Source terms for a wide range of target facility accidents, from anticipated events to worst-case beyond-design-basis events, are provided in Chaps. 3 and 4. The most important criterion applied to these accident source terms is that they should not underestimate potential release. Therefore, conservative methodology was employed for the release estimates. Although the source terms are very conservative, excessive conservatism has been avoided by basing the releases on physical principles. Since it is envisioned that the SNS facility may eventually (after about 10 years) be expanded and modified to support a 4-MW proton beam operational capability, the source terms estimated in this report are applicable to a 4-MW operating proton beam power unless otherwise specified. This is bounding with regard to the 1-MW facility that will be built and operated initially. See further discussion below in Sect. 1.2.

Making tradeoffs between the reasons to leave and reasons to stay employed in long-term care homes: perspectives of licensed nursing staff.

Science.gov (United States)

McGilton, Katherine S; Boscart, Veronique M; Brown, Maryanne; Bowers, Barbara

2014-06-01

Turnover of licensed nursing staff in long-term care (LTC) settings (e.g., nursing homes) is a mounting concern and is associated with poor quality of care and low staff morale. Retention and turnover research in LTC have focused primarily on direct care workers (i.e., nurse aides) leaving the issues largely unexplored for licensed nursing staff (i.e., registered nurses and licensed practical nurses). The main objective of this study was to understand factors that influence nurses' intentions to remain employed at their current job. Qualitative descriptive study. Seven nursing homes in Ontario, Canada. A convenience sample of forty-one licensed LTC nurses. Data were collected through focus groups conducted at each of the participating nursing homes. Focus group discussions were transcribed verbatim. Directed content analysis was used to identify and develop themes. Work conditions were a salient element affecting nurses' intention to stay and included impact of regulations on nurse role flexibility and professional judgment, an underfunded system contributing to insufficient resources and staffing, and a lack of supportive leadership. Factors promoting nurses' willingness to stay included the development of meaningful relationships with residents and staff and opportunities for learning and professional development. Nurses also considered personal and life circumstances (e.g., marital status and seniority) when discussing intention to stay. Nurses in this study weighed positive and negative work-related factors as well as personal circumstances to determine their intent to stay. Developing a more individualized approach to address attrition of licensed nurses in LTC may be the most successful strategy for improving retention of highly skilled staff in this sector. Copyright © 2013 Elsevier Ltd. All rights reserved.

Source term estimation during incident response to severe nuclear power plant accidents

International Nuclear Information System (INIS)

McKenna, T.J.; Glitter, J.G.

1988-10-01

This document presents a method of source term estimation that reflects the current understanding of source term behavior and that can be used during an event. The various methods of estimating radionuclide release to the environment (source terms) as a result of an accident at a nuclear power reactor are discussed. The major factors affecting potential radionuclide releases off site (source terms) as a result of nuclear power plant accidents are described. The quantification of these factors based on plant instrumentation also is discussed. A range of accident conditions from those within the design basis to the most severe accidents possible are included in the text. A method of gross estimation of accident source terms and their consequences off site is presented. 39 refs., 48 figs., 19 tabs

License - D-HaploDB | LSDB Archive [Life Science Database Archive metadata

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License - SKIP Stemcell Database | LSDB Archive [Life Science Database Archive metadata

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License - RGP gmap2000 | LSDB Archive [Life Science Database Archive metadata

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License - RGP estmap2001 | LSDB Archive [Life Science Database Archive metadata

Lifescience Database Archive (English)

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Flowsheets and source terms for radioactive waste projections

International Nuclear Information System (INIS)

Forsberg, C.W.

1985-03-01

Flowsheets and source terms used to generate radioactive waste projections in the Integrated Data Base (IDB) Program are given. Volumes of each waste type generated per unit product throughput have been determined for the following facilities: uranium mining, UF 6 conversion, uranium enrichment, fuel fabrication, boiling-water reactors (BWRs), pressurized-water reactors (PWRs), and fuel reprocessing. Source terms for DOE/defense wastes have been developed. Expected wastes from typical decommissioning operations for each facility type have been determined. All wastes are also characterized by isotopic composition at time of generation and by general chemical composition. 70 references, 21 figures, 53 tables

CONTAIN 2.0 code release and the transition to licensing

International Nuclear Information System (INIS)

Murata, K.K.; Griffith, R.O.; Bergeron, K.D.; Tills, J.

1997-10-01

CONTAIN is a reactor accident simulation code developed by Sandia National Laboratories under US Nuclear Regulatory Commission (USNRC) sponsorship to provide integrated analysis of containment phenomena, including those related to nuclear reactor containment loads and radiological source terms. The recently released CONTAIN 2.0 code version represents a significant advance in CONTAIN modeling capabilities over the last major code release (CONTAIN 1.12V). The new modeling capabilities are discussed here. The principal motivation for many of the recent model improvements has been to allow CONTAIN to model the special features in advanced light water reactor (ALWR) designs. The work done in this area is also summarized. In addition to the ALWR work, the USNRC is currently engaged in an effort to qualify CONTAIN for more general use in licensing, with the intent of supplementing or possibly replacing traditional licensing codes. To qualify the CONTAIN code for licensing applications, studies utilizing CONTAIN 2.0 are in progress. A number of results from this effort are presented in this paper to illustrate the code capabilities. In particular, CONTAIN calculations of the NUPEC M-8-1 and ISP-23 experiments and CVTR test number-sign 3 are presented to illustrate (1) the ability of CONTAIN to model non-uniform gas density and/or temperature distributions, and (2) the relationship between such gas distributions and containment loads. CONTAIN and CONTEMPT predictions for a large break loss of coolant accident scenario in the San Onofre plant are also compared

Relation between source term and emergency planning for nuclear power plants

International Nuclear Information System (INIS)

Shi Zhongqi; Yang Ling

1992-01-01

Some background information of the severe accidents and source terms related to the nuclear power plant emergency planning are presented. The new source term information in NUREG-0956 and NUREG-1150, and possible changes in emergency planning requirements in U.S.A. are briefly provided. It is suggested that a principle is used in selecting source terms for establishing the emergency planning policy and a method is used in determining the Emergency Planning Zone (EPZ) size in China. Based on the research results of (1) EPZ size of PWR nuclear power plants being built in China, and (2) impact of reactor size and selected source terms on the EPZ size, it is concluded that the suggested principle and the method are suitable and feasible for PWR nuclear power plants in China

The end game must end before license renewal begins

International Nuclear Information System (INIS)

Allen, S.R.; Edwards, D.W.

1995-01-01

The quest for a process and strategy to achieve license renewal was begun in the mid-1980s with the view that renewal was an imperative. A major portion of the nation's future electric supply seemed to be at stake. For plants who were becoming noncompetitive because of annual capital recovery, license renewal also appeared as the means of survival. These two perceptions led to a third: License renewal should be sought immediately upon completion of the first 20 yr of operation. Although the basic engineering premise of license renewal remains sound, the perceptions regarding timing of an application may be incorrect. This paper suggests that a gauntlet of uncertainty exists for all plants. Further, it is most severe between the 20th and 30th years of operation. Thus, the competitive viability of the plant must be sustained for most of the initial term before license renewal can become a serious option

31 CFR 594.307 - Licenses; general and specific.

Science.gov (United States)

2010-07-01

...) OFFICE OF FOREIGN ASSETS CONTROL, DEPARTMENT OF THE TREASURY GLOBAL TERRORISM SANCTIONS REGULATIONS General Definitions § 594.307 Licenses; general and specific. (a) Except as otherwise specified, the term...

Evolution of source term definition and analysis

International Nuclear Information System (INIS)

Lutz, R.J. Jr.

2004-01-01

The objective of this presentation was to provide an overview of the evolution of accident fission product release analysis methodology and the obtained results; and to provide an overview of the source term implementation analysis in regulatory decisions

The United States nuclear regulatory commission license renewal process

International Nuclear Information System (INIS)

Holian, B.E.

2009-01-01

The United States (U.S.) Nuclear Regulatory Commission (NRC) license renewal process establishes the technical and administrative requirements for the renewal of operating power plant licenses. Reactor ope-rating licenses were originally issued for 40 years and are allowed to be renewed. The review process for license renewal applications (L.R.A.) provides continued assurance that the level of safety provided by an applicant's current licensing basis is maintained for the period of extended operation. The license renewal review focuses on passive, long-lived structures and components of the plant that are subject to the effects of aging. The applicant must demonstrate that programs are in place to manage those aging effects. The review also verifies that analyses based on the current operating term have been evaluated and shown to be valid for the period of extended operation. The NRC has renewed the licenses for 52 reactors at 30 plant sites. Each applicant requested, and was granted, an extension of 20 years. Applications to renew the licenses of 20 additional reactors at 13 plant sites are under review. As license renewal is voluntary, the decision to seek license renewal and the timing of the application is made by the licensee. However, the NRC expects that, over time, essentially all U.S. operating reactors will request license renewal. In 2009, the U.S. has 4 plants that enter their 41. year of ope-ration. The U.S. Nuclear Industry has expressed interest in 'life beyond 60', that is, requesting approval of a second renewal period. U.S. regulations allow for subsequent license renewals. The NRC is working with the U.S. Department of Energy (DOE) on research related to light water reactor sustainability. (author)

License - The Rice Growth Monitoring for The Phenotypic Functional Analysis | LSDB Archive [Life Science Database Archive metadata

Lifescience Database Archive (English)

Full Text Available s Database Last updated : 2011/11/08 You may use this database in compliance with the terms and conditions o...f the license described below. The license specifies the license terms regarding the use of this database an...d the requirements you must follow in using this database. The license for this database... is specified in the Creative Commons Attribution-Share Alike 2.1 Japan . If you use data from this database..., please be sure attribute this database as follows: The Rice Growth Monitoring for the Phenotypic Fu

37 CFR 404.4 - Authority to grant licenses.

Science.gov (United States)

2010-07-01

... past infringement. Any license shall not confer on any person immunity from the antitrust laws or from... immunized from the operation of state or federal law by reason of the source of the grant. [71 FR 11512, Mar...

Probabilistic source term predictions for use with decision support systems

International Nuclear Information System (INIS)

Grindon, E.; Kinniburgh, C.G.

2003-01-01

Full text: Decision Support Systems for use in off-site emergency management, following an incident at a Nuclear Power Plant (NPP) within Europe, are becoming accepted as a useful and appropriate tool to aid decision makers. An area which is not so well developed is the 'upstream' prediction of the source term released into the environment. Rapid prediction of this source term is crucial to the appropriate early management of a nuclear emergency. The initial source term prediction would today be typically based on simple tabulations taking little, or no, account of plant status. It is the interface between the inward looking plant control room team and the outward looking off-site emergency management team that needs to be addressed. This is not an easy proposition as these two distinct disciplines have little common basis from which to communicate their immediate findings and concerns. Within the Euratom Fifth Framework Programme (FP5), complementary approaches are being developed to the pre-release stage; each based on software tools to help bridge this gap. Traditionally source terms (or releases into the environment) provided for use with Decision Support Systems are estimated on a deterministic basis. These approaches use a single, deterministic assumption about plant status. The associated source term represents the 'best estimate' based an available information. No information is provided an the potential for uncertainty in the source term estimate. Using probabilistic methods the outcome is typically a number of possible plant states each with an associated source term and probability. These represent both the best estimate and the spread of the likely source term. However, this is a novel approach and the usefulness of such source term prediction tools is yet to be tested on a wide scale. The benefits of probabilistic source term estimation are presented here; using, as an example, the SPRINT tool developed within the FP5 STERPS project. System for the

NUPLEX Licensing Subcommittee

International Nuclear Information System (INIS)

Edwards, D.W.; Allen, S.R.

1988-01-01

The NUPLEX Licensing Subcommittee was organized to seek a formal license renewal mechanism that institutionalizes the current licensing basis and consequent level of safety of a plant as the legitimate standard for acceptance and approval of an application for extended operation. Along with defining the most workable approach to and scope of review for license renewal, this paper explains the reasons why a regulatory framework is needed by the early 1990s. The initial results of development work on two key issues, licensing criteria and hearing process, are also presented. at this point six potential license renewal criteria have emerged: evaluation of existing monitoring/maintenance programs, revalidation of current licensing basis, conformance to special regulations, evaluation to a safety goal, plant performance history, and environmental assessment. The work on a hearing process has led to the development of two models for future consideration: hybrid legislative and hybrid adjudicatory

77 FR 2057 - Aquamac Corporation; Notice of Termination of License by Implied Surrender and Soliciting...

Science.gov (United States)

2012-01-13

... Corporation; Notice of Termination of License by Implied Surrender and Soliciting Comments and Motions To.... Type of Proceeding: Termination of License by Implied Surrender. b. Project No.: 2927-006. c. Date... authorized, the licensee is in violation of the terms and conditions of the license. l. This notice is...

Source term estimation during incident response to severe nuclear power plant accidents. Draft

Energy Technology Data Exchange (ETDEWEB)

McKenna, T J; Giitter, J

1987-07-01

The various methods of estimating radionuclide release to the environment (source terms) as a result of an accident at a nuclear power reactor are discussed. The major factors affecting potential radionuclide releases off site (source terms) as a result of nuclear power plant accidents are described. The quantification of these factors based on plant instrumentation also is discussed. A range of accident conditions from those within the design basis to the most severe accidents possible are included in the text. A method of gross estimation of accident source terms and their consequences off site is presented. The goal is to present a method of source term estimation that reflects the current understanding of source term behavior and that can be used during an event. (author)

Source term estimation during incident response to severe nuclear power plant accidents. Draft

International Nuclear Information System (INIS)

McKenna, T.J.; Giitter, J.

1987-01-01

The various methods of estimating radionuclide release to the environment (source terms) as a result of an accident at a nuclear power reactor are discussed. The major factors affecting potential radionuclide releases off site (source terms) as a result of nuclear power plant accidents are described. The quantification of these factors based on plant instrumentation also is discussed. A range of accident conditions from those within the design basis to the most severe accidents possible are included in the text. A method of gross estimation of accident source terms and their consequences off site is presented. The goal is to present a method of source term estimation that reflects the current understanding of source term behavior and that can be used during an event. (author)

Sodium Fast Reactor Safety and Licensing Research Plan

International Nuclear Information System (INIS)

Denman, M.; Lachance, J.; Sofu, T.; Bari, R.; Flanagon, G.; Wigeland, R.

2015-01-01

This paper summarizes potential research priorities for the US Department of Energy (DOE) with the intent of improving the licensability of the sodium cooled fast reactor (SFR). In support of this project, five panels were tasked with identifying potential safety related gaps in the available information, data and models needed to support the licensing of an SFR. The areas examined were sodium technology; accident sequences and initiators; source term characterization, codes and methods; and fuels and materials. It is the intent of this paper to utilize a structured and transparent process that incorporates feedback from all interested stakeholders to suggest future funding priorities for SFR research and development. While numerous gaps were identified, two cross-cutting gaps related to knowledge preservation were agreed upon by all panels and should be addressed in the near future. The first gap is a need to re-evaluate the current procedures for removing the applied technology access control designation from old documents. The second cross-cutting gap is the need for a robust knowledge management and preservation system in all SFR research areas. Closure of these and the other identified gaps will require both a reprioritization of funding within DOE as well as a re-evaluation of existing bureaucratic procedures within the DOE associated with applied technology and knowledge management. (author)

Determination of source term for Krsko NPP extended fuel cycle

International Nuclear Information System (INIS)

Nemec, T.; Persic, A.; Zagar, T.; Zefran, B.

2004-01-01

The activity and composition of the potential radioactive releases (source term) is important in the decision making about off-site emergency measures in case of a release into environment. Power uprate of Krsko NPP during modernization in 2000 as well as changing of the fuel type and the core design have influenced the source term value. In 2003 a project of 'Jozef Stefan' Institute and Slovenian nuclear safety administration determined a plantspecific source term for new conditions of fuel type and burnup for extended fuel cycle. Calculations of activity and isotopic composition of the core have been performed with ORIGEN-ARP program. Results showed that the core activity for extended 15 months fuel cycle is slightly lower than for the 12 months cycles, mainly due to larger share of fresh fuel. (author)

Generic data sources for the update of an environmental report in support of license renewal

International Nuclear Information System (INIS)

Mauro, John J.

1991-01-01

Over the past 2 years, our organization has been providing assistance to the NUMARC PLEX working group in matters pertaining to the environmental impacts of license renewal. Part of this support was the identification of data sets and publications that may be useful to the NRC in the preparation of their Environment Report Supplements (ERSs). The following presents a strategy for preparing an ERS, along with references and data sets pertinent to each ER topic. Each section of the ERS should present the following information: (1) Updated information on plant design and operating experience, along with projections of the plant impacts through the end of its currently licensed period of operation. These impacts are used as a baseline against which to compare the projected impacts for the period of license renewal. In addition, the baseline impacts may be compared to the impacts projected in the plant's original Environmental Report and Environmental Impact Statement. (2) Projections of how the impacts may change during the period of license renewal. The purpose of this information will be to determine the degree to which the projected impacts differ significantly from the impacts presented in the original ER and those that have actually occurred during the period of plant operation. We believe that the ERS will reveal that (1) the actual impacts that have occurred during the period of plant operation are comparable to, or less than, those predicted in the original ER, (2) many impacts have been decreasing with time, such as routine radioactive emissions, and (3) the impacts predicted for the period of license renewal will be comparable to, or less than, the baseline impacts. (author)

Accident source terms for boiling water reactors with high burnup cores.

Energy Technology Data Exchange (ETDEWEB)

Gauntt, Randall O.; Powers, Dana Auburn; Leonard, Mark Thomas

2007-11-01

The primary objective of this report is to provide the technical basis for development of recommendations for updates to the NUREG-1465 Source Term for BWRs that will extend its applicability to accidents involving high burnup (HBU) cores. However, a secondary objective is to re-examine the fundamental characteristics of the prescription for fission product release to containment described by NUREG-1465. This secondary objective is motivated by an interest to understand the extent to which research into the release and behaviors of radionuclides under accident conditions has altered best-estimate calculations of the integral response of BWRs to severe core damage sequences and the resulting radiological source terms to containment. This report, therefore, documents specific results of fission product source term analyses that will form the basis for the HBU supplement to NUREG-1465. However, commentary is also provided on observed differences between the composite results of the source term calculations performed here and those reflected NUREG-1465 itself.

Directional Unfolded Source Term (DUST) for Compton Cameras.

Energy Technology Data Exchange (ETDEWEB)

Mitchell, Dean J.; Mitchell, Dean J.; Horne, Steven M.; O' Brien, Sean; Thoreson, Gregory G

2018-03-01

A Directional Unfolded Source Term (DUST) algorithm was developed to enable improved spectral analysis capabilities using data collected by Compton cameras. Achieving this objective required modification of the detector response function in the Gamma Detector Response and Analysis Software (GADRAS). Experimental data that were collected in support of this work include measurements of calibration sources at a range of separation distances and cylindrical depleted uranium castings.

Development of source term evaluation method for Korean Next Generation Reactor

Energy Technology Data Exchange (ETDEWEB)

Lee, Keon Jae; Cheong, Jae Hak; Park, Jin Baek; Kim, Guk Gee [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

1997-10-15

This project had investigate several design features of radioactive waste processing system and method to predict nuclide concentration at primary coolant basic concept of next generation reactor and safety goals at the former phase. In this project several prediction methods of source term are evaluated conglomerately and detailed contents of this project are : model evaluation of nuclide concentration at Reactor Coolant System, evaluation of primary and secondary coolant concentration of reference Nuclear Power Plant(NPP), investigation of prediction parameter of source term evaluation, basic parameter of PWR, operational parameter, respectively, radionuclide removal system and adjustment values of reference NPP, suggestion of source term prediction method of next generation NPP.

Severe accident source term reassessment

International Nuclear Information System (INIS)

Hazzan, M.J.; Gardner, R.; Warman, E.A.; Jacobs, S.B.

1987-01-01

This paper summarizes the status of the reassessment of severe reactor accident source terms, which are defined as the quantity, type, and timing of fission product releases from such accidents. Concentration is on the major results and conclusions of analyses with modern methods for both pressurized water reactors (PWRs) and boiling water reactors (BWRs), and the special case of containment bypass. Some distinctions are drawn between analyses for PWRs and BWRs. In general, the more the matter is examined, the consequences, or probability of serious consequences, seem to be less. (author)

License - Nikkaji-InChI Mapping Table | LSDB Archive [Life Science Database Archive metadata

Lifescience Database Archive (English)

Full Text Available List Contact us Nikkaji-InChI Mapping Table License License to Use This Database Last updated : 2015/05/22 You may use this database...ense specifies the license terms regarding the use of this database and the requirements you must follow in using this database.... The license for this database is specified in the Creative C...ommons Attribution 2.1 Japan . If you use data from this database, please be sure attribute this database as... . With regard to this database, you are licensed to: freely access part or whole of this database, and acqu

Computer Software: Copyright and Licensing Considerations for Schools and Libraries. ERIC Digest.

Science.gov (United States)

Reed, Mary Hutchings

This digest notes that the terms and conditions of computer software package license agreements control the use of software in schools and libraries, and examines the implications of computer software license agreements for classroom use and for library lending policies. Guidelines are provided for interpreting the Copyright Act, and insuring the…

Source term estimation via monitoring data and its implementation to the RODOS system

International Nuclear Information System (INIS)

Bohunova, J.; Duranova, T.

2000-01-01

A methodology and computer code for interpretation of environmental data, i.e. source term assessment, from on-line environmental monitoring network was developed. The method is based on the conversion of measured dose rates to the source term, i.e. airborne radioactivity release rate, taking into account real meteorological data and location of the monitoring points. The bootstrap estimation methodology and bipivot method to estimate the source term from on-site gamma dose rate monitors is used. The mentioned methods provide an estimate of the mean value of the source term and a confidence interval for it. (author)

76 FR 28336 - Domestic Licensing of Source Material-Amendments/Integrated Safety Analysis

Science.gov (United States)

2011-05-17

... produced in the processing of licensed material. Similar hazards that exist at other fuel cycle facilities... CFR part 40 fuel cycle facilities authorized to possess significant quantities of UF6 are both... is a highly reactive and corrosive chemical that presents a substantial inhalation and skin...

Source term estimation for small sized HTRs

International Nuclear Information System (INIS)

Moormann, R.

1992-08-01

Accidents which have to be considered are core heat-up, reactivity transients, water of air ingress and primary circuit depressurization. The main effort of this paper belongs to water/air ingress and depressurization, which requires consideration of fission product plateout under normal operation conditions; for the latter it is clearly shown, that absorption (penetration) mechanisms are much less important than assumed sometimes in the past. Source term estimation procedures for core heat-up events are shortly reviewed; reactivity transients are apparently covered by them. Besides a general literature survey including identification of areas with insufficient knowledge this paper contains some estimations on the thermomechanical behaviour of fission products in water in air ingress accidents. Typical source term examples are also presented. In an appendix, evaluations of the AVR experiments VAMPYR-I and -II with respect to plateout and fission product filter efficiency are outlined and used for a validation step of the new plateout code SPATRA. (orig.)

To License or Not to License Remanufacturing Business?

Directory of Open Access Journals (Sweden)

Zu-Jun Ma

2018-01-01

Full Text Available Many original equipment manufacturers (OEMs face the choice of whether to license an independent remanufacturer (IR to remanufacture their used products. In this paper, we develop closed-loop supply chain models with licensed and unlicensed remanufacturing operations to analyze the competition and cooperation between an OEM and an IR. The OEM sells new products and collects used products through trade-ins, while the IR intercepts the OEM’s cores to produce remanufactured products and sell them in the same market. We derive optimal decisions for each of the two types of firms in licensed and unlicensed remanufacturing scenarios and identify conditions under which the OEM and the IR would be most likely to cooperate with each other in implementing remanufacturing. The results show although it is beneficial for an OEM to license an IR to remanufacture its cores, it is not always necessary for an IR to accept OEM’s authorization. Moreover, we contrast the result for licensed remanufacturing scenario in the decentralized system with that in the centrally coordinated system to quantify potential inefficiency resulting from decentralization of decision making.

Using Bayesian Belief Network (BBN) modelling for Rapid Source Term Prediction. RASTEP Phase 1

International Nuclear Information System (INIS)

Knochenhauer, M.; Swaling, V.H.; Alfheim, P.

2012-09-01

The project is connected to the development of RASTEP, a computerized source term prediction tool aimed at providing a basis for improving off-site emergency management. RASTEP uses Bayesian belief networks (BBN) to model severe accident progression in a nuclear power plant in combination with pre-calculated source terms (i.e., amount, timing, and pathway of released radio-nuclides). The output is a set of possible source terms with associated probabilities. In the NKS project, a number of complex issues associated with the integration of probabilistic and deterministic analyses are addressed. This includes issues related to the method for estimating source terms, signal validation, and sensitivity analysis. One major task within Phase 1 of the project addressed the problem of how to make the source term module flexible enough to give reliable and valid output throughout the accident scenario. Of the alternatives evaluated, it is recommended that RASTEP is connected to a fast running source term prediction code, e.g., MARS, with a possibility of updating source terms based on real-time observations. (Author)

Using Bayesian Belief Network (BBN) modelling for Rapid Source Term Prediction. RASTEP Phase 1

Energy Technology Data Exchange (ETDEWEB)

Knochenhauer, M.; Swaling, V.H.; Alfheim, P. [Scandpower AB, Sundbyberg (Sweden)

2012-09-15

The project is connected to the development of RASTEP, a computerized source term prediction tool aimed at providing a basis for improving off-site emergency management. RASTEP uses Bayesian belief networks (BBN) to model severe accident progression in a nuclear power plant in combination with pre-calculated source terms (i.e., amount, timing, and pathway of released radio-nuclides). The output is a set of possible source terms with associated probabilities. In the NKS project, a number of complex issues associated with the integration of probabilistic and deterministic analyses are addressed. This includes issues related to the method for estimating source terms, signal validation, and sensitivity analysis. One major task within Phase 1 of the project addressed the problem of how to make the source term module flexible enough to give reliable and valid output throughout the accident scenario. Of the alternatives evaluated, it is recommended that RASTEP is connected to a fast running source term prediction code, e.g., MARS, with a possibility of updating source terms based on real-time observations. (Author)

Licensed reactor nuclear safety criteria applicable to DOE reactors

International Nuclear Information System (INIS)

1993-11-01

This document is a compilation and source list of nuclear safety criteria that the Nuclear Regulatory Commission (NRC) applies to licensed reactors; it can be used by DOE and DOE contractors to identify NRC criteria to be evaluated for application to the DOE reactors under their cognizance. The criteria listed are those that are applied to the areas of nuclear safety addressed in the safety analysis report of a licensed reactor. They are derived from federal regulations, USNRC regulatory guides, Standard Review Plan (SRP) branch technical positions and appendices, and industry codes and standards

An overview of the class I structures license renewal industry report

International Nuclear Information System (INIS)

Renfro, L.J.; Statton, J.A.

1991-01-01

License renewal of a commercial nuclear power plant requires verification that systems, structures and components important to license renewal can perform their intended safety functions throughout the license renewal term. The verification of this continuing performance includes a technical evaluation of the effects of age-related degradation. An industry report (IR) sponsored by the nuclear industry was developed which identifies potentially significant age-related degradation mechanisms that may affect Class I structures and evaluates their impact on the ability of the structures to continue to perform their safety functions. Preventive and/or mitigative options are outlined for managing degradation mechanisms that could significantly affect plant performance during the license renewal period. This paper provides a summary of the IR. (author)

Licensing process in Finland

International Nuclear Information System (INIS)

Tiippana, Petteri

2011-01-01

In accordance with the Nuclear Energy Act, the use of nuclear energy constitutes operations subject to license. The licensing process and conditions for granting a license is defined in the legislation. The licenses are applied from and granted by the Government. This paper discusses briefly the licensing process in Finland and also the roles and responsibilities of main stakeholders in licensing. Licensing of a nuclear power plant in Finland has three steps. The first step is the Decision in Principle (DiP). Goal of DiP is to decide whether using nuclear power is for the overall good for the Finnish society. The second step is Construction License (CL) and the goal of CL phase is to determine whether the design of the proposed plant is safe and that the participating organisations are capable of constructing the plant to meet safety goals. The third step is the Operating License (OL) and the goal of the OL phase is to determine whether the plant operates safely and licensee is capable to operate the plant safely. Main stakeholders in the licensing process in Finland are the utility (licensee) interested in using nuclear power in Finland, Ministry of Employment and the Economy (MEE), Government, Parliament, STUK, the municipality siting the plant and the general public. Government grants all licenses, and Parliament has to ratify Government's Decision in Principle. STUK has to assess the safety of the license applications in each step and give statement to the Ministry. Municipality has to agree to site the plant. Both STUK and the municipality have a veto right in the licensing process

Spatial service delivery system for smart licensing & enforcement management

Science.gov (United States)

Wahap, N. A.; Ismail, N. M.; Nor, N. M.; Ahmad, N.; Omar, M. F.; Termizi, A. A. A.; Zainal, D.; Noordin, N. M.; Mansor, S.

2016-06-01

Spatial information has introduced a new sense of urgency for a better understanding of the public needs in term of what, when and where they need services and through which devices, platform or physical locations they need them. The objective of this project is to value- add existing license management process for business premises which comes under the responsibility of Local Authority (PBT). Manipulation of geospatial and tracing technology via mobile platform allows enforcement officers to work in real-time, use a standardized system, improve service delivery, and optimize operation management. This paper will augment the scope and capabilities of proposed concept namely, Smart Licensing/Enforcement Management (SLEm). It will review the current licensing and enforcement practice of selected PBT in comparison to the enhanced method. As a result, the new enhanced system is expected to offer a total solution for licensing/enforcement management whilst increasing efficiency and transparency for smart city management and governance.

Environmental assessment for final rule on nuclear power plant license renewal

International Nuclear Information System (INIS)

1991-12-01

The Atomic Energy Act and Nuclear Regulatory Commission (NRC) regulations provide for the renewal of nuclear power plant operating licenses beyond their initial 40-year term. The Act and NRC regulations, however, do not specify the procedures, criteria, and standards that must be satisfied in order to renew a license. The NRC is promulgating a rule (10 CFR Part 54) to codify such requirements prior to the receipt of applications for license renewal. The NRC has assessed the possible environmental effects of promulgating requirements in 10 CFR Part 54 now rather than employing such requirements in an ad hoc manner in individual licensing actions. The final part 54 rule requires the development of information and analyses to identify aging problems of systems, structures, and components unique to license renewal that will be of concern during the period of extended operation and will not be controlled by existing effective programs. In general, licensee activities for license renewal may involve replacement, refurbishment, inspection, testing, or monitoring. Such actions will be generally be within the range of similar actions taken for plants during the initial operating term. These actions would be primarily confined within the plants with potential for only minor disruption to the environment. It is unlikely that these actions would change the operating conditions of plants in ways that would change the environmental effects already being experienced. Relicensing under existing regulations would also be primarily focused on aging degradation and would likely result in requirements similar to those that will result from relicensing under the final rule

Safety Evaluation Report related to the full-term operating license for Dresden Nuclear Power Station, Unit 2 ( Docket No. 50-237)

International Nuclear Information System (INIS)

1990-10-01

The Safety Evaluation Report for the full-term operating license application filed by Commonwealth Edison Company for the Dresden Nuclear Power Station, Unit 2, has been prepared by the Office of Nuclear Regulation of the US Nuclear Regulatory Commission. The facility is located in Grundy County, Illinois. Subject to favorable resolution of the items discussed in this report, the staff concludes that the facility can continue to be operated without endangering the health and safety of the public. 72 refs

Sodium fast reactor safety and licensing research plan. Volume I.

Energy Technology Data Exchange (ETDEWEB)

Sofu, Tanju (Argonne National Laboratory, Argonne, IL); LaChance, Jeffrey L.; Bari, R. (Brokhaven National Laboratory Upton, NY); Wigeland, Roald (Idaho National Laboratory, Idaho Falls, ID); Denman, Matthew R.; Flanagan, George F. (Oak Ridge National Laboratory, Oak Ridge, TN)

2012-05-01

This report proposes potential research priorities for the Department of Energy (DOE) with the intent of improving the licensability of the Sodium Fast Reactor (SFR). In support of this project, five panels were tasked with identifying potential safety-related gaps in available information, data, and models needed to support the licensing of a SFR. The areas examined were sodium technology, accident sequences and initiators, source term characterization, codes and methods, and fuels and materials. It is the intent of this report to utilize a structured and transparent process that incorporates feedback from all interested stakeholders to suggest future funding priorities for the SFR research and development. While numerous gaps were identified, two cross-cutting gaps related to knowledge preservation were agreed upon by all panels and should be addressed in the near future. The first gap is a need to re-evaluate the current procedures for removing the Applied Technology designation from old documents. The second cross-cutting gap is the need for a robust Knowledge Management and Preservation system in all SFR research areas. Closure of these and the other identified gaps will require both a reprioritization of funding within DOE as well as a re-evaluation of existing bureaucratic procedures within the DOE associated with Applied Technology and Knowledge Management.

Sodium fast reactor safety and licensing research plan - Volume I

International Nuclear Information System (INIS)

Sofu, Tanju; LaChance, Jeffrey L.; Bari, R.; Wigeland, Roald; Denman, Matthew R.; Flanagan, George F.

2012-01-01

This report proposes potential research priorities for the Department of Energy (DOE) with the intent of improving the licensability of the Sodium Fast Reactor (SFR). In support of this project, five panels were tasked with identifying potential safety-related gaps in available information, data, and models needed to support the licensing of a SFR. The areas examined were sodium technology, accident sequences and initiators, source term characterization, codes and methods, and fuels and materials. It is the intent of this report to utilize a structured and transparent process that incorporates feedback from all interested stakeholders to suggest future funding priorities for the SFR research and development. While numerous gaps were identified, two cross-cutting gaps related to knowledge preservation were agreed upon by all panels and should be addressed in the near future. The first gap is a need to re-evaluate the current procedures for removing the Applied Technology designation from old documents. The second cross-cutting gap is the need for a robust Knowledge Management and Preservation system in all SFR research areas. Closure of these and the other identified gaps will require both a reprioritization of funding within DOE as well as a re-evaluation of existing bureaucratic procedures within the DOE associated with Applied Technology and Knowledge Management.

Development of source term evaluation method for Korean Next Generation Reactor(III)

Energy Technology Data Exchange (ETDEWEB)

Lee, Geon Jae; Park, Jin Baek; Lee, Yeong Il; Song, Min Cheonl; Lee, Ho Jin [Korea Advanced Institue of Science and Technology, Taejon (Korea, Republic of)

1998-06-15

This project had investigated irradiation characteristics of MOX fuel method to predict nuclide concentration at primary and secondary coolant using a core containing 100% of all MOX fuel and development of source term evaluation tool. In this study, several prediction methods of source term are evaluated. Detailed contents of this project are : an evaluation of model for nuclear concentration at Reactor Coolant System, evaluation of primary and secondary coolant concentration of reference Nuclear Power Plant using purely MOX fuel, suggestion of source term prediction method of NPP with a core using MOX fuel.

STACE: Source Term Analyses for Containment Evaluations of transport casks

International Nuclear Information System (INIS)

Seager, K.D.; Gianoulakis, S.E.; Barrett, P.R.; Rashid, Y.R.; Reardon, P.C.

1992-01-01

Following the guidance of ANSI N14.5, the STACE methodology provides a technically defensible means for estimating maximum permissible leakage rates. These containment criteria attempt to reflect the true radiological hazard by performing a detailed examination of the spent fuel, CRUD, and residual contamination contributions to the releasable source term. The evaluation of the spent fuel contribution to the source term has been modeled fairly accurately using the STACE methodology. The structural model predicts the cask drop load history, the mechanical response of the fuel assembly, and the probability of cladding breach. These data are then used to predict the amount of fission gas, volatile species, and fuel fines that are releasable from the cask. There are some areas where data are sparse or lacking (e.g., the quantity and size distribution of fuel rod breaches) in which experimental validation is planned. The CRUD spallation fraction is the major area where no quantitative data has been found; therefore, this also requires experimental validation. In the interim, STACE conservatively assumes a 100% spallation fraction for computing the releasable activity. The source term methodology also conservatively assumes that there is 1 Ci of residual contamination available for release in the transport cask. However, residual contamination is still by far the smallest contributor to the source term activity

Licensing activities for advanced reactors in NNC

International Nuclear Information System (INIS)

Chevalier, A.B.H.; Mustoe, J.; Walters, J.; Ingham, E.L.

2001-01-01

NNC has been involved in safety and licensing activities for advanced reactors for many years. Most recently NNC has been involved with national regulators or their representatives for the HTR (High Temperature Reactor) reactor and the possible siting of ITER (International Thermonuclear Experimental Reactor) within Europe. Commonalties between the two activities can be seen, even though one is a fission process and the other based on a completely new technology. Both have the potential to generate power at a very low overall exposure to the public and station staff, but both also need to demonstrate to the regulator the safety of a design which differs from the standard LWR practice. In both concepts passive design features provide a major part of the safety argument, but the detailed assessment and justification of these features in licensing terms still needs to be made. A number of critical safety issues can be identified, which generally apply to any advanced system. These are: Safety categorization, codes and standards; confinement or containment; ALARA; safety code modelling and data; Occupational Exposure; occupational exposures; decommissioning and waste; no evacuation, or no emergency plans. The UK is notable for a flexible licensing regime, which allows a safety case to be built up from first principles, where this is applicable. In addition, experience of licensing gas cooled, water cooled and liquid metal plant, as well as extensive experience outside the UK provides NNC with a unique insight into the different licensing methodologies which can be applied in the licensing process. This paper discusses some possible approaches which could be applied in order to satisfy regulatory demands when addressing the critical issues listed above. (author)

License agreement, employee work

OpenAIRE

Poncová, Veronika

2012-01-01

The rigorous thesis is focused on license agreement and employee work. The aim of the thesis is not only an analysis of the use of a copyrighted work by a person different from the author of the work, but also an analysis of the performance of copyright by a person different from the author of the work. The thesis consists of five chapters. The opening chapter provides a summary of the notion of copyright, its sources at the national and international levels, but also the European Union legis...

USNRC licensing process as related to nuclear criticality safety

International Nuclear Information System (INIS)

Ketzlach, N.

1987-01-01

The U.S. Code of Federal Regulations establishes procedures and criteria for the issuance of licenses to receive title to, own, acquire, deliver, receive, possess, use, and initially transfer special nuclear material; and establishes and provides for the terms and conditions upon which the Nuclear Regulatory Commission (NRC) will issue such licenses. Section 70.22 of the regulations, ''Contents of Applications'', requires that applications for licenses contain proposed procedures to avoid accidental conditions of criticality. These procedures are elements of a nuclear criticality safety program for operations with fissionable materials at fuels and materials facilities (i.e., fuel cycle facilities other than nuclear reactors) in which there exists a potential for criticality accidents. To assist the applicant in providing specific information needed for a nuclear criticality safety program in a license application, the NRC has issued regulatory guides. The NRC requirements for nuclear criticality safety include organizational, administrative, and technical requirements. For purely technical matters on nuclear criticality safety these guides endorse national standards. Others provide guidance on the standard format and content of license applications, guidance on evaluating radiological consequences of criticality accidents, or guidance for dealing with other radiation safety issues. (author)

Source term determination from subcritical multiplication measurements at Koral-1 reactor

International Nuclear Information System (INIS)

Blazquez, J.B.; Barrado, J.M.

1978-01-01

By using an AmBe neutron source two independent procedures have been settled for the zero-power experimental fast-reactor Coral-1 in order to measure the source term which appears in the point kinetical equations. In the first one, the source term is measured when the reactor is just critical with source by taking advantage of the wide range of the linear approach to critical for Coral-1. In the second one, the measurement is made in subcritical state by making use of the previous calibrated control rods. Several applications are also included such as the measurement of the detector dead time, the determinations of the reactivity of small samples and the shape of the neutron importance of the source. (author)

Development regulation regarding with licensing of nuclear installation

International Nuclear Information System (INIS)

Bambang Riyono; Yudi Pramono; Dahlia Cakrawati Sinaga

2011-01-01

Provisions of Article 17 paragraph (3) of Law Number 10 Year 1997 on Nuclear cleary mandates for the establishment of government regulations (GR) on Nuclear licensing containing the requirements and procedure, both from the standpoint of their utilization and installation. To use has been rising GR No.29 Year 2008 on the Use of Ionizing Radiation Sources and Nuclear Materials, while for the installation has been published PP No.43 Year 2006 on Nuclear Reactor Licensing, and BAPETEN Chairman Decree No.3 Year 2006 on Non-reactor Nuclear Installation Licensing. Based on the background of the preparation of both the aforementioned are just regulate the reactor and utilization, not yet fully meet the mandate of Article 17 paragraph (3) of Law No.10 of 1997 on Nuclear, including other nuclear installations. For these reasons, it initiated the need for a separate regulation containing provisions concerning licensing of non-reactor nuclear installations. On the other side from the understanding the legal aspects and interpretations of the Law No.10 of 2004 on the Establishment Regulation Legislation, should be in single mandate of Article 17 paragraph (3) of Law No.10 of 1997 on Nuclear would only produce one of the requirements and procedure for the use or installation, or a maximum of two (2) GR related licensing the use and installation. This is encourages conducted the assessing or studies related to how possible it is according to the legal aspect is justified to combine in one Nuclear licensing regulations regarding both the use and installation, by looking at the complexity of installation and wide scope of utilization of nuclear energy in Indonesia. The results of this paper is expected to provide input in the preparation of GR on licensing of nuclear installations. (author)

Radiation protection and safety guide no. GRPB-G-2: notification and authorization by registration or licensing, exemption and exclusion

International Nuclear Information System (INIS)

Schandorf, C.; Darko, O.; Yeboah, J.; Osei, E.K.; Asiamah, S.D.

1995-01-01

The obligatory requirement for the notification of the Radiation Protection Board and application for authorization by registration or licensing are important elements of the national system for controlling radiation sources and practices which may be potentially harmful to people. The present document provides guidance for Notification and Authorization by Registration or Licensing. In pursuance of the provision of the Radiation Protection Instrument, 1993, L I 1559, Part II C ontrol and Use of Radiation Sources , the present Guide specifies the Radiation Protection Board (RPB) scheme of notification and authorization by registration of licensing. Criteria for exempting and excluding sources and practices from regulatory control are highlighted

Order of 15 October 1992 amending the Order of 26 March 1974 on the competence of persons licensed to use radioelements in unsealed sources for medical uses

International Nuclear Information System (INIS)

1992-01-01

This Order amends the 1974 Order which provides that a license to use artificial radioelements in unsealed sources may only be granted to medical doctors and to holders of a diploma, a certificate attesting studies or other certificate specified in the Order. The 1992 Order adds some requirements regarding specialized diplomas. (NEA)

Libraries and licensing

Directory of Open Access Journals (Sweden)

Maja Žumer

2001-01-01

Full Text Available In the mid 90s, the abundance of various electronic publications exposed libraries to the problems of licensing electronic content. Various licensing principles have been prepared recently to help libraries in the process; it can be said that in general, the knowledge of licensing issues has improved in libraries of all types. Libraries form consortia in order to gain stronger negotiating positions and obtain better conditions.In the article, new licensing principles are presented in more detail, as well as some domestic and foreign experiences with consortia forming.

A Study on Improvement of Algorithm for Source Term Evaluation

International Nuclear Information System (INIS)

Park, Jeong Ho; Park, Do Hyung; Lee, Jae Hee

2010-03-01

The program developed by KAERI for source term assessment of radwastes from the advanced nuclear fuel cycle consists of spent fuel database analysis module, spent fuel arising projection module, and automatic characterization module for radwastes from pyroprocess. To improve the algorithm adopted the developed program, following items were carried out: - development of an algorithm to decrease analysis time for spent fuel database - development of setup routine for a analysis procedure - improvement of interface for spent fuel arising projection module - optimization of data management algorithm needed for massive calculation to estimate source terms of radwastes from advanced fuel cycle The program developed through this study has a capability to perform source term estimation although several spent fuel assemblies with different fuel design, initial enrichment, irradiation history, discharge burnup, and cooling time are processed at the same time in the pyroprocess. It is expected that this program will be very useful for the design of unit process of pyroprocess and disposal system

Creative Commons licenses and the non-commercial condition: Implications for the re-use of biodiversity information.

Science.gov (United States)

Hagedorn, Gregor; Mietchen, Daniel; Morris, Robert A; Agosti, Donat; Penev, Lyubomir; Berendsohn, Walter G; Hobern, Donald

2011-01-01

The Creative Commons (CC) licenses are a suite of copyright-based licenses defining terms for the distribution and re-use of creative works. CC provides licenses for different use cases and includes open content licenses such as the Attribution license (CC BY, used by many Open Access scientific publishers) and the Attribution Share Alike license (CC BY-SA, used by Wikipedia, for example). However, the license suite also contains non-free and non-open licenses like those containing a "non-commercial" (NC) condition. Although many people identify "non-commercial" with "non-profit", detailed analysis reveals that significant differences exist and that the license may impose some unexpected re-use limitations on works thus licensed. After providing background information on the concepts of Creative Commons licenses in general, this contribution focuses on the NC condition, its advantages, disadvantages and appropriate scope. Specifically, it contributes material towards a risk analysis for potential re-users of NC-licensed works.

Source terms in relation to air cleaning

International Nuclear Information System (INIS)

Bernero, R.M.

1985-01-01

There are two sets of source terms for consideration in air cleaning, those for routine releases and those for accident releases. With about 1000 reactor years of commercial operating experience in the US done, there is an excellent data base for routine and expected transient releases. Specifications for air cleaning can be based on this body of experience with confidence. Specifications for air cleaning in accident situations is another matter. Recent investigations of severe accident behavior are offering a new basis for source terms and air cleaning specifications. Reports by many experts in the field describe an accident environment notably different from previous models. It is an atmosphere heavy with aerosols, both radioactive and inert. Temperatures are sometimes very high; radioiodine is typically in the form of cesium iodide aerosol particles; other nuclides, such as tellurium, are also important aerosols. Some of the present air cleaning requirements may be very important in light of these new accident behavior models. Others may be wasteful or even counterproductive. The use of the new data on accident behavior models to reevaluate requirements promptly is discussed

Source-term reevaluation for US commercial nuclear power reactors: a status report

International Nuclear Information System (INIS)

Herzenberg, C.L.; Ball, J.R.; Ramaswami, D.

1984-12-01

Only results that had been discussed publicly, had been published in the open literature, or were available in preliminary reports as of September 30, 1984, are included here. More than 20 organizations are participating in source-term programs, which have been undertaken to examine severe accident phenomena in light-water power reactors (including the chemical and physical behavior of fission products under accident conditions), update and reevaluate source terms, and resolve differences between predictions and observations of radiation releases and related phenomena. Results from these source-term activities have been documented in over 100 publications to date

Radioactive sealed sources: Reasonable accountability, exemption, and licensing activity thresholds -- A technical basis

International Nuclear Information System (INIS)

Lee, D.W.; Shingleton, K.L.

1996-01-01

Perhaps owing to their small size and portability, some radiation accidents/incidents have involved radioactive sealed sources (RSSs). As a result, programs for the control and accountability of RSSs have come to be recommended and emplaced that essentially require RSSs to be controlled in a manner different from bulk, unsealed radioactive material. Crucially determining the total number of RSSs for which manpower-intensive radiation protection surveillance is provided is the individual RSS activity above which such surveillance is required and below which such effort is not considered cost effective. Individual RSS activity thresholds are typically determined through scenarios which impart a chosen internal or external limiting dose to Reference Man under specified exposure conditions. The resultant RSS threshold activity levels have meaning commensurate with the assumed scenario exposure parameters, i.e., if they are realistic and technically based. A review of how the Department of Energy (DOE), the International Atomic Energy Agency (IAEA), and the Nuclear Regulatory Commission (NRC) have determined their respective accountability, exemption, and licensing threshold activity values is provided. Finally, a fully explained method using references readily available to practicing health physicists is developed using realistic, technically-based calculation parameters by which RSS threshold activities may be locally generated

Incidents with hazardous radiation sources

International Nuclear Information System (INIS)

Schoenhacker, Stefan

2016-01-01

Incidents with hazardous radiation sources can occur in any country, even those without nuclear facilities. Preparedness for such incidents is supposed to fulfill globally agreed minimum standards. Incidents are categorized in incidents with licensed handling of radiation sources as for material testing, transport accidents of hazardous radiation sources, incidents with radionuclide batteries, incidents with satellites containing radioactive inventory, incidents wit not licensed handling of illegally acquired hazardous radiation sources. The emergency planning in Austria includes a differentiation according to the consequences: incidents with release of radioactive materials resulting in restricted contamination, incidents with release of radioactive materials resulting in local contamination, and incidents with the hazard of e@nhanced exposure due to the radiation source.

Accident source terms for Light-Water Nuclear Power Plants. Final report

International Nuclear Information System (INIS)

Soffer, L.; Burson, S.B.; Ferrell, C.M.; Lee, R.Y.; Ridgely, J.N.

1995-02-01

In 1962 tile US Atomic Energy Commission published TID-14844, ''Calculation of Distance Factors for Power and Test Reactors'' which specified a release of fission products from the core to the reactor containment for a postulated accident involving ''substantial meltdown of the core''. This ''source term'', tile basis for tile NRC's Regulatory Guides 1.3 and 1.4, has been used to determine compliance with tile NRC's reactor site criteria, 10 CFR Part 100, and to evaluate other important plant performance requirements. During the past 30 years substantial additional information on fission product releases has been developed based on significant severe accident research. This document utilizes this research by providing more realistic estimates of the ''source term'' release into containment, in terms of timing, nuclide types, quantities and chemical form, given a severe core-melt accident. This revised ''source term'' is to be applied to the design of future light water reactors (LWRs). Current LWR licensees may voluntarily propose applications based upon it

Reassessment of the technical bases for estimating source terms. Draft report for comment

International Nuclear Information System (INIS)

Silberberg, M.; Mitchell, J.A.; Meyer, R.O.; Pasedag, W.F.; Ryder, C.P.; Peabody, C.A.; Jankowski, M.W.

1985-07-01

NUREG-0956 describes the NRC staff and contractor efforts to reassess and update the agency's analytical procedures for estimating accident source terms for nuclear power plants. The effort included development of a new source term analytical procedure - a set of computer codes - that is intended to replace the methodology of the Reactor Safety Study (WASH-1400) and to be used in reassessing the use of TID-14844 assumptions (10 CFR 100). NUREG-0956 describes the development of these codes, the demonstration of the codes to calculate source terms for specific cases, the peer review of this work, some perspectives on the overall impact of new source terms on plant risks, the plans for related research projects, and the conclusions and recommendations resulting from the effort

ORNL's NRC-sponsored HTGR safety and licensing analysis activities for Fort St. Vrain and advanced reactors

International Nuclear Information System (INIS)

Ball, S.J.; Cleveland, J.C.; Harrington, R.M.

1985-01-01

The ORNL safety analysis program for the HTGR was established in 1974 to provide technical assistance to the USNRC on licensing questions for both Fort St. Vrain and advanced plant concepts. The emphasis has been on development of major component and system dynamic simulation codes, and use of these codes to analyze specific licensing-related scenarios. The program has also emphasized code verification, using Fort St. Vrain data where applicable, and comparing results with industry-generated codes. By the use of model and parameter adjustment routines, safety-significant uncertainties have been identified. A major part of the analysis work has been done for the Fort St. Vrain HTGR, and has included analyses of FSAR accident scenario re-evaluations, the core block oscillation problem, core support thermal stress questions, technical specification upgrade review, and TMI action plan applicability studies. The large, 2240-MW(t) cogeneration lead plant design was analyzed in a multi-laboratory cooperative effort to estimate fission product source terms from postulated severe accidents

Pennsylvania Source Term Tracking System

International Nuclear Information System (INIS)

1992-08-01

The Pennsylvania Source Term Tracking System tabulates surveys received from radioactive waste generators in the Commonwealth of radioactive waste is collected each quarter from generators using the Low-Level Radioactive Waste Management Quarterly Report Form (hereafter called the survey) and then entered into the tracking system data base. This personal computer-based tracking system can generate 12 types of tracking reports. The first four sections of this reference manual supply complete instructions for installing and setting up the tracking system on a PC. Section 5 presents instructions for entering quarterly survey data, and Section 6 discusses generating reports. The appendix includes samples of each report

Reactor licensing

International Nuclear Information System (INIS)

Harvie, J.D.

2002-01-01

This presentation discusses reactor licensing and includes the legislative basis for licensing, other relevant legislation , the purpose of the Nuclear Safety and Control Act, important regulations, regulatory document, policies, and standards. It also discusses the role of the CNSC, its mandate and safety philosophy

Using Bayesian Belief Network (BBN) modelling for rapid source term prediction. Final report

Energy Technology Data Exchange (ETDEWEB)

Knochenhauer, M.; Swaling, V.H.; Dedda, F.D.; Hansson, F.; Sjoekvist, S.; Sunnegaerd, K. [Lloyd' s Register Consulting AB, Sundbyberg (Sweden)

2013-10-15

The project presented in this report deals with a number of complex issues related to the development of a tool for rapid source term prediction (RASTEP), based on a plant model represented as a Bayesian belief network (BBN) and a source term module which is used for assigning relevant source terms to BBN end states. Thus, RASTEP uses a BBN to model severe accident progression in a nuclear power plant in combination with pre-calculated source terms (i.e., amount, composition, timing, and release path of released radio-nuclides). The output is a set of possible source terms with associated probabilities. One major issue has been associated with the integration of probabilistic and deterministic analyses are addressed, dealing with the challenge of making the source term determination flexible enough to give reliable and valid output throughout the accident scenario. The potential for connecting RASTEP to a fast running source term prediction code has been explored, as well as alternative ways of improving the deterministic connections of the tool. As part of the investigation, a comparison of two deterministic severe accident analysis codes has been performed. A second important task has been to develop a general method where experts' beliefs can be included in a systematic way when defining the conditional probability tables (CPTs) in the BBN. The proposed method includes expert judgement in a systematic way when defining the CPTs of a BBN. Using this iterative method results in a reliable BBN even though expert judgements, with their associated uncertainties, have been used. It also simplifies verification and validation of the considerable amounts of quantitative data included in a BBN. (Author)

Using Bayesian Belief Network (BBN) modelling for rapid source term prediction. Final report

International Nuclear Information System (INIS)

Knochenhauer, M.; Swaling, V.H.; Dedda, F.D.; Hansson, F.; Sjoekvist, S.; Sunnegaerd, K.

2013-10-01

The project presented in this report deals with a number of complex issues related to the development of a tool for rapid source term prediction (RASTEP), based on a plant model represented as a Bayesian belief network (BBN) and a source term module which is used for assigning relevant source terms to BBN end states. Thus, RASTEP uses a BBN to model severe accident progression in a nuclear power plant in combination with pre-calculated source terms (i.e., amount, composition, timing, and release path of released radio-nuclides). The output is a set of possible source terms with associated probabilities. One major issue has been associated with the integration of probabilistic and deterministic analyses are addressed, dealing with the challenge of making the source term determination flexible enough to give reliable and valid output throughout the accident scenario. The potential for connecting RASTEP to a fast running source term prediction code has been explored, as well as alternative ways of improving the deterministic connections of the tool. As part of the investigation, a comparison of two deterministic severe accident analysis codes has been performed. A second important task has been to develop a general method where experts' beliefs can be included in a systematic way when defining the conditional probability tables (CPTs) in the BBN. The proposed method includes expert judgement in a systematic way when defining the CPTs of a BBN. Using this iterative method results in a reliable BBN even though expert judgements, with their associated uncertainties, have been used. It also simplifies verification and validation of the considerable amounts of quantitative data included in a BBN. (Author)

Source term model evaluations for the low-level waste facility performance assessment

Energy Technology Data Exchange (ETDEWEB)

Yim, M.S.; Su, S.I. [North Carolina State Univ., Raleigh, NC (United States)

1995-12-31

The estimation of release of radionuclides from various waste forms to the bottom boundary of the waste disposal facility (source term) is one of the most important aspects of LLW facility performance assessment. In this work, several currently used source term models are comparatively evaluated for the release of carbon-14 based on a test case problem. The models compared include PRESTO-EPA-CPG, IMPACTS, DUST and NEFTRAN-II. Major differences in assumptions and approaches between the models are described and key parameters are identified through sensitivity analysis. The source term results from different models are compared and other concerns or suggestions are discussed.

An investigation of the closure problem applied to reactor accident source terms

International Nuclear Information System (INIS)

Brearley, I.R.; Nixon, W.; Hayns, M.R.

1987-01-01

The closure problem, as considered here, focuses attention on the question of when in current research programmes enough has been learned about the source terms for reactor accident releases. Noting that current research is tending to reduce the estimated magnitude of the aerosol component of atmospheric, accidental releases, several possible criteria for closure are suggested. Moreover, using the reactor accident consequence model CRACUK, the effect of gradually reducing the aerosol release fractions of a pressurized water reactor (PWR2) source term (as defined in the WASH-1400 study) is investigated and the implications of applying the suggested criteria to current source term research discussed. (author)

Safety Evaluation Report related to the full-term operating license for Millstone Nuclear Power Station, Unit No. 1 (Docket No. 50-245). Supplement No. 1

International Nuclear Information System (INIS)

1986-08-01

This report, prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission, supplements the Safety Evaluation Report (NUREG-1143, October 1985). It fulfills a commitment to provide the Advisory Committee on Reactor Safeguards report, identifies the changes that have occurred since the Safety Evaluation Report was issued, and specifies the effective lifetime for the Full-Term Operating License

Future of Open Source systems

Directory of Open Access Journals (Sweden)

Karel Charvát

2010-02-01

Full Text Available Software distribution strategies have many aspects and can be analysed by reviewing different incisions of a strategy. The focus of this paper is on Licensing aspect involves licensing strategy, licensing risks, licensing enforcement costs. Furthermore, by formulating licensing strategy main technical and logistical aspects are predicted also. The key issues of this paper are different business modes for FOSS software and also SWOT analysis of usage and development of FOSS software from point of view of different user groups. This analysis was provided as part of work of Humboldt IP and collaborative@rural IP. Currently this strategy are important issue of members of Czech Centre for Science and Society and WirelessInfo Living Lab, where the models based on dual licensing are key strategy.Keywords: Open Source, Licensing, FOSS base business models. SWOT analysis, Knowledge society, Knowledge economy

Sodium fast reactor safety and licensing research plan - Volume II

International Nuclear Information System (INIS)

Ludewig, H.; Powers, D.A.; Hewson, John C.; LaChance, Jeffrey L.; Wright, A.; Phillips, J.; Zeyen, R.; Clement, B.; Garner, Frank; Walters, Leon; Wright, Steve; Ott, Larry J.; Suo-Anttila, Ahti Jorma; Denning, Richard; Ohshima, Hiroyuki; Ohno, S.; Miyhara, S.; Yacout, Abdellatif; Farmer, M.; Wade, D.; Grandy, C.; Schmidt, R.; Cahalen, J.; Olivier, Tara Jean; Budnitz, R.; Tobita, Yoshiharu; Serre, Frederic; Natesan, Ken; Carbajo, Juan J.; Jeong, Hae-Yong; Wigeland, Roald; Corradini, Michael; Thomas, Justin; Wei, Tom; Sofu, Tanju; Flanagan, George F.; Bari, R.; Porter D.

2012-01-01

Expert panels comprised of subject matter experts identified at the U.S. National Laboratories (SNL, ANL, INL, ORNL, LBL, and BNL), universities (University of Wisconsin and Ohio State University), international agencies (IRSN, CEA, JAEA, KAERI, and JRC-IE) and private consultation companies (Radiation Effects Consulting) were assembled to perform a gap analysis for sodium fast reactor licensing. Expert-opinion elicitation was performed to qualitatively assess the current state of sodium fast reactor technologies. Five independent gap analyses were performed resulting in the following topical reports: (1) Accident Initiators and Sequences (i.e., Initiators/Sequences Technology Gap Analysis), (2) Sodium Technology Phenomena (i.e., Advanced Burner Reactor Sodium Technology Gap Analysis), (3) Fuels and Materials (i.e., Sodium Fast Reactor Fuels and Materials: Research Needs), (4) Source Term Characterization (i.e., Advanced Sodium Fast Reactor Accident Source Terms: Research Needs), and (5) Computer Codes and Models (i.e., Sodium Fast Reactor Gaps Analysis of Computer Codes and Models for Accident Analysis and Reactor Safety). Volume II of the Sodium Research Plan consolidates the five gap analysis reports produced by each expert panel, wherein the importance of the identified phenomena and necessities of further experimental research and code development were addressed. The findings from these five reports comprised the basis for the analysis in Sodium Fast Reactor Research Plan Volume I.

Sodium fast reactor safety and licensing research plan. Volume II.

Energy Technology Data Exchange (ETDEWEB)

Ludewig, H. (Brokhaven National Laboratory, Upton, NY); Powers, D. A.; Hewson, John C.; LaChance, Jeffrey L.; Wright, A. (Argonne National Laboratory, Argonne, IL); Phillips, J.; Zeyen, R. (Institute for Energy Petten, Saint-Paul-lez-Durance, France); Clement, B. (IRSN/DPAM.SEMIC Bt 702, Saint-Paul-lez-Durance, France); Garner, Frank (Radiation Effects Consulting, Richland, WA); Walters, Leon (Advanced Reactor Concepts, Los Alamos, NM); Wright, Steve; Ott, Larry J. (Oak Ridge National Laboratory, Oak Ridge, TN); Suo-Anttila, Ahti Jorma; Denning, Richard (Ohio State University, Columbus, OH); Ohshima, Hiroyuki (Japan Atomic Energy Agency, Ibaraki, Japan); Ohno, S. (Japan Atomic Energy Agency, Ibaraki, Japan); Miyhara, S. (Japan Atomic Energy Agency, Ibaraki, Japan); Yacout, Abdellatif (Argonne National Laboratory, Argonne, IL); Farmer, M. (Argonne National Laboratory, Argonne, IL); Wade, D. (Argonne National Laboratory, Argonne, IL); Grandy, C. (Argonne National Laboratory, Argonne, IL); Schmidt, R.; Cahalen, J. (Argonne National Laboratory, Argonne, IL); Olivier, Tara Jean; Budnitz, R. (Lawrence Berkeley National Laboratory, Berkeley, CA); Tobita, Yoshiharu (Japan Atomic Energy Agency, Ibaraki, Japan); Serre, Frederic (Centre d' %C3%94etudes nucl%C3%94eaires de Cadarache, Cea, France); Natesan, Ken (Argonne National Laboratory, Argonne, IL); Carbajo, Juan J. (Oak Ridge National Laboratory, Oak Ridge, TN); Jeong, Hae-Yong (Korea Atomic Energy Research Institute, Daejeon, Korea); Wigeland, Roald (Idaho National Laboratory, Idaho Falls, ID); Corradini, Michael (University of Wisconsin-Madison, Madison, WI); Thomas, Justin (Argonne National Laboratory, Argonne, IL); Wei, Tom (Argonne National Laboratory, Argonne, IL); Sofu, Tanju (Argonne National Laboratory, Argonne, IL); Flanagan, George F. (Oak Ridge National Laboratory, Oak Ridge, TN); Bari, R. (Brokhaven National Laboratory, Upton, NY); Porter D. (Idaho National Laboratory, Idaho Falls, ID); Lambert, J. (Argonne National Laboratory, Argonne, IL); Hayes, S. (Idaho National Laboratory, Idaho Falls, ID); Sackett, J. (Idaho National Laboratory, Idaho Falls, ID); Denman, Matthew R.

2012-05-01

Expert panels comprised of subject matter experts identified at the U.S. National Laboratories (SNL, ANL, INL, ORNL, LBL, and BNL), universities (University of Wisconsin and Ohio State University), international agencies (IRSN, CEA, JAEA, KAERI, and JRC-IE) and private consultation companies (Radiation Effects Consulting) were assembled to perform a gap analysis for sodium fast reactor licensing. Expert-opinion elicitation was performed to qualitatively assess the current state of sodium fast reactor technologies. Five independent gap analyses were performed resulting in the following topical reports: (1) Accident Initiators and Sequences (i.e., Initiators/Sequences Technology Gap Analysis), (2) Sodium Technology Phenomena (i.e., Advanced Burner Reactor Sodium Technology Gap Analysis), (3) Fuels and Materials (i.e., Sodium Fast Reactor Fuels and Materials: Research Needs), (4) Source Term Characterization (i.e., Advanced Sodium Fast Reactor Accident Source Terms: Research Needs), and (5) Computer Codes and Models (i.e., Sodium Fast Reactor Gaps Analysis of Computer Codes and Models for Accident Analysis and Reactor Safety). Volume II of the Sodium Research Plan consolidates the five gap analysis reports produced by each expert panel, wherein the importance of the identified phenomena and necessities of further experimental research and code development were addressed. The findings from these five reports comprised the basis for the analysis in Sodium Fast Reactor Research Plan Volume I.

Nuclear reactor operator licensing

International Nuclear Information System (INIS)

Bursey, R.J.

1978-01-01

The Atomic Energy Act of 1954, which was amended in 1974 by the Energy Reorganization Act, established the requirement that individuals who had the responsibility of operating the reactors in nuclear power plants must be licensed. Section 107 of the act states ''the Commission shall (1) prescribe uniform conditions for licensing individuals; (2) determine the qualifications of such individuals; and (3) issue licenses to such individuals in such form as the Commission may prescribe.'' The article discusses the types of licenses, the selection and training of individuals, and the administration of the Nuclear Regulatory Commission licensing examinations

Operator licensing examiner standards

International Nuclear Information System (INIS)

1987-05-01

The Operator Licensing Examiner Standards provide policy and guidance to NRC examiners and establish the procedures and practices for examining and licensing of applicants for NRC operator licenses pursuant to Part 55 of Title 10 of the Code of Federal Regulations (10 CFR 55). They are intended to assist NRC examiners and facility licensees to understand the examination process better and to provide for equitable and consistent administration of examinations to all applicants by NRC examiners. These standards are not a substitute for the operator licensing regulations and are subject to revision or other internal operator examination licensing policy changes

Data assimilation and source term estimation during the early phase of a nuclear accident

Energy Technology Data Exchange (ETDEWEB)

Golubenkov, A.; Borodin, R. [SPA Typhoon, Emergency Centre (Russian Federation); Sohier, A.; Rojas Palma, C. [Centre de l`Etude de l`Energie Nucleaire, Mol (Belgium)

1996-02-01

The mathematical/physical base of possible methods to model the source term during an accidental release of radionuclides is discussed. Knowledge of the source term is important in view of optimizing urgent countermeasures to the population. In most cases however, it will be impossible to assess directly the release dynamics. Therefore methods are under development in which the source term is modelled, based on the comparison of off-site monitoring data and model predictions using an atmospheric dispersion model. The degree of agreement between the measured and calculated characteristics of the radioactive contamination of the air and the ground surface is an important criterion in this process. Due to the inherent complexity, some geometrical transformations taking space-time discrepancies between observed and modelled contamination fields are defined before the source term is adapted. This work describes the developed algorithms which are also tested against data from some tracer experiments performed in the past. This method is also used to reconstruct the dynamics of the Chernobyl source term. Finally this report presents a concept of software to reconstruct a multi-isotopic source term in real-time.

Data assimilation and source term estimation during the early phase of a nuclear accident

International Nuclear Information System (INIS)

Golubenkov, A.; Borodin, R.; Sohier, A.; Rojas Palma, C.

1996-02-01

The mathematical/physical base of possible methods to model the source term during an accidental release of radionuclides is discussed. Knowledge of the source term is important in view of optimizing urgent countermeasures to the population. In most cases however, it will be impossible to assess directly the release dynamics. Therefore methods are under development in which the source term is modelled, based on the comparison of off-site monitoring data and model predictions using an atmospheric dispersion model. The degree of agreement between the measured and calculated characteristics of the radioactive contamination of the air and the ground surface is an important criterion in this process. Due to the inherent complexity, some geometrical transformations taking space-time discrepancies between observed and modelled contamination fields are defined before the source term is adapted. This work describes the developed algorithms which are also tested against data from some tracer experiments performed in the past. This method is also used to reconstruct the dynamics of the Chernobyl source term. Finally this report presents a concept of software to reconstruct a multi-isotopic source term in real-time

Licensing in an international triopoly

Science.gov (United States)

Ferreira, Fernanda A.; Ferreira, Flávio

2011-12-01

We study the effects of entry of two foreign firms on domestic welfare in the presence of licensing, when the incumbent is technologically superior to the entrants. We consider two different situations: (i) the cost-reducing innovation is licensed to both entrants; (ii) the cost-reducing innovation is licensed to just one of the entrants. We analyse three kind of license: (lump-sum) fixed-fee; (per-unit) royalty; and two-part tariff, that is a combination of a fixed-fee and a royalty. We prove that a two part tariff is never an optimal licensing scheme for the incumbent. Moreover, (i) when the technology is licensed to the two entrants, the optimal contract consists of a licensing with only output royalty; and (ii) when the technology is licensed to just one of the entrants, the optimal contract consists of a licensing with only a fixed-fee.

IRIS Licensing Status

International Nuclear Information System (INIS)

Kling, Charles L.; Carelli, Mario D.

2006-01-01

The International Reactor Innovative and Secure (IRIS) nuclear power plant is well into the pre-application review process with the US NRC and has accomplished its first near term goal of obtaining US NRC feedback on the long term testing program. To date, the IRIS team has submitted to the US NRC a number of documents patterned after the Evaluation Model Development and Assessment Process (EMDAP) outlined in Regulatory Guide 1,203. They have covered a detailed description of IRIS, initial safety analysis results, PIRT development for limiting transients, scaling analysis and a description of the test program. The IRIS Safety-by-Desing TM intrinsically eliminates and/or significantly reduces the consequences of traditional LWR accidents. In addition, the fewer passive safety systems are similar in principle to those of the US NRC approved AP1000 design. For these reasons, the IRIS testing program only needs to include those features unique to the IRIS design. NRC feedback was that the planned test program appeared to be complete and could generate sufficient information to support a Design Certification (DC) submittal. The US NRC has also stated that a DC application must include complete information regarding the test program. On this basis the IRIS team has initiated an aggressive program to conduct IRIS testing to support a DC submittal by the end of 2008. Subsequent US NRC review should be expeditious because of the AP1000 precedent, allowing IRIS to obtain its Final Design Approval (FDA) in 2012; thereby, maintaining its goal of deployment in the 2015-2017 time frame. The next steps in the pre-application review process will be to provide the US NRC with a road map of the anticipated IRIS licensing process, a review of current licensing requirements showing that IRIS meets or exceeds all current criteria and information to support the long term goal of redefining the Emergency Planning Zone (EPZ)

Licensing of nuclear facilities according to the Bulgarian Act on the Safe Use of Nuclear Energy

International Nuclear Information System (INIS)

Stoyanova-Todorova, P.

2004-01-01

The new Bulgarian Act on the Safe Use of Nuclear Energy /Nuclear Act/ has replaced the former Act on the Use of Nuclear Energy for Peaceful Purposes. The new Nuclear Act covers the activities involving nuclear energy and sources of ionising radiation mainly by establishing a consistent licensing regime. About 13 regulations specifying the provisions of the Nuclear Act have been recently adopted by the Council of Ministers, the most important one being the Regulation on the Procedure for Issue of Licenses and Permits for the Safe Use of Nuclear Energy. The Chairman of the Nuclear Regulatory Agency (NRA) is authorised by the law to consider any application for issue of a license or a permit under the Bulgarian Nuclear Act. The procedure starts with an application, filed with the NRA, and continues about nine months. The final decision could be for issuing of the license or permit or a refusal for issuing the claimed document. The denial must be grounded and is subject to appeal. The Nuclear Act prescribes the conditions for issuing of two types of licensing documents (authorisations): licenses and permits. From a legal point of view the two types of licensing documents have one and the same nature - they are individual administrative acts according to the Bulgarian law. That is why there is no difference between them in terms of the issuing procedure. The difference between licenses and permits could be explained as follows: while a license is issued for reiterated activities, a permit is issued for non-reoccurring activities, this division being a specific feature of the Bulgarian Nuclear Act. In the field of nuclear facilities usage only one type of license is provided for by the Nuclear Act - a license for operation of a nuclear facility unit. For the rest of the activities issuing of permits is envisaged, those permits being in compliance with the main stages of the authorisation process formulated by the IAEA, following the step-by-step approach - siting, design

Impact of New Radiation Safety Standards on Licensing Requirements of Nuclear Power Plant

International Nuclear Information System (INIS)

Strohal, P.; Subasic, D.; Valcic, I.

1996-01-01

As the outcomes of the newly introduced safety philosophies, new and more strict safety design requirements for nuclear installation are expected to be introduced. New in-depth defence measures should be incorporated into the design and operation procedure for a nuclear installation, to compensate for potential failures in protection or safety measures. The new requirements will also apply to licensing of NPP's operation as well as to licensing of nuclear sites, especially for radioactive waste disposal sites. This paper intends to give an overview of possible impacts of new internationally agreed basic safety standards with respect to NPP and related technologies. Recently issued new basic safety standards for radiation protection are introducing some new safety principles which may have essential impact on future licensing requirements regarding nuclear power plants and radioactive waste installations. These new standards recognize exposures under normal conditions ('practices') and intervention conditions. The term interventions describes the human activities that seek to reduce the existing radiation exposure or existing likelihood of incurring exposure which is not part of a controlled practice. The other new development in safety standards is the introduction of so called potential exposure based on the experience gained from a number of radiation accidents. This exposure is not expected to be delivered with certainty but it may result from an accident at a source or owing to an event or sequence of events of a probabilistic nature, including equipment failures and operating errors. (author)

EDF source term reduction project main outcomes and further developments

International Nuclear Information System (INIS)

Ranchoux, Gilles; Bonnefon, Julien; Benfarah, Moez; Wintergerst Matthieu; Gressier, Frederic; Leclercq, Stephanie

2012-09-01

The dose reduction is a strategic purpose for EDF in link with the stakes of, nuclear acceptability, respect of regulation and productivity gains. This consists not only in improving the reactor shutdown organization (time spent in control area, biological shielding,...) but also in improving the radiological state of the unit and the efficiency of the source term reduction operations. Since 2003, EDF has been running an innovative project called 'Source Term Reduction' federating the different EDF research and engineering centers in order to: - participate to the long term view about Radiological Protection issues (international feedback analyses), - develop contamination prediction tools (OSCAR software) suitable for the industrial needs (operating units and EPR design), - develop scientific models useful for the understanding of contamination mechanisms to support the strategic decision processes, - carry on with updating and analyzing of contamination measurements feedback in corrosion products (EMECC and CZT campaigns), - carry on with the operational support at short or middle term by optimizing startup and shutdown processes, pre-oxidation or and by improving purification efficiency or material characteristics. This paper will show in a first part the main 2011 results in occupational exposure (collective and individual dose, RCS index...). In a second part, an overview of the main EDF outcomes of the last 3 years in the field of source term reduction will be presented. Future developments extended to contamination issues in EDF NPPs will be also pointed out in this paper. (authors)

14 CFR 431.73 - Continuing accuracy of license application; application for modification of license.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 4 2010-01-01 2010-01-01 false Continuing accuracy of license application; application for modification of license. 431.73 Section 431.73 Aeronautics and Space COMMERCIAL SPACE... Conditions § 431.73 Continuing accuracy of license application; application for modification of license. (a...

Long-Term Trends in the Sources of Boston Crime Guns

Directory of Open Access Journals (Sweden)

Anthony A. Braga

2017-10-01

Full Text Available Analyses of firearm trace data, most collected over relatively brief periods, suggest that a noteworthy share of guns used in crime were recently diverted from legal commerce. This article analyzes a longitudinal database on firearm recoveries by the Boston Police Department between 1981 and 2015 and successfully traced handguns between 1991 and 2015. The percentage of high-capacity semiautomatic pistols among recovered handguns increased dramatically in the 1980s and 1990s. A persistent share of traced handguns were imported from licensed dealers in southern states and an increasing share first purchased at licensed dealers in New Hampshire and Maine. These analyses suggest that market disruption strategies may reduce illegal diversions of new handguns from licensed dealers and the passage of one-handgun-a-month laws may influence where criminals get their guns.

Code Forking, Governance, and Sustainability in Open Source Software

OpenAIRE

Juho Lindman; Linus Nyman

2013-01-01

The right to fork open source code is at the core of open source licensing. All open source licenses grant the right to fork their code, that is to start a new development effort using an existing code as its base. Thus, code forking represents the single greatest tool available for guaranteeing sustainability in open source software. In addition to bolstering program sustainability, code forking directly affects the governance of open source initiatives. Forking, and even the mere possibilit...

Backup Sourcing Decisions for Coping with Supply Disruptions under Long-Term Horizons

Directory of Open Access Journals (Sweden)

Jing Hou

2016-01-01

Full Text Available This paper studies a buyer’s inventory control problem under a long-term horizon. The buyer has one major supplier that is prone to disruption risks and one backup supplier with higher wholesale price. Two kinds of sourcing methods are available for the buyer: single sourcing with/without contingent supply and dual sourcing. In contingent sourcing, the backup supplier is capacitated and/or has yield uncertainty, whereas in dual sourcing the backup supplier has an incentive to offer output flexibility during disrupted periods. The buyer’s expected cost functions and the optimal base-stock levels using each sourcing method under long-term horizon are obtained, respectively. The effects of three risk parameters, disruption probability, contingent capacity or uncertainty, and backup flexibility, are examined using comparative studies and numerical computations. Four sourcing methods, namely, single sourcing with contingent supply, dual sourcing, and single sourcing from either of the two suppliers, are also compared. These findings can be used as a valuable guideline for companies to select an appropriate sourcing strategy under supply disruption risks.

NRC's license renewal regulations

International Nuclear Information System (INIS)

Akstulewicz, Francis

1991-01-01

In order to provide for the continuity of the current generation of nuclear power plant operating licenses and at the same time ensure the health and safety of the public, and the quality of the environment, the US Nuclear Regulatory Commission (NRC) established a goal of developing and issuing regulations and regulatory guidance for license renewal in the early 1990s. This paper will discuss some of those activities underway to achieve this goal. More specifically, this paper will discuss the Commission's regulatory philosophy for license renewal and the two major license renewal rule makings currently underway. The first is the development of a new Part 54 to address procedural and technical requirements for license renewal; the second is a revision to existing Part 51 to exclude environmental issues and impacts from consideration during the license renewal process. (author)

Changing mobility patterns and road mortality among pre-license teens in a late licensing country: an epidemiological study.

Science.gov (United States)

Twisk, Divera; Bos, Niels; Shope, Jean T; Kok, Gerjo

2013-04-11

magnitude of the problem because of the physical resilience of young adolescents that leads to high survival rates but probably also to long term disabilities. In addition, to explore the generalizability of these results, international comparisons among and between early and late licensing countries are necessary, especially in relation to moped riding as an alternative for car driving.

Reevaluation of HFIR source term: Supplement 2

International Nuclear Information System (INIS)

Thomas, W.E.

1986-11-01

The HFIR source term has been reevaluated to assess the impact of the increase in core lifetime from 15 to 24 days. Calculations were made to determine the nuclide activities of the iodines, noble gases, and other fission products. The results show that there is no significant change in off-site dose due to the increased fuel cycle for the release scenario postulated in ORNL-3573

Licensed Healthcare Facilities

Data.gov (United States)

California Natural Resource Agency — The Licensed Healthcare Facilities point layer represents the locations of all healthcare facilities licensed by the State of California, Department of Health...

2015 Business Licenses

Data.gov (United States)

City of Jackson, Mississippi — This data displays all business license information for the year of 2015. This information details license classifications and status. This information will updated...

Teenagers' licensing decisions and their views of licensing policies: a national survey.

Science.gov (United States)

Williams, Allan F

2011-08-01

One objective was to determine teenage licensing rates on a national basis, interest in early licensure, and reasons for delay. A second objective was to learn teenagers' opinions about licensing policies, important in states considering ways to upgrade their current licensing systems. One thousand three hundred eighty-three 15- to 18-year-olds completed an online survey in November 2010. They were drawn from a nationally representative panel of US households recruited using probability-based sampling. The panel included cell phone-only households, and Internet access was provided to those without it. Weighting procedures were applied so that the study population represented the national US population of 15- to 18-year-olds. Most teens said that they were interested in getting a license as soon as legally possible, but many had not started the process. At 16, teens were about equally divided among those who had not started, those in the learner stage, and those with a restricted or full license. At 18, 62 percent had full licenses; 22 percent had not started. For those old enough to start, lack of a car, costs, parent availability, ability to get around without a car, and being busy with other activities were leading reasons for delay. The majority of teens were not in favor of higher licensing ages. Forty-six percent thought the minimum learner age should be 16; 30 percent thought the full license age should be 18 or older. The majority approved of night (78%) and passenger (57%) restrictions, and 85 and 93 percent endorsed cell phone and texting bans, respectively. When these policies were packaged together in a single law that included an age 16 start, night, passenger, cell phone and texting bans, and a full license at age 18, 74 percent of teens were in favor. Teenagers are not as supportive of strong licensing policies as parents of teens, but there is evidence that they will support comprehensive policies likely to lead to further reductions in teen crash

Consideration of emergency source terms for pebble-bed high temperature gas-cooled reactor

International Nuclear Information System (INIS)

Tao, Liu; Jun, Zhao; Jiejuan, Tong; Jianzhu, Cao

2009-01-01

Being the last barrier in the nuclear power plant defense-in-depth strategy, emergency planning (EP) is an integrated project. One of the key elements in this process is emergency source terms selection. Emergency Source terms for light water reactor (LWR) nuclear power plant (NPP) have been introduced in many technical documents, and advanced NPP emergency planning is attracting attention recently. Commercial practices of advanced NPP are undergoing in the world, pebble-bed high-temperature gas-cooled reactor (HTGR) power plant is under construction in China which is considered as a representative of advanced NPP. The paper tries to find some pieces of suggestion from our investigation. The discussion of advanced NPP EP will be summarized first, and then the characteristics of pebble-bed HTGR relating to EP will be described. Finally, PSA insights on emergency source terms selection and current pebble-bed HTGR emergency source terms suggestions are proposed

Evaluation of the LMFBR cover gas source term and synthesis of the associated R and D

International Nuclear Information System (INIS)

Balard, F.; Carluec, B.

1996-01-01

At the end of the seventies and the beginning of the eighties, there appeared a pressing need of experimental results to assess the LMFBR's safety level. Because of the urgency, analytical studies were not systematically undertaken and maximum credible cover gas instantaneous source terms (radionuclides core release fraction) were got directly from crude out-of-pile experiment interpretations. Two types of studies and mock-ups were undertaken depending on the timescale of the phenomena: instantaneous source terms (corresponding to an unlikely energetic core disruptive accident CDA), and delayed ones (tens of minutes to some hours). The experiments performed in this frame are reviewed in this presentation: 1) instantaneous source term: - FAUST experiments: I, Cs, UO2 source terms (FzK, Germany), - FAST experiments : pool depth influence on non volatile source term (USA), - CARAVELLE experiments: nonvolatile source term in SPX1 geometry (CEA, France); 2) delayed source term: - NALA experiments: I, Cs, Sr, UO2 source term (FzK, Germany), - PAVE experiments: I source term (CEA, France), - NACOWA experiments: cover gas aerosols enrichment in I and Cs (FzK, Germany) - other French experiments in COPACABANA and GULLIVER facilities. The volatile fission products release is tightly bound to sodium evaporation and a large part of the fission products is dissolved in the liquid sodium aerosols present in the cover gas. Thus the knowledge of the amount of aerosol release to the cover gas is important for the evaluation of the source term. The maximum credible cover gas instantaneous source terms deduced from the experiments have led to conservative source terms to be taken into account in safety analysis. Nevertheless modelling attempts of the observed (in-pile or out-of-pile) physico-chemical phenomena have been undertaken for extrapolation to the reactor case. The main topics of this theoretical research are as follows: fission products evaporation in the cover gas (Fz

State Licenses & Permits

Data.gov (United States)

Small Business Administration — Starting a business? Confused about whether you need a business license or permit? Virtually every business needs some form of license or permit to operate legally....

Operator licensing examiner standards

International Nuclear Information System (INIS)

1983-10-01

The Operator Licensing Examiner Standards provide policy and guidance to NRC examiners and establish the procedures and practices for examining and licensing of applicants for NRC operator licenses pursuant to Part 55 of Title 10 of the Code of Federal Regulations (10 CFR 55). They are intended to assist NRC examiners and facility licensees to understand the examination process better and to provide for equitable and consistent administration of examinations to all applicants by NRC examiners. These standards are not a substitute for the operator licensing regulations and are subject to revision or other internal operator examination licensing policy changes. As appropriate, these standards will be revised periodically to accommodate comments and reflect new information or experience

The SLOWPOKE licensing model

Energy Technology Data Exchange (ETDEWEB)

Snell, V. G.; Takats, F.; Szivos, K.

1989-08-15

The SLOWPOKE Energy System (SES-10) is a 10 MW heating reactor that has been developed in Canada. It will be capable of running without a licensed operator in continuous attendance, and will be sited in urban areas. It has forgiving safety characteristics, including transient time-scales of the order of hours. A process called `up-front` licensing has been evolved in Canada to identify, and resolve, regulatory concerns early in the process. Because of the potential market in Hungary for nuclear district heating, a licensing plan has been developed that incorporates Canadian licensing experience, identifies specific Hungarian requirements, and reduces the risk of licensing delays by seeking agreement of all parties at an early stage in the program.

License to build

International Nuclear Information System (INIS)

Huntelaar, Mark; Vos, Renate de; Roobol, Lars

2007-01-01

Full text: A new license under the nuclear power act is applied for at the Dutch Government for the building of a High Active Repackaging Unit (HAVA-VU in Dutch) at NRG in Petten, The Netherlands. This new building is necessary to comply with our nuclear license to dispose of high active nuclear waste at Petten to the intermediate storage facility (COVRA). In the first part of this paper attention is given to the formal procedure followed by the Government, what type of documents are to be submitted, what time frames are followed, how citizen participation is organized, and as final result a new license. In the second part more detailed information is given about the present license renewal needed for the High Active Repackaging Unit

Aging management review for license renewal and plant life management

International Nuclear Information System (INIS)

Rinckel, M.A.; Young, G.G.

2002-01-01

Full text: United States nuclear power plants are initially licensed for a period of 40-years. The 40-year term, which was established by the Atomic Energy Commission in the 1950s, is believed to be based on engineering judgement and is consistent with the typical amortization schedule for purchasing fossil power plants. Under 10 CFR Part 54, the license renewal rule, additional terms of 20-years may be obtained through the preparation of a license renewal application that must be reviewed and approved by the Nuclear Regulatory Commission (NRC). The license renewal rule requires that applicants perform ageing management reviews on passive long-lived structures and components to demonstrate that ageing will be managed during the period of extended operation (i.e., additional 20 years of operation). ageing of active components, which are excluded from 10 CFR Part 54, is accomplished through the Maintenance Rule, 10 CFR Part 65, using performance-based monitoring. The license renewal rule, 10 CFR Part 54, was initially published in 1991. After significant interaction with the nuclear industry from 1991 through 1994, the NRC revised the rule in 1995 to focus on passive long-lived structures and components. In 1998, the first two applications for license renewal were submitted to the NRC by Baltimore Gas and Electric for the two-unit Calvert Cliffs nuclear power plant and by Duke Energy for the three-unit Oconee nuclear power plant. In March 2000, the NRC approved the application for the two-unit Calvert Cliffs nuclear power plant for an additional 20 years. Two months later, the NRC approved the renewal of the operating licenses for the three-unit Oconee nuclear station. The NRC completed these reviews in a timely, predictable, and stable manner. As of February 2002, the NRC has approved renewal of operating licenses for eight nuclear units and has applications under review for 15 more units. Twelve additional companies have notified the NRC of their intention to seek

A nuclear source term analysis for spacecraft power systems

International Nuclear Information System (INIS)

McCulloch, W.H.

1998-01-01

All US space missions involving on board nuclear material must be approved by the Office of the President. To be approved the mission and the hardware systems must undergo evaluations of the associated nuclear health and safety risk. One part of these evaluations is the characterization of the source terms, i.e., the estimate of the amount, physical form, and location of nuclear material, which might be released into the environment in the event of credible accidents. This paper presents a brief overview of the source term analysis by the Interagency Nuclear Safety Review Panel for the NASA Cassini Space Mission launched in October 1997. Included is a description of the Energy Interaction Model, an innovative approach to the analysis of potential releases from high velocity impacts resulting from launch aborts and reentries

PFLOTRAN-RepoTREND Source Term Comparison Summary.

Energy Technology Data Exchange (ETDEWEB)

Frederick, Jennifer M

2018-03-01

Code inter-comparison studies are useful exercises to verify and benchmark independently developed software to ensure proper function, especially when the software is used to model high-consequence systems which cannot be physically tested in a fully representative environment. This summary describes the results of the first portion of the code inter-comparison between PFLOTRAN and RepoTREND, which compares the radionuclide source term used in a typical performance assessment.

Low-level waste disposal performance assessments - Total source-term analysis

Energy Technology Data Exchange (ETDEWEB)

Wilhite, E.L.

1995-12-31

Disposal of low-level radioactive waste at Department of Energy (DOE) facilities is regulated by DOE. DOE Order 5820.2A establishes policies, guidelines, and minimum requirements for managing radioactive waste. Requirements for disposal of low-level waste emplaced after September 1988 include providing reasonable assurance of meeting stated performance objectives by completing a radiological performance assessment. Recently, the Defense Nuclear Facilities Safety Board issued Recommendation 94-2, {open_quotes}Conformance with Safety Standards at Department of Energy Low-Level Nuclear Waste and Disposal Sites.{close_quotes} One of the elements of the recommendation is that low-level waste performance assessments do not include the entire source term because low-level waste emplaced prior to September 1988, as well as other DOE sources of radioactivity in the ground, are excluded. DOE has developed and issued guidance for preliminary assessments of the impact of including the total source term in performance assessments. This paper will present issues resulting from the inclusion of all DOE sources of radioactivity in performance assessments of low-level waste disposal facilities.

Rules for the licensing of new experiments in BR2: application to the test irradiation of new MTR-fuels

International Nuclear Information System (INIS)

Joppen, F.

2000-01-01

New types of MTR fuel elements are being developed and require a qualification before routine operation could be authorized. During the test irradiation the new fuel elements .are considered as experimental devices and their irradiation is allowed according to the procedures for experiments. Authorization is based on the advice .of a consultative committee on experiments. This procedure is valid as long as the irradiation is covered by the actual reactor license. An additional license or an amendment is only required if due to the experiment the risk for the workers or the environment is increased in a significant way. A few experimental fuel plates loaded in the primary loop of the reactor will not increase this risk. The source term for potential radioactive releases remains more or less the same. The probability for an accident can be limited by restricting the heat flux and surface temperature. (author)

PLOTLIB: a computerized nuclear waste source-term library storage and retrieval system

International Nuclear Information System (INIS)

Marshall, J.R.; Nowicki, J.A.

1978-01-01

The PLOTLIB code was written to provide computer access to the Nuclear Waste Source-Term Library for those users with little previous computer programming experience. The principles of user orientation, quick accessibility, and versatility were extensively employed in the development of the PLOTLIB code to accomplish this goal. The Nuclear Waste Source-Term Library consists of 16 ORIGEN computer runs incorporating a wide variety of differing light water reactor (LWR) fuel cycles and waste streams. The typical isotopic source-term data consist of information on watts, curies, grams, etc., all of which are compiled as a function of time after reactor discharge and unitized on a per metric ton heavy metal basis. The information retrieval code, PLOTLIB, is used to process source-term information requests into computer plots and/or user-specified output tables. This report will serve both as documentation of the current data library and as an operations manual for the PLOTLIB computer code. The accompanying input description, program listing, and sample problems make this code package an easily understood tool for the various nuclear waste studies under way at the Office of Waste Isolation

Analyses of operating license renewal for nuclear power plants in USA

International Nuclear Information System (INIS)

Chiba, Goro

2007-01-01

Although the originally-approved operating period for nuclear power plants in the U.S. is 40 years, the operating periods of many plants have been extended by license renewal for another 20 years. On the other hand, in Japan, plant life management is carried out assuming long-term operation of the plant, and the electric power company submits reports, such as aging technology assessment, and receives evaluation by the authorities. In this paper, the situation regarding plant life management was investigated and a Japan-U.S. comparison was made. As a result, differences were found in the procedure, the background, the manpower, the review period, etc. in Japan and the U.S. but there is no difference between Japan and the U.S. in aiming for a check of the integrity of components, assuming long-term operation for 60 years. Moreover, trend analysis using the overseas fault database of INSS examined the effect on the preservation activities of a license renewal. As a result, there is a tendency for license renewal not to be applied for in units in which the number of aging faults increases with the increase in elapsed years. The U.S. license renewal system was considered to be effective in plant life management, and suggested the validity of plant life management in Japan which is employing the equivalent system to the U.S. (author)

Low-level radioactive waste source terms for the 1992 integrated data base

International Nuclear Information System (INIS)

Loghry, S.L.; Kibbey, A.H.; Godbee, H.W.; Icenhour, A.S.; DePaoli, S.M.

1995-01-01

This technical manual presents updated generic source terms (i.e., unitized amounts and radionuclide compositions) which have been developed for use in the Integrated Data Base (IDB) Program of the U.S. Department of Energy (DOE). These source terms were used in the IDB annual report, Integrated Data Base for 1992: Spent Fuel and Radioactive Waste Inventories, Projections, and Characteristics, DOE/RW-0006, Rev. 8, October 1992. They are useful as a basis for projecting future amounts (volume and radioactivity) of low-level radioactive waste (LLW) shipped for disposal at commercial burial grounds or sent for storage at DOE solid-waste sites. Commercial fuel cycle LLW categories include boiling-water reactor, pressurized-water reactor, fuel fabrication, and uranium hexafluoride (UF 6 ) conversion. Commercial nonfuel cycle LLW includes institutional/industrial (I/I) waste. The LLW from DOE operations is category as uranium/thorium fission product, induced activity, tritium, alpha, and open-quotes otherclose quotes. Fuel cycle commercial LLW source terms are normalized on the basis of net electrical output [MW(e)-year], except for UF 6 conversion, which is normalized on the basis of heavy metal requirement [metric tons of initial heavy metal ]. The nonfuel cycle commercial LLW source term is normalized on the basis of volume (cubic meters) and radioactivity (curies) for each subclass within the I/I category. The DOE LLW is normalized in a manner similar to that for commercial I/I waste. The revised source terms are based on the best available historical data through 1992

Impact of source terms on distances to which reactor accident consequences occur

International Nuclear Information System (INIS)

Ostmeyer, R.M.

1982-01-01

Estimates of the distances over which reactor accident consequences might occur are important for development of siting criteria and for emergency response planning. This paper summarizes the results of a series of CRAC2 calculations performed to estimate these distances. Because of the current controversy concerning the magnitude of source terms for severe accidents, the impact of source term reductions upon distance estimates is also examined

The long-term problems of contaminated land: Sources, impacts and countermeasures

International Nuclear Information System (INIS)

Baes, C.F. III.

1986-11-01

This report examines the various sources of radiological land contamination; its extent; its impacts on man, agriculture, and the environment; countermeasures for mitigating exposures; radiological standards; alternatives for achieving land decontamination and cleanup; and possible alternatives for utilizing the land. The major potential sources of extensive long-term land contamination with radionuclides, in order of decreasing extent, are nuclear war, detonation of a single nuclear weapon (e.g., a terrorist act), serious reactor accidents, and nonfission nuclear weapons accidents that disperse the nuclear fuels (termed ''broken arrows'')

Contestable Licensing

OpenAIRE

Zvika Neeman; Gerhard O. Orosel

2000-01-01

We analyze a model of repeated franchise bidding for natural monopoly with contestable licensing - a franchisee halds an (exclusive) license to operate a franchise until another rm offers to pay more for it. In a world where quality is observable but not veri able, the simple regulatory scheme we describe combines market-like incentives with regulatory oversight to generate efficient outcomes.

Using Reactive Transport Modeling to Evaluate the Source Term at Yucca Mountain

Energy Technology Data Exchange (ETDEWEB)

Y. Chen

2001-12-19

The conventional approach of source-term evaluation for performance assessment of nuclear waste repositories uses speciation-solubility modeling tools and assumes pure phases of radioelements control their solubility. This assumption may not reflect reality, as most radioelements (except for U) may not form their own pure phases. As a result, solubility limits predicted using the conventional approach are several orders of magnitude higher then the concentrations of radioelements measured in spent fuel dissolution experiments. This paper presents the author's attempt of using a non-conventional approach to evaluate source term of radionuclide release for Yucca Mountain. Based on the general reactive-transport code AREST-CT, a model for spent fuel dissolution and secondary phase precipitation has been constructed. The model accounts for both equilibrium and kinetic reactions. Its predictions have been compared against laboratory experiments and natural analogues. It is found that without calibrations, the simulated results match laboratory and field observations very well in many aspects. More important is the fact that no contradictions between them have been found. This provides confidence in the predictive power of the model. Based on the concept of Np incorporated into uranyl minerals, the model not only predicts a lower Np source-term than that given by conventional Np solubility models, but also produces results which are consistent with laboratory measurements and observations. Moreover, two hypotheses, whether Np enters tertiary uranyl minerals or not, have been tested by comparing model predictions against laboratory observations, the results favor the former. It is concluded that this non-conventional approach of source term evaluation not only eliminates over-conservatism in conventional solubility approach to some extent, but also gives a realistic representation of the system of interest, which is a prerequisite for truly understanding the long-term

Using Reactive Transport Modeling to Evaluate the Source Term at Yucca Mountain

International Nuclear Information System (INIS)

Y. Chen

2001-01-01

The conventional approach of source-term evaluation for performance assessment of nuclear waste repositories uses speciation-solubility modeling tools and assumes pure phases of radioelements control their solubility. This assumption may not reflect reality, as most radioelements (except for U) may not form their own pure phases. As a result, solubility limits predicted using the conventional approach are several orders of magnitude higher then the concentrations of radioelements measured in spent fuel dissolution experiments. This paper presents the author's attempt of using a non-conventional approach to evaluate source term of radionuclide release for Yucca Mountain. Based on the general reactive-transport code AREST-CT, a model for spent fuel dissolution and secondary phase precipitation has been constructed. The model accounts for both equilibrium and kinetic reactions. Its predictions have been compared against laboratory experiments and natural analogues. It is found that without calibrations, the simulated results match laboratory and field observations very well in many aspects. More important is the fact that no contradictions between them have been found. This provides confidence in the predictive power of the model. Based on the concept of Np incorporated into uranyl minerals, the model not only predicts a lower Np source-term than that given by conventional Np solubility models, but also produces results which are consistent with laboratory measurements and observations. Moreover, two hypotheses, whether Np enters tertiary uranyl minerals or not, have been tested by comparing model predictions against laboratory observations, the results favor the former. It is concluded that this non-conventional approach of source term evaluation not only eliminates over-conservatism in conventional solubility approach to some extent, but also gives a realistic representation of the system of interest, which is a prerequisite for truly understanding the long-term

Demonstrating safety during license renewal should not be a large task

International Nuclear Information System (INIS)

Berto, D.S.

1993-01-01

The principal regulatory goal related to nuclear power plant operation is to ensure the health and safety of the public. The principal goal of extended plant operation via the license renewal process is also to ensure the health and safety of the public. The license renewal documentation issued by the Nuclear Regulatory Commission (NRC) provides guidance on what will be acceptable to the NRC in a license renewal application to demonstrate that this goal will be met. Application of this guidance is currently open to wide interpretation, with many of the current approaches proving to be extremely costly, complex, and uncertain of acceptability. This paper evaluates the requirements necessary to ensure the continued health and safety of the public during any license renewal term. This evaluation is based on the stated goals of the License Renewal Rule and on the published bases for the Rule. An approach to License Renewal is recommended that: (1) meets the stated goals of the NRC; (2) is consistent with current regulatory practices; and (3) will continue to ensure the health and safety of the public. This recommended approach is also much less costly than other current approaches, and can be easily agreed to by all participants. This approach will meet regulatory goals, while removing the cost and uncertainty obstacles currently being confronted by utilities. Providing a viable approach to license renewal will allow the renewal process to be pursued by utilities. Without such an approach, safe and reliable nuclear power plants will be permanently shut down at the arbitrary 40 year license limit

AP1000R licensing and deployment in the United States

International Nuclear Information System (INIS)

Jordan, R. P.; Russ, P. A.; Filiak, P. P.; Castiglione, L. L.

2012-01-01

In recent years, both domestic and foreign utilities have turned to the standardized Westinghouse AP1000 plant design in satisfying their near - and long-term - sustainable energy needs. As direct support to these actions, licensing the AP1000 design has played a significant role by providing one of the fundamental bases in clearing regulatory hurdles leading to the start of new plant construction. Within the U.S. alone, Westinghouse AP1000 licensing activities have reached unprecedented milestones with the approvals of both AP1000 Design Certification and Southern Company's combined construction permit and operating license (COL) application directly supporting the construction of two new nuclear plants in Georgia. Further COL application approvals are immediately pending for an additional two AP1000 plants in South Carolina. And, across the U.S. nuclear industry spectrum, there are 10 other COL applications under regulatory review representing some 16 new plants at 10 sites. In total, these actions represent the first wave of new plant licensing under the regulatory approval process since 1978. Fundamental to the Nuclear Regulatory Commission's AP1000 Design Certification is the formal recognition of the AP1000 passive safety design through regulatory acceptance rulemaking. Through recognition and deployment of the AP1000 Design Certification, the utility licensee / operator of this reactor design are now offered an opportunity to use a simplified 'one-step' combined license process, thereby managing substantial back-end construction schedule risk from regulatory and intervention delays. Application of this regulatory philosophy represents both acceptance and encouragement of standardized reactor designs like the AP1000. With the recent AP1000 Design Certification and utility COL acceptances, the fundamental licensing processes of this philosophy have successfully proven the attainment of significant milestones with the next stage licensing actions directed

Licensing, supervision, retrofitting

International Nuclear Information System (INIS)

Steinkemper, H.

1991-01-01

The following proposals for the amendment to the Atomic Energy Act are made: the term of provisions against damage and the content and scope of the principle of commensurability should be defined by law. Their concretization should be left to the level of the statutory instruments and technical codes. In usage the scope of application of the subsequent obligation should be approximated to the category of element relevant to licensing. Lability to indemnification for subsequent obligations should be abolished. The need for a backfitting licence in the case of 'substantial' alterations requires a closer definition. A legal obligation should be placed on operators of nuclear reactors to carry out periodical safety checks. (orig./HSCH) [de

78 FR 73549 - Government-Owned Inventions; Availability for Licensing

Science.gov (United States)

2013-12-06

... extend market coverage for companies and may also be available for licensing. FOR FURTHER INFORMATION... resistance due to the high sequence conservation of the target. More stable than thioesters. Development... makes this invention a novel and potential long-term therapeutic for restoration of exocrine gland...

Licensing procedure by steps, indemnity precaution, control by administrative courts

International Nuclear Information System (INIS)

Sellner, D.

1986-01-01

The author describes three problems of the Wyhl-judgement of the Federal Administrative Court. The terms 'licensing procedure by steps', 'indemnity precaution pursuant to sec. 7, para. 2, No. 3 Atomic Energy Act', and 'control density of administrative courts' are concretized. The author chooses these terms because they have important impulses even for other fields than Atomic Energy Law. (CW) [de

Does Self-Licensing Benefit Self- Regulation Over Time? An Ecological Momentary Assessment Study of Food Temptations

NARCIS (Netherlands)

Prinsen, S.|info:eu-repo/dai/nl/369408217; Evers, C.|info:eu-repo/dai/nl/280594232; Wijngaards, Leoniek; van Vliet, Renee; de Ridder, D.T.D.|info:eu-repo/dai/nl/070706174

2018-01-01

Self-licensing, employing reasons to justify indulgence, may help resolve the conflict between immediate temptations and long-term goals in favor of the former. It was hypothesized that this conflict-resolving potential of self-licensing may benefit self-regulation over time. With a momentary

Developing an Open Source Option for NASA Software

Science.gov (United States)

Moran, Patrick J.; Parks, John W. (Technical Monitor)

2003-01-01

We present arguments in favor of developing an Open Source option for NASA software; in particular we discuss how Open Source is compatible with NASA's mission. We compare and contrast several of the leading Open Source licenses, and propose one - the Mozilla license - for use by NASA. We also address some of the related issues for NASA with respect to Open Source. In particular, we discuss some of the elements in the External Release of NASA Software document (NPG 2210.1A) that will likely have to be changed in order to make Open Source a reality withm the agency.

Nuclear plant license renewal

International Nuclear Information System (INIS)

Gazda, P.A.; Bhatt, P.C.

1991-01-01

During the next 10 years, nuclear plant license renewal is expected to become a significant issue. Recent Electric Power Research Institute (EPRI) studies have shown license renewal to be technically and economically feasible. Filing an application for license renewal with the Nuclear Regulatory Commission (NRC) entails verifying that the systems, structures, and components essential for safety will continue to perform their safety functions throughout the license renewal period. This paper discusses the current proposed requirements for this verification and the current industry knowledge regarding age-related degradation of structures. Elements of a license renewal program incorporating NRC requirements and industry knowledge including a schedule are presented. Degradation mechanisms for structural components, their significance to nuclear plant structures, and industry-suggested age-related degradation management options are also reviewed

The long-term problems of contaminated land: Sources, impacts and countermeasures

Energy Technology Data Exchange (ETDEWEB)

Baes, C.F. III

1986-11-01

This report examines the various sources of radiological land contamination; its extent; its impacts on man, agriculture, and the environment; countermeasures for mitigating exposures; radiological standards; alternatives for achieving land decontamination and cleanup; and possible alternatives for utilizing the land. The major potential sources of extensive long-term land contamination with radionuclides, in order of decreasing extent, are nuclear war, detonation of a single nuclear weapon (e.g., a terrorist act), serious reactor accidents, and nonfission nuclear weapons accidents that disperse the nuclear fuels (termed ''broken arrows'').

Challenges of SMR licensing practices

Energy Technology Data Exchange (ETDEWEB)

Soderholm, K., E-mail: kristiina.soderholm@fortum.com [Fortum Power, Espoo (Finland)

2012-12-15

This paper aims to increase the understanding of high level Nuclear Power Plant (NPP) licensing processes in Finland, France, the UK, Canada and the USA. These countries have been selected for this study because of their different licensing processes and recent actions in new NPP construction. After discussing their similarities and differences, suitable features for Small Modular Reactor licensing can be emphasized and suggested. Some of the studied licensing processes have elements that are already quite well suited for application to SMRs, but all of these different national processes can benefit from studying and implementing lessons learned from SMR specific licensing needs. The main SMR features to take into account in licensing are standardization of the design, modularity, mass production and serial construction. Modularity can be divided into two different categories: the first category is simply a single unit facility constructed of independently engineered modules (e.g., construction process for Westinghouse AP-1000 NPP) and the second is a facility structure composed of many reactor modules where modules are manufactured in factories and installed into the facility as needed (e.g., NuScale Power SMR design). Short construction schedules will not be fully benefited from if the long licensing process prolongs the commissioning and approach to full-power operation. The focus area of this study is to better understand the possibility of SMR deployment in small nuclear countries, such as Finland, which currently has four operating NPPs. The licensing process needs to be simple and clear to make SMR deployment feasible from an economical point of view. This paper uses public information and interviews with experts to establish the overview of the different licensing processes and their main steps. A high-level comparison of the licensing steps has been carried out. Certain aspects of the aviation industry licensing process have also been studied and certain

Understanding Licensing Behavior

DEFF Research Database (Denmark)

Cabaleiro, Goretti; Moreira, Solon; Reichstein, Toke

The potential for rent dissipation has been argued to be the main cause of firms? licensing out behavior being stifled.However, this aspect has been scarcely studied empirically. We draw on rent dissipation arguments, and hypothesize that firms suffering from the not-invented-here (NIH) syndrome......, firms in competitive product markets, and firms that have incurred substantial sunk cost are associated with lower rates of technology out-licensing. We also posit that sunk costs negatively moderate the relationship between competition in the licensor?s product market, and licensing rate. We test our...

Nuclear power stations licensing

International Nuclear Information System (INIS)

Solito, J.

1978-04-01

The judicial aspects of nuclear stations licensing are presented. The licensing systems of the United States, Spain, France and Federal Republic of Germany are focused. The decree n 0 60.824 from July 7 sup(th), 1967 and the following legislation which define the systematic and area of competence in nuclear stations licensing are analysed [pt

Recent advances in the source term area within the SARNET European severe accident research network

International Nuclear Information System (INIS)

Herranz, L.E.; Haste, T.; Kärkelä, T.

2015-01-01

Highlights: • Main achievements of source term research in SARNET are given. • Emphasis on the radiologically important iodine and ruthenium fission products. • Conclusions on FP release, transport in the RCS and containment behaviour. • Significance of large-scale integral experiments to validate the analyses used. • A thorough list of the most recent references on source term research results. - Abstract: Source Term has been one of the main research areas addressed within the SARNET network during the 7th EC Framework Programme of EURATOM. The entire source term domain was split into three major areas: oxidising impact on source term, iodine chemistry in the reactor coolant system and containment and data and code assessment. The present paper synthesises the main technical outcome stemming from the SARNET FWP7 project in the area of source term and includes an extensive list of references in which deeper insights on specific issues may be found. Besides, based on the analysis of the current state of the art, an outlook of future source term research is outlined, where major changes in research environment are discussed (i.e., the end of the Phébus FP project; the end of the SARNET projects; and the launch of HORIZON 2020). Most probably research projects will be streamlined towards: release and transport under oxidising conditions, containment chemistry, existing and innovative filtered venting systems and others. These will be in addition to a number of projects that have been completed or are ongoing under different national and international frameworks, like VERDON, CHIP and EPICUR started under the International Source Term Programme (ISTP), the OECD/CSNI programmes BIP, BIP2, STEM, THAI and THAI2, and the French national programme MIRE. The experimental PASSAM project under the 7th EC Framework programme, focused on source term mitigation systems, is highlighted as a good example of a project addressing potential enhancement of safety systems

Recent advances in the source term area within the SARNET European severe accident research network

Energy Technology Data Exchange (ETDEWEB)

Herranz, L.E., E-mail: luisen.herranz@ciemat.es [Centro de Investigaciones Energeticas Medio Ambientales y Tecnologica, CIEMAT, Avda. Complutense 40, E-28040 Madrid (Spain); Haste, T. [Institut de Radioprotection et de Sûreté Nucléaire, IRSN, BP 3, F-13115 St Paul lez Durance Cedex (France); Kärkelä, T. [VTT Technical Research Centre of Finland, P.O. Box 1000, FI-02044 VTT Espoo (Finland)

2015-07-15

Highlights: • Main achievements of source term research in SARNET are given. • Emphasis on the radiologically important iodine and ruthenium fission products. • Conclusions on FP release, transport in the RCS and containment behaviour. • Significance of large-scale integral experiments to validate the analyses used. • A thorough list of the most recent references on source term research results. - Abstract: Source Term has been one of the main research areas addressed within the SARNET network during the 7th EC Framework Programme of EURATOM. The entire source term domain was split into three major areas: oxidising impact on source term, iodine chemistry in the reactor coolant system and containment and data and code assessment. The present paper synthesises the main technical outcome stemming from the SARNET FWP7 project in the area of source term and includes an extensive list of references in which deeper insights on specific issues may be found. Besides, based on the analysis of the current state of the art, an outlook of future source term research is outlined, where major changes in research environment are discussed (i.e., the end of the Phébus FP project; the end of the SARNET projects; and the launch of HORIZON 2020). Most probably research projects will be streamlined towards: release and transport under oxidising conditions, containment chemistry, existing and innovative filtered venting systems and others. These will be in addition to a number of projects that have been completed or are ongoing under different national and international frameworks, like VERDON, CHIP and EPICUR started under the International Source Term Programme (ISTP), the OECD/CSNI programmes BIP, BIP2, STEM, THAI and THAI2, and the French national programme MIRE. The experimental PASSAM project under the 7th EC Framework programme, focused on source term mitigation systems, is highlighted as a good example of a project addressing potential enhancement of safety systems

10 CFR 150.20 - Recognition of Agreement State licenses.

Science.gov (United States)

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Recognition of Agreement State licenses. 150.20 Section 150.20 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXEMPTIONS AND CONTINUED REGULATORY AUTHORITY... the activities authorized, for an unlimited period of time. (5) Shall comply with all terms and...

Estimation of Source terms for Emergency Planning and Preparedness

Energy Technology Data Exchange (ETDEWEB)

Yi, Chul Un; Chung, Bag Soon; Ahn, Jae Hyun; Yoon, Duk Ho; Jeong, Chul Young; Lim, Jong Dae [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Kang, Sun Gu; Suk, Ho; Park, Sung Kyu; Lim, Hac Kyu; Lee, Kwang Nam [Korea Power Engineering Company Consulting and Architecture Engineers, (Korea, Republic of)

1997-12-31

In this study the severe accident sequences for each plant of concern, which represent accident sequences with a high core damage frequency and significant accident consequences, were selected based on the results of probabilistic safety assessments and source term and time-histories of various safety parameters under severe accidents. Accidents progression analysis for each selected accident sequence was performed by MAAP code. It was determined that the measured values, dose rate and radioisotope concentration, could provide information to the operators on occurrence and timing of core damage, reactor vessel failure, and containment failure during severe accidents. Radioactive concentration in the containment atmosphere, which may be measured by PASS, was estimated. Radioisotope concentration in emergency planning, evaluation of source term behavior in the containment, estimation of core damage degree, analysis of severe accident phenomena, core damage timing, and the amount of radioisotope released to the environment. (author). 50 refs., 60 figs.

Role of library's subscription licenses in promoting open access to scientific research

KAUST Repository

Buck, Stephen

2018-01-01

This presentation, based on KAUST’’s experience to date, will attempt to explain the different ways of bringing Open Access models to scientific Publisher’s licenses. Our dual approach with offset pricing is to redirect subscription money to publishing money and embed green open access deposition terms in understandable language in our license agreements. Resolving the inherent complexities in open access publishing, repository depositions and offsetting models will save libraries money and also time wasted on tedious and unnecessary administration work. Researchers will also save their time with overall clarity and transparency. This will enable trust and, where mistakes are made, and there inevitably will be with untried models, we can learn from these mistakes and make better, more robust services with auto deposition of our articles to our repository fed by Publishers’ themselves. The plan is to cover all Publishers with OA license terms for KAUST author’s right while continuing our subscription to them. There are marketing campaigns, awareness sessions are planned, in addition to establishing Libguides to help researchers, in addition to manage offset pricing models.

Role of library's subscription licenses in promoting open access to scientific research

KAUST Repository

Buck, Stephen

2018-04-30

This presentation, based on KAUST’’s experience to date, will attempt to explain the different ways of bringing Open Access models to scientific Publisher’s licenses. Our dual approach with offset pricing is to redirect subscription money to publishing money and embed green open access deposition terms in understandable language in our license agreements. Resolving the inherent complexities in open access publishing, repository depositions and offsetting models will save libraries money and also time wasted on tedious and unnecessary administration work. Researchers will also save their time with overall clarity and transparency. This will enable trust and, where mistakes are made, and there inevitably will be with untried models, we can learn from these mistakes and make better, more robust services with auto deposition of our articles to our repository fed by Publishers’ themselves. The plan is to cover all Publishers with OA license terms for KAUST author’s right while continuing our subscription to them. There are marketing campaigns, awareness sessions are planned, in addition to establishing Libguides to help researchers, in addition to manage offset pricing models.

Added Value of uncertainty Estimates of SOurce term and Meteorology (AVESOME)

DEFF Research Database (Denmark)

Sørensen, Jens Havskov; Schönfeldt, Fredrik; Sigg, Robert

In the early phase of a nuclear accident, two large sources of uncertainty exist: one related to the source term and one associated with the meteorological data. Operational methods are being developed in AVESOME for quantitative estimation of uncertainties in atmospheric dispersion prediction.......g. at national meteorological services, the proposed methodology is feasible for real-time use, thereby adding value to decision support. In the recent NKS-B projects MUD, FAUNA and MESO, the implications of meteorological uncertainties for nuclear emergency preparedness and management have been studied...... uncertainty in atmospheric dispersion model forecasting stemming from both the source term and the meteorological data is examined. Ways to implement the uncertainties of forecasting in DSSs, and the impacts on real-time emergency management are described. The proposed methodology allows for efficient real...

Learning-by-Licensing: How Chinese Firms Benefit From Licensing-In Technologies

DEFF Research Database (Denmark)

Wang, Yuandi; Roijakkers, N.; Vanhaverbeke, W.

2012-01-01

This paper explores how interfirm variations in their in-licensed technology portfolios influence subsequent innovation performance. Existing studies mainly assume licensed technologies are homogeneously accessible to firms, and a prevailing explanation as to why firms vary in their innovation pe...

78 FR 15970 - Cedarville Rancheria-Liquor Licensing Ordinance of the Cedarville Rancheria, Ordinance No. 2012-05

Science.gov (United States)

2013-03-13

... otherwise. The term shall also include the businesses of the Tribe. It shall be interchangeable in this.... The Executive Committee shall have the authority to issue the following types of liquor licenses... morals. The Executive Committee shall deny an application for issuance, renewal or transfer of a license...

Building a Snow Data Management System using Open Source Software (and IDL)

Science.gov (United States)

Goodale, C. E.; Mattmann, C. A.; Ramirez, P.; Hart, A. F.; Painter, T.; Zimdars, P. A.; Bryant, A.; Brodzik, M.; Skiles, M.; Seidel, F. C.; Rittger, K. E.

2012-12-01

At NASA's Jet Propulsion Laboratory free and open source software is used everyday to support a wide range of projects, from planetary to climate to research and development. In this abstract I will discuss the key role that open source software has played in building a robust science data processing pipeline for snow hydrology research, and how the system is also able to leverage programs written in IDL, making JPL's Snow Data System a hybrid of open source and proprietary software. Main Points: - The Design of the Snow Data System (illustrate how the collection of sub-systems are combined to create a complete data processing pipeline) - Discuss the Challenges of moving from a single algorithm on a laptop, to running 100's of parallel algorithms on a cluster of servers (lesson's learned) - Code changes - Software license related challenges - Storage Requirements - System Evolution (from data archiving, to data processing, to data on a map, to near-real-time products and maps) - Road map for the next 6 months (including how easily we re-used the snowDS code base to support the Airborne Snow Observatory Mission) Software in Use and their Software Licenses: IDL - Used for pre and post processing of data. Licensed under a proprietary software license held by Excelis. Apache OODT - Used for data management and workflow processing. Licensed under the Apache License Version 2. GDAL - Geospatial Data processing library used for data re-projection currently. Licensed under the X/MIT license. GeoServer - WMS Server. Licensed under the General Public License Version 2.0 Leaflet.js - Javascript web mapping library. Licensed under the Berkeley Software Distribution License. Python - Glue code and miscellaneous data processing support. Licensed under the Python Software Foundation License. Perl - Script wrapper for running the SCAG algorithm. Licensed under the General Public License Version 3. PHP - Front-end web application programming. Licensed under the PHP License Version

Operator licensing examiner standards

International Nuclear Information System (INIS)

1993-01-01

The Operator Licensing Examiner Standards provide policy and guidance to NRC examiners and establish the procedures and practices for examining licensees and applicants for reactor operator and senior reactor operator licenses at power reactor facilities pursuant to Part 55 of Title 10 of the Code of Federal Regulations (10 CFR 55). The Examiner Standards are intended to assist NRC examiners and facility licensees to better understand the initial and requalification examination processes and to ensure the equitable and consistent administration of examinations to all applicants. These standards are not a substitute for the operator licensing regulations and are subject to revision or other internal operator licensing policy changes

Flexible licensing

Directory of Open Access Journals (Sweden)

Martyn Jansen

2012-07-01

Full Text Available The case is presented for a more flexible approach to licensing online library resources. Today's distributed education environment creates pressure for UK higher and further education institutions (HEI/FEIs to form partnerships and to develop educational products and roll them out across the globe. Online library resources are a key component of distributed education and yet existing licensing agreements struggle to keep pace with the increasing range of users and purposes for which they are required. This article describes the process of developing a flexible approach to licensing and proposes a new model licence for online library resources which has the adaptability needed in this new global educational landscape. These ideas have been presented and discussed at various workshops across Eduserv's and JISC Collections' higher education and publisher communities, and further consultation is ongoing.

Design parameters and source terms: Volume 1, Design parameters: Revision 0

International Nuclear Information System (INIS)

1987-10-01

The Design Parameters and Source Terms Document was prepared in accordance with DOE request and to provide data for the environmental impact study to be performed in the future for the Deaf Smith County, Texas site for a nuclear waste repository in salt. This document updates a previous unpublished report by Stearns Catalytic Corporation (SCC), entitled ''Design Parameters and Source Terms for a Two-Phase Repository in Salt,'' 1985, to the level of the Site Characterization Plan - Conceptual Design Report. The previous unpublished SCC Study identifies the data needs for the Environmental Assessment effort for seven possible Salt Repository sites

Regulatory analysis for final rule on nuclear power plant license renewal

International Nuclear Information System (INIS)

1991-12-01

This regulatory analysis provides the supporting information for the final rule (10 CFR Part 54) that defines the Nuclear Regulatory Commission's requirements for renewing the operating licenses of commercial nuclear power plants. A set of four specific alternatives for the safety review of license renewal applications is defined and evaluated. These are: Alternative A-current licensing basis; Alternative B-extension of Alternative A to require assessment and managing of aging; Alternative C -- extension of Alternative B to require assessment of design differences against selected new-plant standards using probabilistic risk assessment; and Alternative D -- extension of Alternative B to require compliance with all new-plant standards. A quantitative comparison of the four alternatives in terms of impact-to-value ratio is presented, and Alternative B is the most cost-beneficial safety review alternative

Trends in nuclear licensing

Energy Technology Data Exchange (ETDEWEB)

Dalton, N W [Council for Nuclear Safety, Hennopsmeer, Pretoria (South Africa)

1990-06-01

The development of nuclear safety and licensing is briefly reviewed in four stages namely: The Formative Period (1946-1959), The Expansive Period (1960-1969), The Mature Period (1970-1979) and the Apprehensive Period (1980-1989). Particular safety issues in the respective periods are highlighted to indicate the changing emphasis of nuclear licensing over the past thirty years or so. Against this background, nuclear licensing. (author)

Trends in nuclear licensing

International Nuclear Information System (INIS)

Dalton, N.W.

1990-01-01

The development of nuclear safety and licensing is briefly reviewed in four stages namely: The Formative Period (1946-1959), The Expansive Period (1960-1969), The Mature Period (1970-1979) and the Apprehensive Period (1980-1989). Particular safety issues in the respective periods are highlighted to indicate the changing emphasis of nuclear licensing over the past thirty years or so. Against this background, nuclear licensing. (author)

Coarse Grid Modeling of Turbine Film Cooling Flows Using Volumetric Source Terms

Science.gov (United States)

Heidmann, James D.; Hunter, Scott D.

2001-01-01

The recent trend in numerical modeling of turbine film cooling flows has been toward higher fidelity grids and more complex geometries. This trend has been enabled by the rapid increase in computing power available to researchers. However, the turbine design community requires fast turnaround time in its design computations, rendering these comprehensive simulations ineffective in the design cycle. The present study describes a methodology for implementing a volumetric source term distribution in a coarse grid calculation that can model the small-scale and three-dimensional effects present in turbine film cooling flows. This model could be implemented in turbine design codes or in multistage turbomachinery codes such as APNASA, where the computational grid size may be larger than the film hole size. Detailed computations of a single row of 35 deg round holes on a flat plate have been obtained for blowing ratios of 0.5, 0.8, and 1.0, and density ratios of 1.0 and 2.0 using a multiblock grid system to resolve the flows on both sides of the plate as well as inside the hole itself. These detailed flow fields were spatially averaged to generate a field of volumetric source terms for each conservative flow variable. Solutions were also obtained using three coarse grids having streamwise and spanwise grid spacings of 3d, 1d, and d/3. These coarse grid solutions used the integrated hole exit mass, momentum, energy, and turbulence quantities from the detailed solutions as volumetric source terms. It is shown that a uniform source term addition over a distance from the wall on the order of the hole diameter is able to predict adiabatic film effectiveness better than a near-wall source term model, while strictly enforcing correct values of integrated boundary layer quantities.

77 FR 38772 - Prospective Grant of Exclusive Patent License

Science.gov (United States)

2012-06-29

... transverse to the beam's direction of propagation. Laser light is directed onto at least a portion of the... Source from a Photoionized Cold Atom Beam,'' NIST Docket No. 11-018 to LoTIS Technologies LLC, having a... license would be for the field: Devices that produce or include a focused beam of electrons and/or ions...

Technical Barriers, Licenses and Tariffs as Means of Limiting Market Access

DEFF Research Database (Denmark)

Schröder, Philipp J.H.; Jørgensen, Jan Guldager

2006-01-01

Technical barriers (standards), import licenses and tariffs may be deployed as means of limiting the market access of foreign firms. The present paper examines these measures in a setting of monopolistic competition. We find that, if protection focuses predominantly on the number of foreign firms...... accessing the domestic market, a technical barrier (an import license) may dominate a tariff (tariff and a tech- nical barrier) in terms of consumer welfare, even when tariff revenues are fully redistributed. However, if protection pays su±cient focus on limiting the total import volume, then tariffs...

Streamlining the license renewal review process

International Nuclear Information System (INIS)

Dozier, J.; Lee, S.; Kuo, P.T.

2001-01-01

The staff of the NRC has been developing three regulatory guidance documents for license renewal: the Generic Aging Lessons Learned (GALL) report, Standard Review Plan for License Renewal (SRP-LR), and Regulatory Guide (RG) for Standard Format and Content for Applications to Renew Nuclear Power Plant Operating Licenses. These documents are designed to streamline the license renewal review process by providing clear guidance for license renewal applicants and the NRC staff in preparing and reviewing license renewal applications. The GALL report systematically catalogs aging effects on structures and components; identifies the relevant existing plant programs; and evaluates the existing programs against the attributes considered necessary for an aging management program to be acceptable for license renewal. The GALL report also provides guidance for the augmentation of existing plant programs for license renewal. The revised SRP-LR allows an applicant to reference the GALL report to preclude further NRC staff evaluation if the plant's existing programs meet the criteria described in the GALL report. During the review process, the NRC staff will focus primarily on existing programs that should be augmented or new programs developed specifically for license renewal. The Regulatory Guide is expected to endorse the Nuclear Energy Institute (NEI) guideline, NEI 95-10, Revision 2, entitled 'Industry Guideline for Implementing the Requirements of 10 CFR Part 54 - The License Renewal Rule', which provides guidance for preparing a license renewal application. This paper will provide an introduction to the GALL report, SRP-LR, Regulatory Guide, and NEI 95-10 to show how these documents are interrelated and how they will be used to streamline the license renewal review process. This topic will be of interest to domestic power utilities considering license renewal and international ICONE participants seeking state-of-the-art information about license renewal in the United States

The Monticello license renewal project

International Nuclear Information System (INIS)

Clauss, J.M.; Harrison, D.L.; Pickens, T.A.

1993-01-01

Today, 111 nuclear power plants provide over 20 percent of the electrical energy generated in the United States. The operating license of the oldest operating plant will expire in 2003, one-third of the existing operating licenses will expire by 2010 and the newest plant's operating license will expire in 2033. The National Energy Strategy (NES) prepared by the Department of Energy (DOE) assumes that 70 percent of the current operating plants will continue to operate beyond their current license expiration. Power from current operating plants can assist in ensuring an adequate, diverse, and environmentally acceptable energy supply for economic growth and improved U.S. competitiveness. In order to preserve this energy resource, three major tasks must be successfully completed: (1) establishment of regulations, technical standards, and procedures for the preparation and review of License Renewal Applications (LRAs); (2) development of technical criteria and bases for monitoring, refurbishing or replacing plant equipment; and (3) demonstration of the regulatory process by a plant obtaining a renewed license. Since 1986, the DOE has been working with the nuclear industry and the Nuclear Regulatory Commission (NRC) to establish and demonstrate the option to extend the life of a nuclear power plant by renewing the operating license. The Monticello Lead Plant demonstration project was initiated in September 1988, following the Pilot Plant studies. This paper is primarily focused on the status and insights gained from the Northern States Power Company (NSP) Monticello Lead Plant demonstration project. The following information is included: (1) Current Status - Monticello License Renewal Application; (2) Economic Analysis; (3) License Renewal Regulatory Uncertainty Issues; (4) Key Decisions; (5) Management Structure; (6) Technical and Licensing Perspective; (7) NRC Interactions; (8) Summary

Open Source, Open Standards, and Health Care Information Systems

Science.gov (United States)

2011-01-01

Recognition of the improvements in patient safety, quality of patient care, and efficiency that health care information systems have the potential to bring has led to significant investment. Globally the sale of health care information systems now represents a multibillion dollar industry. As policy makers, health care professionals, and patients, we have a responsibility to maximize the return on this investment. To this end we analyze alternative licensing and software development models, as well as the role of standards. We describe how licensing affects development. We argue for the superiority of open source licensing to promote safer, more effective health care information systems. We claim that open source licensing in health care information systems is essential to rational procurement strategy. PMID:21447469

PWR reactor pressure vessel internals license renewal industry report; revision 1. Final report

International Nuclear Information System (INIS)

Schwirian, R.; Robison, G.

1994-07-01

The U.S. nuclear power industry, through coordination by the Nuclear Management and Resources Council (NUMARC), and sponsorship by the U.S. Department of Energy (DOE) and the Electric Power Research Institute (EPRI), has evaluated age-related degradation effects for a number of major plant systems, structures and components, in the license renewal technical Industry Reports (IRs). License renewal applicants may choose to reference these IRs in support of their plant-specific license renewal applications, as an equivalent to the integrated plant assessment provisions of the license renewal rule (10 CFR Part 54). Pressurized water reactor (PWR) reactor pressure vessel (RPV) internals designed by all three U.S. PWR nuclear steam supply system vendors have been evaluated relative to the effects of age-related degradation mechanisms; the capability of current design limits; inservice examination, testing, repair, refurbishment, and other programs to manage these effects; and the assurance that these internals can continue to perform their intended safety functions in the license renewal term. This industry report (IR), one of a series of ten, provides a generic technical basis for evaluation of PWR reactor pressure vessel internals for license renewal

NRC source term assessment for incident response dose projections

International Nuclear Information System (INIS)

Easley, P.; Pasedag, W.

1984-01-01

The NRC provides advice and assistance to licensees and State and local authorities in responding to accidents. The TACT code supports this function by providing source term projections for two situations during early (15 to 60 minutes) accident response: (1) Core/containment damage is indicated, but there are no measured releases. Quantification of a predicted release permits emergency response before people are exposed. With TACT, response personnel can estimate releases based on fuel and cladding conditions, coolant boundary and containment integrity, and mitigative systems operability. For this type of estimate, TACT is intermediate between default assumptions and time-consuming mechanistic codes. (2) A combination of plant status and limited release data are available. For this situation, iterations between predictions based on known conditions which are compared to measured releases gives reasonable confidence in supplemental source term information otherwise unavailable: nuclide mix, releases not monitored, and trending or abrupt changes. The assumptions and models used in TACT, and examples of its use, are given in this paper

IAEA news: • Newcomer countries face common challenges in nuclear infrastructure development. • Safety and licensing requirements for small modular reactors: IAEA hosts first workshop for regulators. • IAEA reaches milestone in disposal of radioactive sources

International Nuclear Information System (INIS)

Kollar, Lenka; Dyck, Elisabeth; Dixit, Aabha; Gaspar, Miklos; Gil, Laura

2016-01-01

• Newcomer countries face common challenges in nuclear infrastructure development: Countries embarking on a nuclear power programme need to make sure that the development of their legal, regulatory and support infrastructure keeps pace with the construction of the power plant itself. This is the only way to ensure that the programme proceeds in a safe, secure and sustainable way, concluded participants of a workshop on nuclear power infrastructure development hosted at the IAEA last February. • Safety and licensing requirements for small modular reactors: IAEA hosts first workshop for regulators: A new generation of advanced, prefab nuclear power reactors called small modular reactors (SMRs) could be licensed and hit the market as early as 2020, and the IAEA is helping regulators prepare for their debut. In a series of workshops that began earlier this year, the IAEA is working closely with regulators on approaches to safety and licensing ahead of potential SMR deployment worldwide. • IAEA reaches milestone in disposal of radioactive sources: Successful tests of a promising technology for moving and storing low level radioactive sealed sources are paving the way for a new disposal method for dealing with small volumes of radioactive waste around the world. The method, which involves placing and covering sealed sources in a narrow hole a few hundred metres deep, would allow countries to safely and securely take charge of their own disused radioactive sources. The proof of concept for the technology was tested in Croatia late last year — without the use of actual radioactive material.

Selected source term topics. Report to CSNI by an OECD/NEA Group of experts

International Nuclear Information System (INIS)

1987-04-01

CSNI Report 136 summarizes the results of the work performed by the Group of Experts on the Source Term and Environmental Consequences (PWG4) during the period extending from 1983 and 1986. This report is complementary to Part 1, 'Technical Status of the Source Term' of CSNI Report 135, 'Report to CSNI on Source Term Assessment, Containment atmosphere control systems, and accident consequences'; it considers in detail a number of very specific issues thought to be important in the source term area. It consists of: an executive summary (prepared by the Chairman of the Group), a section on conclusions and recommendations, and five technical chapters (fission product chemistry in the primary circuit of a LWR during severe accidents; resuspension/re-entrainment of aerosols in LWRs following a meltdown accident; iodine chemistry under severe accident conditions; effects of combustion, steam explosions and pressurized melt ejection on fission product behaviour; radionuclide removal by pool scrubbing), a technical annex and two appendices

Development of the methodology for application of revised source term to operating nuclear power plants in Korea

International Nuclear Information System (INIS)

Kang, M.S.; Kang, P.; Kang, C.S.; Moon, J.H.

2004-01-01

Considering the current trend in applying the revised source term proposed by NUREG-1465 to the nuclear power plants in the U.S., it is expected that the revised source term will be applied to the Korean operating nuclear power plants in the near future, even though the exact time can not be estimated. To meet the future technical demands, it is necessary to prepare the technical system including the related regulatory requirements in advance. In this research, therefore, it is intended to develop the methodology to apply the revised source term to operating nuclear power plants in Korea. Several principles were established to develop the application methodologies. First, it is not necessary to modify the existing regulations about source term (i.e., any back-fitting to operating nuclear plants is not necessary). Second, if the pertinent margin of safety is guaranteed, the revised source term suggested by NUREG-1465 may be useful to full application. Finally, a part of revised source term could be selected to application based on the technical feasibility. As the results of this research, several methodologies to apply the revised source term to the Korean operating nuclear power plants have been developed, which include: 1) the selective (or limited) application to use only some of all the characteristics of the revised source term, such as release timing of fission products and chemical form of radio-iodine and 2) the full application to use all the characteristics of the revised source term. The developed methodologies are actually applied to Ulchin 9 and 4 units and their application feasibilities are reviewed. The results of this research are used as either a manual in establishing the plan and the procedure for applying the revised source term to the domestic nuclear plant from the utility's viewpoint; or a technical basis of revising the related regulations from the regulatory body's viewpoint. The application of revised source term to operating nuclear

76 FR 55711 - Confirmatory Order Modifying License No. SNM-2001 for the Shallow Land Disposal Area, Parks...

Science.gov (United States)

2011-09-08

... NUCLEAR REGULATORY COMMISSION [Docket No. 40-8907; NRC-2011-0193] Confirmatory Order Modifying License No. SNM-2001 for the Shallow Land Disposal Area, Parks Township, Armstrong County, PA; Notice of... (SNM), pursuant to the terms and conditions of the aforementioned License, at the Shallow Land Disposal...

Licensing for industrial gamma and X-ray radiography installation in Peru

International Nuclear Information System (INIS)

Medina G, E.

1988-01-01

According the regulations for ionizing radiation source installations an application to the Peruvian National Authority should be forwarded in order to get the construction on operation license both industrial gamma and X-ray. Radiography is considered as well as personnel aspects. The proceedings are described

76 FR 52994 - Application for a License To Export Heavy Water

Science.gov (United States)

2011-08-24

... NUCLEAR REGULATORY COMMISSION Application for a License To Export Heavy Water Pursuant to 10 CFR... (liters). producing an active water). pharmaceutical ingredient known as CTP-499, which incorporates heavy water as the source of deuterium to achieve the hydrogen-deuterium exchange. November 30, 2010 December...

An ion source upgrade for an axial injection based commercial cyclotron

International Nuclear Information System (INIS)

Dehnel, M.P.; Stewart, T.; Roeder, M.; Le Du, K.

2005-01-01

The TRIUMF H - volume-cusp ion source technology licensed by Dehnel Consulting Ltd ranges in output current from 1 to 15 mA with beam energies in the 22-30 keV range. For those Cyclone 30 cyclotrons installed with an early 1980's style Lawrence Berkeley Lab (LBL) volume-cusp ion source, an upgrade to a 5 mA TRIUMF H - volume-cusp ion source would pay dividends in terms of longer filament, filament post and ion source lens lifetime, as well as less eroded material build-up in the source. In addition, the 5 mA ion source would approximately double the beam current available to inject into the cyclotron while reducing the emittance by about a factor of four. The new system has the potential to significantly boost radioisotope production at Cyclone 30 facilities utilizing the older style LBL ion source

Source-term model for the SYVAC3-NSURE performance assessment code

International Nuclear Information System (INIS)

Rowat, J.H.; Rattan, D.S.; Dolinar, G.M.

1996-11-01

Radionuclide contaminants in wastes emplaced in disposal facilities will not remain in those facilities indefinitely. Engineered barriers will eventually degrade, allowing radioactivity to escape from the vault. The radionuclide release rate from a low-level radioactive waste (LLRW) disposal facility, the source term, is a key component in the performance assessment of the disposal system. This report describes the source-term model that has been implemented in Ver. 1.03 of the SYVAC3-NSURE (Systems Variability Analysis Code generation 3-Near Surface Repository) code. NSURE is a performance assessment code that evaluates the impact of near-surface disposal of LLRW through the groundwater pathway. The source-term model described here was developed for the Intrusion Resistant Underground Structure (IRUS) disposal facility, which is a vault that is to be located in the unsaturated overburden at AECL's Chalk River Laboratories. The processes included in the vault model are roof and waste package performance, and diffusion, advection and sorption of radionuclides in the vault backfill. The model presented here was developed for the IRUS vault; however, it is applicable to other near-surface disposal facilities. (author). 40 refs., 6 figs

Real-Time Vehicle Speed Estimation Based on License Plate Tracking in Monocular Video Sequences

Directory of Open Access Journals (Sweden)

Aleksej MAKAROV

2016-02-01

Full Text Available A method of estimating the vehicle speed from images obtained by a fixed over-the-road monocular camera is presented. The method is based on detecting and tracking vehicle license plates. The contrast between the license plate and its surroundings is enhanced using infrared light emitting diodes and infrared camera filters. A range of the license plate height values is assumed a priori. The camera vertical angle of view is measured prior to installation. The camera tilt is continuously measured by a micro-electromechanical sensor. The distance of the license plate from the camera is theoretically derived in terms of its pixel coordinates. Inaccuracies due to the frame rate drift, to the tilt and the angle of view measurement errors, to edge pixel detection and to a coarse assumption of the vehicle license plate height are analyzed and theoretically formulated. The resulting system is computationally efficient, inexpensive and easy to install and maintain along with the existing ALPR cameras.

Considerations about source term now used aiming to emergency planning

International Nuclear Information System (INIS)

Austregesilo Filho, H.

1987-01-01

The applicability of source terms, in parametric studies for improving external emergengy plan for Angra-I reactor is presented. The source term is defined as, the quantity and radioactive material disposable for releasing to the environment in case of austere accident in a nuclear power plant. The following hypothesis: occuring accident, 100% of the noble gases, 50% of halogens and 1% of solid fission products contained into the reactor core, are released immediately toward the containment building; the radioactivity releasing to the environment is done at a constant rate of 0.1% in mass per day; the actuation of mitigated systems of radioactivity releasing, such as, spray of container or system of air recirculation by filters, is not considered; and the releasing is done at soil level. (M.C.K.) [pt

Driving behaviors and accident risk under lifetime license revocation.

Science.gov (United States)

Chang, Hsin-Li; Woo, T Hugh; Tseng, Chien-Ming; Tseng, I-Yen

2011-07-01

This study explored the driving behaviors and crash risk of 768 drivers who were under administrative lifetime driver's license revocation (ALLR). It was found that most of the ALLR offenders (83.2%) were still driving and only a few (16.8%) of them gave up driving completely. Of the offenders still driving, 67.6% experienced encountering a police roadside check, but were not detained or ticketed by the police. Within this group, 50.6% continued driving while encountering a police check, 18.0% of them made an immediate U-turn and 9.5% of them parked and exited their car. As to crash risk, 15.2% of the ALLR offenders had at least one crash experience after the ALLR had been imposed. The results of the logistic regression models showed that the offenders' crash risk while under the ALLR was significantly correlated with their personal characteristics (personal income), penalty status (incarceration, civil compensation and the time elapsed since license revocation), annual distance driven, and needs for driving (working, commuting and driving kids). Low-income offenders were more inclined to have a crash while driving under the ALLR. Offenders penalized by being incarcerated or by paying a high civil compensation drove more carefully and were less of a crash risk under the ALLR. The results also showed there were no differences in crash risk under the ALLR between hit-and-run offences and drunk driving offences or for offenders with a professional license or an ordinary license. Generally, ALLR offenders drove somewhat more carefully and were less of a crash risk (4.3 crashes per million km driven) than legal licensed drivers (23.1 crashes per million km driven). Moreover, they seemed to drive more carefully than drivers who were under short-term license suspension/revocation which previous studies have found. Copyright © 2011 Elsevier Ltd. All rights reserved.

The exemption from the requirement of registration and/or licensing of some sources. machines and devices emitting ionizing and /or on ionizing radiation: a proposed draft for Israeli regulations

Energy Technology Data Exchange (ETDEWEB)

Schlesinger, T; Margaliot, M [Israel Atomic Energy Commission, Yavne (Israel). Soreq Nuclear Research Center

1997-11-16

The licensing and authorization of the import, purchase, distribution, transportation and application of radioactive materials and devices emitting ionizing and/or non-ionizing radiation are carried out in Israel by the Ministries of the Environment and of Health. The legal basis for file authority of these Ministries in radiation protection matters is file {sup P}harmacists Regulation- Radioactive Elements and Products Thereof, 1981 (revision 1994) (PRREPT). Licenses are issued by the Chief Radiation Executive (CUE) appointed by the Minister of the Environment and the Minister of Health. The Regulations include a clause which enables the CUE to exempt certain amounts of radioactive materials from file requirements laid down in the PRREPT. The exemption clause is general and does not indicate the types and amounts of radioactive material may be exempted. The proposed draft Israeli regulations are related to exemption of some sources, machines and devices emitting ionizing and non-ionizing radiation, wife a suggestion to extend file above mentioned exemption clause to include some machines and devices and to provide an explicit and detailed list of materials, sources and devices to be exempted. Among these are the following: (authors)

The exemption from the requirement of registration and/or licensing of some sources. machines and devices emitting ionizing and /or on ionizing radiation: a proposed draft for Israeli regulations

International Nuclear Information System (INIS)

Schlesinger, T.; Margaliot, M.

1997-01-01

The licensing and authorization of the import, purchase, distribution, transportation and application of radioactive materials and devices emitting ionizing and/or non-ionizing radiation are carried out in Israel by the Ministries of the Environment and of Health. The legal basis for file authority of these Ministries in radiation protection matters is file P harmacists Regulation- Radioactive Elements and Products Thereof, 1981 (revision 1994) (PRREPT). Licenses are issued by the Chief Radiation Executive (CUE) appointed by the Minister of the Environment and the Minister of Health. The Regulations include a clause which enables the CUE to exempt certain amounts of radioactive materials from file requirements laid down in the PRREPT. The exemption clause is general and does not indicate the types and amounts of radioactive material may be exempted. The proposed draft Israeli regulations are related to exemption of some sources, machines and devices emitting ionizing and non-ionizing radiation, wife a suggestion to extend file above mentioned exemption clause to include some machines and devices and to provide an explicit and detailed list of materials, sources and devices to be exempted. Among these are the following: (authors)

Graduated driver licensing and differential deterrence: The effect of license type on intentions to violate road rules.

Science.gov (United States)

Poirier, Brigitte; Blais, Etienne; Faubert, Camille

2018-01-01

In keeping with the differential deterrence theory, this article assesses the moderating effect of license type on the relationship between social control and intention to violate road rules. More precisely, the article has two objectives: (1) to assess the effect of license type on intentions to infringe road rules; and (2) to pinpoint mechanisms of social control affecting intentions to violate road rules based on one's type of driver license (a restricted license or a full license). This effect is examined among a sample of 392 young drivers in the province of Quebec, Canada. Drivers taking part in the Graduated Driver Licensing (GDL) program have limited demerit points and there is zero tolerance for drinking-and-driving. Propensity score matching techniques were used to assess the effect of the license type on intentions to violate road rules and on various mechanisms of social control. Regression analyses were then conducted to estimate the moderating effect of license type. Average treatment effects from propensity score matching analyses indicate that respondents with a restricted license have lower levels of intention to infringe road rules. While moral commitment and, to a lesser extent, the perceived risk of arrest are both negatively associated with intentions to violate road rules, the license type moderates the relationship between delinquent peers and intentions to violate road rules. The effect of delinquent peers is reduced among respondents with a restricted driver license. Finally, a diminished capability to resist peer pressure could explain the increased crash risk in months following full licensing. Copyright © 2017 Elsevier Ltd. All rights reserved.

75 FR 60341 - Licenses, Certifications, and Approvals for Material Licensees; Reopening of Comment Period

Science.gov (United States)

2010-09-30

... approval processes for byproduct, source and special nuclear material licenses, and irradiators to clarify... review the proposed amendment in order to provide constructive comments, an extension was necessary. No...

A note on variational multiscale methods for high-contrast heterogeneous porous media flows with rough source terms

KAUST Repository

Calo, Victor M.

2011-09-01

In this short note, we discuss variational multiscale methods for solving porous media flows in high-contrast heterogeneous media with rough source terms. Our objective is to separate, as much as possible, subgrid effects induced by the media properties from those due to heterogeneous source terms. For this reason, enriched coarse spaces designed for high-contrast multiscale problems are used to represent the effects of heterogeneities of the media. Furthermore, rough source terms are captured via auxiliary correction equations that appear in the formulation of variational multiscale methods [23]. These auxiliary equations are localized and one can use additive or multiplicative constructions for the subgrid corrections as discussed in the current paper. Our preliminary numerical results show that one can capture the effects due to both spatial heterogeneities in the coefficients (such as permeability field) and source terms (e.g., due to singular well terms) in one iteration. We test the cases for both smooth source terms and rough source terms and show that with the multiplicative correction, the numerical approximations are more accurate compared to the additive correction. © 2010 Elsevier Ltd.

Comparison of open-source linear programming solvers.

Energy Technology Data Exchange (ETDEWEB)

Gearhart, Jared Lee; Adair, Kristin Lynn; Durfee, Justin David.; Jones, Katherine A.; Martin, Nathaniel; Detry, Richard Joseph

2013-10-01

When developing linear programming models, issues such as budget limitations, customer requirements, or licensing may preclude the use of commercial linear programming solvers. In such cases, one option is to use an open-source linear programming solver. A survey of linear programming tools was conducted to identify potential open-source solvers. From this survey, four open-source solvers were tested using a collection of linear programming test problems and the results were compared to IBM ILOG CPLEX Optimizer (CPLEX) [1], an industry standard. The solvers considered were: COIN-OR Linear Programming (CLP) [2], [3], GNU Linear Programming Kit (GLPK) [4], lp_solve [5] and Modular In-core Nonlinear Optimization System (MINOS) [6]. As no open-source solver outperforms CPLEX, this study demonstrates the power of commercial linear programming software. CLP was found to be the top performing open-source solver considered in terms of capability and speed. GLPK also performed well but cannot match the speed of CLP or CPLEX. lp_solve and MINOS were considerably slower and encountered issues when solving several test problems.

Establishing a safety and licensing basis for generation IV advanced reactors. License by test

International Nuclear Information System (INIS)

Kadak, Andrew C.

2001-01-01

The license by test approach to licensing is a novel method of licensing reactors. It provides an opportunity to deal with innovative non-water reactors in a direct way on a time scale that could permit early certification based on tests of a demonstration reactor. The uncertainties in the design and significant contributors to risk would be identified in the PRA during the design. Deterministic analysis computer codes could be tested on a real reactor. Scaling effects and associated uncertainties would be minimized. License by test is an approach that has sufficient merit to be developed and tested

USA perspectives. Safety and security of radioactive sources

International Nuclear Information System (INIS)

Dicus, G.J.

1999-01-01

In contrast to the 103 licensed nuclear power plants in the United States, there are about 157,000 licenses that authorize the use of radioactive materials subject to US Atomic Energy Act. as amended. Each year the NRC receives about 200 reports of lost, stolen or abandoned radioactive sources and devices. The NRC has established a programme to review and analyze reports and other information on losses, thefts, abandonments, and discoveries of radioactive sources that helped to identify and characterize the problem with safety and security of radioactive sources in devices used under the general license programme. In summary, a large number of radioactive sources in use in the USA have a very good safety record. When used properly by trained personnel with effective regulatory oversight, the many uses of radioactive sources are safe and provide a net benefit to society. If problems occur such as overexposures or contamination of property, it is essential that hey are promptly reported to the regulatory authority. If necessary appropriate emergency response measures can be taken, and the problems analysed. In that way, effective risk-informed regulatory measures can be activated to assure the continued safety and security of radioactive sources

22 CFR 96.30 - State licensing.

Science.gov (United States)

2010-04-01

... Licensing and Corporate Governance § 96.30 State licensing. (a) The agency or person is properly licensed or... person follows applicable State licensing and regulatory requirements in all jurisdictions in which it provides adoption services. (c) If it provides adoption services in a State in which it is not itself...

Operating reactors licensing actions summary

International Nuclear Information System (INIS)

1982-07-01

The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

Operating reactors licensing actions summary

International Nuclear Information System (INIS)

1982-05-01

The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

Operating reactors licensing actions summary

International Nuclear Information System (INIS)

1983-01-01

The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

Operating reactors licensing actions summary

International Nuclear Information System (INIS)

1983-03-01

The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

Operating reactors licensing actions summary

International Nuclear Information System (INIS)

1982-11-01

The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

Operating reactors licensing actions summary

International Nuclear Information System (INIS)

1982-10-01

The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

Operating reactors licensing actions summary

International Nuclear Information System (INIS)

1982-08-01

The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

Operating reactors licensing actions summary

International Nuclear Information System (INIS)

1982-09-01

The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

Development and licensing of a melting plant for Chernobyl scrap

International Nuclear Information System (INIS)

Sappok, M.; Zunk, H.; Fashevsky, K.A.

1998-01-01

One decade after the accident at unit 4 of the Chernobyl nuclear power station, a melting plant for radioactively contaminated metallic materials, the so-called SURF facility, is being planned and licensed for erection in the direct neighbourhood of the NPP area. Main goal is the recycling of the material largely decontaminated by the melting process, by means of manufacturing of casks and containers for waste disposal and of shielding equipment. The melting plant will be part of the Ukrainian waste handling centre (CPPRO). The technology is based on the long-term experience gained at Siempelkamp's CARLA plant in Krefeld. Within 1995 and 1996 the licensing conditions were defined, the licensing documents prepared and the formal procedure initiated. The complex is scheduled to start operation in 2001, in case the necessary financing is allocated. To this end the proposed site of the facility has undergone the state assessment. The technical documentation for construction is at the stage of development. (author)

Operator licensing examiner standards

International Nuclear Information System (INIS)

1994-06-01

The Operator Licensing Examiner Standards provide policy and guidance to NRC examiners and establish the procedures and practices for examining licensees and applicants for reactor operator and senior reactor operator licenses at power reactor facilities pursuant to Part 55 of Title 10 of the Code of Federal Regulations (10 CFR 55). The Examiner Standards are intended to assist NRC examiners and facility licensees to better understand the initial and requalification examination processes and to ensure the equitable and consistent administration of examinations to all applicants. These standards are not a substitute for the operator licensing regulations and are subject to revision or other internal operator licensing policy changes. Revision 7 was published in January 1993 and became effective in August 1993. Supplement 1 is being issued primarily to implement administrative changes to the requalification examination program resulting from the amendment to 10 CFR 55 that eliminated the requirement for every licensed operator to pass an NRC-conducted requalification examination as a condition for license renewal. The supplement does not substantially alter either the initial or requalification examination processes and will become effective 30 days after its publication is noticed in the Federal Register. The corporate notification letters issued after the effective date will provide facility licensees with at least 90 days notice that the examinations will be administered in accordance with the revised procedures

Licensing in an International Market

Science.gov (United States)

Ferreira, Fernanda A.

2008-09-01

We study the effects of entry of a foreign firm on domestic welfare in the presence of licensing, when the entrant is technologically superior to the incumbent. We show that foreign entry increases domestic welfare for sufficiently large technological differences between the firms under both fixed-fee licensing and royalty licensing.

22 CFR 120.20 - License.

Science.gov (United States)

2010-04-01

... 22 Foreign Relations 1 2010-04-01 2010-04-01 false License. 120.20 Section 120.20 Foreign Relations DEPARTMENT OF STATE INTERNATIONAL TRAFFIC IN ARMS REGULATIONS PURPOSE AND DEFINITIONS § 120.20 License. License means a document bearing the word “license” issued by the Directorate of Defense Trade...

Cellular Phone Towers, Cell tower locations as derived from various sources including the Department of Licenses and Inspections and the Department of Planning and Zoning., Published in 2010, 1:2400 (1in=200ft) scale, Howard County Government.

Data.gov (United States)

NSGIC Local Govt | GIS Inventory — Cellular Phone Towers dataset current as of 2010. Cell tower locations as derived from various sources including the Department of Licenses and Inspections and the...

The impact of reliability centered maintenance on plant prospects for license renewal

International Nuclear Information System (INIS)

Elliott, J.O.; Nakahara, Y.

1991-01-01

Much attention has been directed in recent years to means of extending nuclear power plant life. As many plants enter their third decade of service, the questions loom large of how to keep aging plants reliable, as well as how to assure reliability and safety to an extent sufficient to warrant license renewal at the end of the current licensing term. Concurrently the nuclear industry has seen a growing interest in reducing the cost and complexity of maintenance activities while at the same time improving plant reliability and availability. Attainment of these seemingly contradictory aims is being aided by the introduction of a maintenance philosophy developed originally by the airline industry and subsequently applied with great success both in that industry and the U.S. military services. Reliability Centered Maintenance (RCM), in its basic form, may be described as a consideration of reliability and maintenance problems from a systems level approach, allowing a focus on preservation of system functions as the aim of a maintenance program optimized for both safety and economics. It is this systematic view of plant maintenance, with the emphasis on preservation of overall functions rather than individual parts and components which sets RCM apart from past nuclear plant maintenance philosophies. It is also the factor which makes application of RCM an ideal first step in development of strategies for life extension and license renewal, both for aging plants, and for plants just beginning their first license term

Technology Licensing and Firm Innovation

DEFF Research Database (Denmark)

Moreira, Solon

acquisition. The findings indicate that technology licensing is positively related to the number of inventions produced by the licensee in the years subsequent to the licensing deal. Subsequently, I investigate the moderating effect that organizational slack and myopia have on this main relationship....... The findings also suggest that high levels of Organizational Slack (available financial resources) strengthen the positive effect of licensing on innovation. However, higher levels of Organizational Myopia (the extent to which a firm draws on its own knowledge) can decrease the main effect of licensing....

Scenarios and analytical methods for UF6 releases at NRC-licensed fuel cycle facilities

International Nuclear Information System (INIS)

Siman-Tov, M.; Dykstra, J.; Holt, D.D.; Huxtable, W.P.; Just, R.A.; Williams, W.R.

1984-06-01

This report identifies and discusses potential scenarios for the accidental release of UF 6 at NRC-licensed UF 6 production and fuel fabrication facilities based on a literature review, site visits, and DOE enrichment plant experience. Analytical tools needed for evaluating source terms for such releases are discussed, and the applicability of existing methods is reviewed. Accident scenarios are discussed under the broad headings of cylinder failures, UF 6 process system failures, nuclear criticality events, and operator errors and are categorized by location, release source, phase of UF 6 prior to release, release flow characteristics, release causes, initiating events, and UF 6 inventory at risk. At least three types of releases are identified for further examination: (1) a release from a liquid-filled cylinder outdoors, (2) a release from a pigtail or cylinder in a steam chest, (3) an indoor release from either (a) a pigtail or liquid-filled cylinder or (b) other indoor source depending on facility design and operating procedures. Indoor release phenomena may be analyzed to determine input terms for a ventilation model by using a time-dependent homogeneous compartment model or a more complex hydrodynamic model if time-dependent, spatial variations in concentrations, temperature, and pressure are important. Analytical tools for modeling directed jets and explosive releases are discussed as well as some of the complex phenomena to be considered in analyzing UF 6 releases both indoors and outdoors

Cogeneration plants in Italy: Licensing aspects

International Nuclear Information System (INIS)

Buscaglione, A.

1991-01-01

This paper focusses on administrative/bureaucratic problems relative to the licensing of cogeneration plants in Italy. The current stumbling block appears to lie in organizational difficulties relative to the coordination of various Government authorized safety committees responsible for the drafting up of suitable legislation governing cogeneration plant fire safety aspects. The author cites the possible environmental benefits in terms of air pollution abatement that could have been had with the timely start-up of a new 7 MW plant (in Lombardia) still awaiting its go-ahead authorization

Online driver's license renewal.

Science.gov (United States)

2015-09-01

The Kentucky Department of Vehicle Regulation is exploring the possibility of developing and implementing online : drivers license renewal. The objective of this project was to: 1) evaluate online drivers license and REAL ID renewal : programs ...

76 FR 53980 - Request for a License To Import Radioactive Waste

Science.gov (United States)

2011-08-30

... NUCLEAR REGULATORY COMMISSION Request for a License To Import Radioactive Waste Pursuant to 10 CFR... Hitachi Nuclear Energy, LLC. Radioactive waste Up to 210 Cobalt- Recycling, China August 1, 2011, August 5, consisting of 60 sealed forensic testing 2011, IW030. used Cobalt-60 sources. or storage and radioactive...

The need for legislative framework (licensing)

International Nuclear Information System (INIS)

Krech, H.

1977-01-01

For reasons of public acceptance the basis of a licensing system should be laid down in a law, details can be fixed in regulations below the law-level. The competence for licensing nuclear installations should be attributed to one body, which is not a the same time charged with the promotion of nuclear energy. The licensing authority has to be provided with sufficient technical advice, given by experts organized in advisory bodies. Normally a licensing procedure is split into several steps (site approval, construction permit, operation licence), each step can be subdivided. Some general aspects of licensing conditions (personal, technical and financial) as well as of the licensing procedure are outlined. The participation of the public is of particular importance but also involves most intricate problems. The paper concludes with some critical remarks on the role of administrative courts with respect to the licensing of nuclear power plants. (orig.) [de

Open source clustering software.

Science.gov (United States)

de Hoon, M J L; Imoto, S; Nolan, J; Miyano, S

2004-06-12

We have implemented k-means clustering, hierarchical clustering and self-organizing maps in a single multipurpose open-source library of C routines, callable from other C and C++ programs. Using this library, we have created an improved version of Michael Eisen's well-known Cluster program for Windows, Mac OS X and Linux/Unix. In addition, we generated a Python and a Perl interface to the C Clustering Library, thereby combining the flexibility of a scripting language with the speed of C. The C Clustering Library and the corresponding Python C extension module Pycluster were released under the Python License, while the Perl module Algorithm::Cluster was released under the Artistic License. The GUI code Cluster 3.0 for Windows, Macintosh and Linux/Unix, as well as the corresponding command-line program, were released under the same license as the original Cluster code. The complete source code is available at http://bonsai.ims.u-tokyo.ac.jp/mdehoon/software/cluster. Alternatively, Algorithm::Cluster can be downloaded from CPAN, while Pycluster is also available as part of the Biopython distribution.

Centrifugal Filtration System for Severe Accident Source Term Treatment

Energy Technology Data Exchange (ETDEWEB)

Liu, Shu Chang; Yim, Man Sung [KAIST, Daejeon (Korea, Republic of)

2016-05-15

The objective of this paper is to present the conceptual design of a filtration system that can be used to process airborne severe accident source term. Reactor containment may lose its structural integrity due to over-pressurization during a severe accident. This can lead to uncontrolled radioactive releases to the environment. For preventing the dispersion of these uncontrolled radioactive releases to the environment, several ways to capture or mitigate these radioactive source term releases are under investigation at KAIST. Such technologies are based on concepts like a vortex-like air curtain, a chemical spray, and a suction arm. Treatment of the radioactive material captured by these systems would be required, before releasing to environment. For current filtration systems in the nuclear industry, IAEA lists sand, multi-venturi scrubber, high efficiency particulate arresting (HEPA), charcoal and combinations of the above in NS-G-1-10, 4.143. Most if not all of the requirements of the scenario for applying this technology near the containment of an NPP site and the environmental constraints were analyzed for use in the design of the centrifuge filtration system.

AP1000{sup R} licensing and deployment in the United States

Energy Technology Data Exchange (ETDEWEB)

Jordan, R. P.; Russ, P. A.; Filiak, P. P.; Castiglione, L. L. [Westinghouse Electric Company LLC, 1000 Westinghouse Drive, Cranberry Township, PA 16066 (United States)

2012-07-01

In recent years, both domestic and foreign utilities have turned to the standardized Westinghouse AP1000 plant design in satisfying their near - and long-term - sustainable energy needs. As direct support to these actions, licensing the AP1000 design has played a significant role by providing one of the fundamental bases in clearing regulatory hurdles leading to the start of new plant construction. Within the U.S. alone, Westinghouse AP1000 licensing activities have reached unprecedented milestones with the approvals of both AP1000 Design Certification and Southern Company's combined construction permit and operating license (COL) application directly supporting the construction of two new nuclear plants in Georgia. Further COL application approvals are immediately pending for an additional two AP1000 plants in South Carolina. And, across the U.S. nuclear industry spectrum, there are 10 other COL applications under regulatory review representing some 16 new plants at 10 sites. In total, these actions represent the first wave of new plant licensing under the regulatory approval process since 1978. Fundamental to the Nuclear Regulatory Commission's AP1000 Design Certification is the formal recognition of the AP1000 passive safety design through regulatory acceptance rulemaking. Through recognition and deployment of the AP1000 Design Certification, the utility licensee / operator of this reactor design are now offered an opportunity to use a simplified 'one-step' combined license process, thereby managing substantial back-end construction schedule risk from regulatory and intervention delays. Application of this regulatory philosophy represents both acceptance and encouragement of standardized reactor designs like the AP1000. With the recent AP1000 Design Certification and utility COL acceptances, the fundamental licensing processes of this philosophy have successfully proven the attainment of significant milestones with the next stage licensing

Licensing an assured isolation facility for low-level radioactive waste. Volume 1: Licensing strategy and issues

International Nuclear Information System (INIS)

Silverman, D.J.; Bauser, M.A.; Baird, R.D.

1998-07-01

This report provides a detailed set of proposed criteria and guidance for the preparation of a license application for an assured isolation facility (AIF). The report is intended to provide a detailed planning basis upon which a prospective applicant may begin pre-licensing discussions with the Nuclear Regulatory Commission and initiate development of a license application. The report may also be useful to the NRC or to state regulatory agencies that may be asked to review such an application. Volume 1 of this report provides background information, and describes the licensing approach and methodology. Volume 2 identifies specific information that is recommended for inclusion in a license application

EMPIRICAL STUDY OF CAR LICENSE PLATES RECOGNITION

Directory of Open Access Journals (Sweden)

Nasa Zata Dina

2015-01-01

Full Text Available The number of vehicles on the road has increased drastically in recent years. The license plate is an identity card for a vehicle. It can map to the owner and further information about vehicle. License plate information is useful to help traffic management systems. For example, traffic management systems can check for vehicles moving at speeds not permitted by law and can also be installed in parking areas to se-cure the entrance or exit way for vehicles. License plate recognition algorithms have been proposed by many researchers. License plate recognition requires license plate detection, segmentation, and charac-ters recognition. The algorithm detects the position of a license plate and extracts the characters. Various license plate recognition algorithms have been implemented, and each algorithm has its strengths and weaknesses. In this research, I implement three algorithms for detecting license plates, three algorithms for segmenting license plates, and two algorithms for recognizing license plate characters. I evaluate each of these algorithms on the same two datasets, one from Greece and one from Thailand. For detecting li-cense plates, the best result is obtained by a Haar cascade algorithm. After the best result of license plate detection is obtained, for the segmentation part a Laplacian based method has the highest accuracy. Last, the license plate recognition experiment shows that a neural network has better accuracy than other algo-rithm. I summarize and analyze the overall performance of each method for comparison.

Operating reactors licensing actions summary

International Nuclear Information System (INIS)

1982-04-01

The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis

Licensing aspects regarding the RBMN project

International Nuclear Information System (INIS)

Cuccia, Valeria; Sacramento, Arivaldo M.; Aleixo, Bruna L.; Ferreira, Vinicius V.M.

2013-01-01

The licensing process of a waste disposal facility is a complex and demanding undertaking. It proceeds in phases, starting with the site selection and ending many decades later, when the radionuclides decayed and no longer offer possible hazard. That is one of the reasons why the licensing process for the Brazilian repository for low and intermediate level radioactive waste (RBMN Project) is a challenge for all the technicians involved. Besides that, the only national experience associated to this subject arose after a radiological accident in the State of Goias, in 1987. Two different institutions are involved in this licensing process: IBAMA, for environmental licensing, and CNEN, for nuclear licensing. Both of them will evaluate the possible impacts caused by the waste disposal, so it is essential to avoid conflicts and duplications of activities. The RBMN project has different teams for each main activity, and one of them is the Licensing group. This team has been planning the licensing activities for the repository, studying the legal framework and estimating costs and execution time for each step. This paper presents the status of the licensing activities regarding to the RBMN project done by the CNEN staff. (author)

Managing Licensing in a Market for Technology

DEFF Research Database (Denmark)

Arora, Ashish; Rønde, Thomas; Fosfuri, Andrea

the technology makes licensing decisions—to centralized licensing. The business unit has superior information about licensing opportunities but may not have the appropriate incentives because its rewards depend upon product market performance. If licensing is decentralized, the business unit forgoes valuable...... licensing opportunities since the rewards for licensing are (optimally) weaker than those for product market profits. This distortion is stronger when production-based incentives are more powerful, making centralization more attractive. Growth of technology markets favors centralization and drives higher...

Advanced Reactor PSA Methodologies for System Reliability Analysis and Source Term Assessment

Energy Technology Data Exchange (ETDEWEB)

Grabaskas, D.; Brunett, A.; Passerini, S.; Grelle, A.; Bucknor, M.

2017-06-26

Beginning in 2015, a project was initiated to update and modernize the probabilistic safety assessment (PSA) of the GE-Hitachi PRISM sodium fast reactor. This project is a collaboration between GE-Hitachi and Argonne National Laboratory (Argonne), and funded in part by the U.S. Department of Energy. Specifically, the role of Argonne is to assess the reliability of passive safety systems, complete a mechanistic source term calculation, and provide component reliability estimates. The assessment of passive system reliability focused on the performance of the Reactor Vessel Auxiliary Cooling System (RVACS) and the inherent reactivity feedback mechanisms of the metal fuel core. The mechanistic source term assessment attempted to provide a sequence specific source term evaluation to quantify offsite consequences. Lastly, the reliability assessment focused on components specific to the sodium fast reactor, including electromagnetic pumps, intermediate heat exchangers, the steam generator, and sodium valves and piping.

Department of Energy licensing strategy

International Nuclear Information System (INIS)

Frei, M.W.

1984-01-01

The Department of Energy (DOE) is authorized by the Nuclear Waste Policy Act of 1982 (Act) to site, design, construct, and operate mined geologic repositories for high-level radioactive wastes and is required to obtain licenses from the Nuclear Regulatory Commission (NRC) to achieve that mandate. To this end the DOE has developed a licensing approach which defines program strategies and which will facilitate and ease the licensing process. This paper will discuss the regulatory framework within which the repository program is conducted, the DOE licensing strategy, and the interactions between DOE and NRC in implementing the strategy. A licensing strategy is made necessary by the unique technical nature of the repository. Such a facility has never before been licensed; furthermore, the duration of isolation of waste demanded by the proposed EPA standard will require a degree of reliance on probabilistic performance assessment as proof of compliance that is a first of a kind for any industry. The licensing strategy is also made necessary by the complex interrelationships among the many involved governmental agencies and even within DOE itself, and because these relationships will change with time. Program activities which recognize these relationships are essential for implementing the Act. The guiding principle in this strategy is an overriding commitment to safeguarding public health and safety and to protecting the environment

ITER safety task NID-5a: ITER tritium environmental source terms - safety analysis basis

International Nuclear Information System (INIS)

Natalizio, A.; Kalyanam, K.M.

1994-09-01

The Canadian Fusion Fuels Technology Project's (CFFTP) is part of the contribution to ITER task NID-5a, Initial Tritium Source Term. This safety analysis basis constitutes the first part of the work for establishing tritium source terms and is intended to solicit comments and obtain agreement. The analysis objective is to provide an early estimate of tritium environmental source terms for the events to be analyzed. Events that would result in the loss of tritium are: a Loss of Coolant Accident (LOCA), a vacuum vessel boundary breach. a torus exhaust line failure, a fuelling machine process boundary failure, a fuel processing system process boundary failure, a water detritiation system process boundary failure and an isotope separation system process boundary failure. 9 figs

Realistic minimum accident source terms - Evaluation, application, and risk acceptance

International Nuclear Information System (INIS)

Angelo, P. L.

2009-01-01

The evaluation, application, and risk acceptance for realistic minimum accident source terms can represent a complex and arduous undertaking. This effort poses a very high impact to design, construction cost, operations and maintenance, and integrated safety over the expected facility lifetime. At the 2005 Nuclear Criticality Safety Division (NCSD) Meeting in Knoxville Tenn., two papers were presented mat summarized the Y-12 effort that reduced the number of criticality accident alarm system (CAAS) detectors originally designed for the new Highly Enriched Uranium Materials Facility (HEUMF) from 258 to an eventual as-built number of 60. Part of that effort relied on determining a realistic minimum accident source term specific to the facility. Since that time, the rationale for an alternate minimum accident has been strengthened by an evaluation process that incorporates realism. A recent update to the HEUMF CAAS technical basis highlights the concepts presented here. (authors)

Application of up-front licensing

Energy Technology Data Exchange (ETDEWEB)

Grant, S D [Atomic Energy of Canada Ltd., Saskatoon, SK (Canada); Snell, V G [Atomic Energy of Canada Ltd., Mississauga, ON (Canada)

1996-12-31

AECL has been pioneering `up-front` licensing of new reactor designs. The CANDU 3 design has been formally reviewed by AECB staff for a number of years. The CANDU 9 design has just started the up-front licensing process. The process gives designers, regulators and potential customers early confidence in the licensability of future plants. (author). 4 refs., 2 tabs.

Application of up-front licensing

International Nuclear Information System (INIS)

Grant, S.D.; Snell, V.G.

1995-01-01

AECL has been pioneering 'up-front' licensing of new reactor designs. The CANDU 3 design has been formally reviewed by AECB staff for a number of years. The CANDU 9 design has just started the up-front licensing process. The process gives designers, regulators and potential customers early confidence in the licensability of future plants. (author). 4 refs., 2 tabs

Regulatory systems-based licensing guidance documentation

International Nuclear Information System (INIS)

Delligatti, M.S.

1991-01-01

The US Nuclear Regulatory Commission (NRC) has developed a series of licensing guidance documents based on the regulatory requirements in Part 60 of Title 10 of the Code of Federal Regulations (10 CFR Part 60). This regulatory systems-based approach to licensing guidance documentation relies on the definition of the high-level waste repository in 10 CFR Part 60. A document which is important for the frame-work it gives to other programmatic licensing guidance is the Draft Regulatory Guide open-quotes Format and Content for the License Application for the High-Level Waste Repositoryclose quotes (FCRG). The FCRG describes a format and content acceptable to NRC for a high-level waste repository license application pursuant to the requirements of 10 CFR Part 60. Other licensing guidance documents will be compatible with the FCRG

On the “non-discrimination” aspect of FRAND licensing: A response to the Indian Competition Commission's recent orders

Directory of Open Access Journals (Sweden)

David J. Teece

2018-03-01

Full Text Available The Indian Competition Commission has recently challenged Ericsson's practice of licensing its standards-essential patents (SEPs, relating to cellular standards, for percentage-based royalties based on the selling prices of the end-user licensed products. Ericsson had committed to the relevant standards-development organisation that it would license its SEPs on “fair, reasonable and non-discriminatory” (“FRAND” terms. The Commission contends that such royalties are “prima facie discriminatory” in violation of the Competition Act, in the (novel sense that different products selling for different prices pay different per-unit royalties. We analyse the broader implications of the Commission's reasoning, concerned that if adopted, the Commission's reasoning would disrupt common industry licensing practices. Keywords: Patents, Licensing, Discrimination, Telecommunications, FRAND, Standards, Industry practice

Radiation protection type testing and licensing of diagnostic X-ray equipment in the GDR

International Nuclear Information System (INIS)

Taschner, P.; Poulheim, K.F.; Feldheim, W.

1987-01-01

The results of more than 10 years experience in type testing and type licensing of diagnostic X-ray equipment with respect to meeting radiation protection requirements as well as the implications for the conduct of these procedures resulting from the introduction of new radiation protection legislation in 1983 and 1984, are described. At present an updated version of the 'Regulation of 16 December 1977 concerning radiation protection type testing and licensing of sealed radiation sources and equipment emitting ionizing radiation' is being prepared. (author)

7 CFR 51.52 - Licensing and identification of certain official devices.

Science.gov (United States)

2010-01-01

... MARKETING SERVICE (Standards, Inspections, Marketing Practices), DEPARTMENT OF AGRICULTURE REGULATIONS AND STANDARDS UNDER THE AGRICULTURAL MARKETING ACT OF 1946 FRESH FRUITS, VEGETABLES AND OTHER PRODUCTS 1,2... similar aid under such terms and conditions as may be specified by the Administrator. Licenses shall be...

New Source Term Model for the RESRAD-OFFSITE Code Version 3

Energy Technology Data Exchange (ETDEWEB)

Yu, Charley [Argonne National Lab. (ANL), Argonne, IL (United States); Gnanapragasam, Emmanuel [Argonne National Lab. (ANL), Argonne, IL (United States); Cheng, Jing-Jy [Argonne National Lab. (ANL), Argonne, IL (United States); Kamboj, Sunita [Argonne National Lab. (ANL), Argonne, IL (United States); Chen, Shih-Yew [Argonne National Lab. (ANL), Argonne, IL (United States)

2013-06-01

This report documents the new source term model developed and implemented in Version 3 of the RESRAD-OFFSITE code. This new source term model includes: (1) "first order release with transport" option, in which the release of the radionuclide is proportional to the inventory in the primary contamination and the user-specified leach rate is the proportionality constant, (2) "equilibrium desorption release" option, in which the user specifies the distribution coefficient which quantifies the partitioning of the radionuclide between the solid and aqueous phases, and (3) "uniform release" option, in which the radionuclides are released from a constant fraction of the initially contaminated material during each time interval and the user specifies the duration over which the radionuclides are released.

Incidents with hazardous radiation sources; Zwischenfaelle mit gefaehrlichen Strahlenquellen

Energy Technology Data Exchange (ETDEWEB)

Schoenhacker, Stefan [Bundesministerium fuer Inneres, Traiskirchen (Austria). Abt. 1/9 - Zivilschutzschule

2016-07-01

Incidents with hazardous radiation sources can occur in any country, even those without nuclear facilities. Preparedness for such incidents is supposed to fulfill globally agreed minimum standards. Incidents are categorized in incidents with licensed handling of radiation sources as for material testing, transport accidents of hazardous radiation sources, incidents with radionuclide batteries, incidents with satellites containing radioactive inventory, incidents wit not licensed handling of illegally acquired hazardous radiation sources. The emergency planning in Austria includes a differentiation according to the consequences: incidents with release of radioactive materials resulting in restricted contamination, incidents with release of radioactive materials resulting in local contamination, and incidents with the hazard of e@nhanced exposure due to the radiation source.

Impact of ITER liquid metal design options on safety level and licensing - Sweden

International Nuclear Information System (INIS)

Harfors, C.; Devell, L.; Johansson, Kjell; Lundell, B.; Rolandsson, S.

1993-01-01

The safety level and licensability of five design options for ITER coolant, breeding material and structural material are assessed, with emphasis on some specified accident scenarios. The safety level is assessed in terms of barrier requirements and the feasibility to construct and qualify such a barrier. The licensability in Sweden of each design option is assessed based on the indicated safety level and on a judgement of the technical feasibility to construct and qualify the ITER tokamak itself, based on the selected design option. 20 refs

Development model to public hearing for environmental licensing of nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Vasques, Luciana Gomes; Aquino, Afonso Rodrigues de, E-mail: lu_vasques@usp.br, E-mail: araquino@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2015-07-01

The use of nuclear technology has always been a matter of concern from an environmental point of view. Although disputed, the generation of electricity in nuclear reactors was considered a source of clean emission in relation to emission of gases responsible for the greenhouse effect. In Brazil, nuclear activities are regulated and supervised by the Brazilian Commission of Nuclear Energy - CNEN. Environmental issues associated with nuclear activities are described by CONAMA, and the developments in this area are licensed by IBAMA, regardless of obtaining nuclear licenses issued by CNEN. Obtaining environmental licenses (prior, installation and operation) depends initially on preparing the Environmental Impact Study - EIS and the Environmental Impact Report - EIR, consisting of a presentation of EIS in language accessible to all. EIR is forwarded to bodies and entities with some connection to the enterprise, to be manifested with IBAMA about the relevance of its content. This information serves as a resource for Public Hearings, which are meetings organized by entrepreneurs, conducted by IBAMA, and rely on public participation, can be considered as a licensing step. Public Hearings are subject to subjectivity, and the model proposed in this research becomes more objective ill-defined, difficult to understand actions for the entrepreneur. (author)

Development model to public hearing for environmental licensing of nuclear facilities

International Nuclear Information System (INIS)

Vasques, Luciana Gomes; Aquino, Afonso Rodrigues de

2015-01-01

The use of nuclear technology has always been a matter of concern from an environmental point of view. Although disputed, the generation of electricity in nuclear reactors was considered a source of clean emission in relation to emission of gases responsible for the greenhouse effect. In Brazil, nuclear activities are regulated and supervised by the Brazilian Commission of Nuclear Energy - CNEN. Environmental issues associated with nuclear activities are described by CONAMA, and the developments in this area are licensed by IBAMA, regardless of obtaining nuclear licenses issued by CNEN. Obtaining environmental licenses (prior, installation and operation) depends initially on preparing the Environmental Impact Study - EIS and the Environmental Impact Report - EIR, consisting of a presentation of EIS in language accessible to all. EIR is forwarded to bodies and entities with some connection to the enterprise, to be manifested with IBAMA about the relevance of its content. This information serves as a resource for Public Hearings, which are meetings organized by entrepreneurs, conducted by IBAMA, and rely on public participation, can be considered as a licensing step. Public Hearings are subject to subjectivity, and the model proposed in this research becomes more objective ill-defined, difficult to understand actions for the entrepreneur. (author)

A novel integrated approach for the hazardous radioactive dust source terms estimation in future nuclear fusion power plants.

Science.gov (United States)

Poggi, L A; Malizia, A; Ciparisse, J F; Gaudio, P

2016-10-01

An open issue still under investigation by several international entities working on the safety and security field for the foreseen nuclear fusion reactors is the estimation of source terms that are a hazard for the operators and public, and for the machine itself in terms of efficiency and integrity in case of severe accident scenarios. Source term estimation is a crucial key safety issue to be addressed in the future reactors safety assessments, and the estimates available at the time are not sufficiently satisfactory. The lack of neutronic data along with the insufficiently accurate methodologies used until now, calls for an integrated methodology for source term estimation that can provide predictions with an adequate accuracy. This work proposes a complete methodology to estimate dust source terms starting from a broad information gathering. The wide number of parameters that can influence dust source term production is reduced with statistical tools using a combination of screening, sensitivity analysis, and uncertainty analysis. Finally, a preliminary and simplified methodology for dust source term production prediction for future devices is presented.

Licensing of away-from-reactor (AFR) installations

International Nuclear Information System (INIS)

Gray, P.L.

1980-01-01

Storage of spent fuel at Away-From-Reactor (AFR) installations will allow reactors to continue to operate until reprocessing or other fuel disposal means are available. AFR installations must be licensed by the Nuclear Regulatory Commission (NRC). Although wide experience in licensing reactors exists, the licensing of an AFR installation is a relatively new activity. Only one has been licensed to date. This paper delineates the requirements for licensing an AFR installation and projects a licensing schedule. Because the NRC is developing specific AFR requirements, this schedule is based primarily on draft NRC documents. The major documents needed for an AFR license application are similar to those for a reactor. They include: a Safety Analysis Report (SAR), and Environmental Report (ER), safeguards and security plans, decommissioning plans, proposed technical specifications, and others. However, the licensing effort has one major difference in that for AFR installations it will be a one-step effort, with follow-up, rather than the two-step process used for reactors. The projected licensing schedule shows that the elapsed time between filing an application and issuance of a license will be about 32 months, assuming intervention. The legal procedural steps will determine the time schedule and will override considerations of technical complexity. A license could be issued in about 14 months in the absence of intervention

Data bank usage in reload design and licensing

International Nuclear Information System (INIS)

Goudey, J.L.; Hansen, E.C.; Scigliano, S.M.; Williams, R.D.

1986-01-01

In 1977 the Nuclear Energy Business Operations of General Electric Company (GE) began a major project to automate sequential execution of the data transfer between the various computer programs used in performing calculations to support design, release, licensing, and core management of fuel used in boiling water reactors (BWRs). A centralized and controlled data bank was designed and implemented to complement the data management system and to achieve the following objectives: (1) enhance the quality and reliability of engineering data used for design and licensing of BWR fuel; (2) provide for traceability and long-term retrievability of engineering data as required by 10CFR50, Appendix B; (3) standardize the location and minimize the redundancy of engineering data; and (4) make engineering data readily available to all individuals and computer programs with a need for it. The structure of this data bank, which has become known as the BWR Engineering Data Bank or BWR/EDB, was purposefully left flexible and expandable with the ability to accommodate numerical, logical, and textual data. The BWR/EDB has been used by GE during fuel release, fuel and core design, reload licensing, and core management activities for 30 to 40 commercial power reactors over the past several years

Current status of LTO licensing programme for Bohunice nuclear power plant

International Nuclear Information System (INIS)

Borak, J.; Kupca, L.

2012-01-01

The objective of long term operation (LTO) licensing programme for Bohunice nuclear power plant is to demonstrate that the relevant structures and components shall perform their functions throughout the entire LTO period during which they shall meet all the relevant safety requirements. All the activities-which should result in utility's request to obtain the licence for LTO-must be performed in line with the relevant legal basis. As of May 2012, the anticipated duration of currently running programme is thirteen months. All relevant documentation, required by the established legal basis, shall be submitted to the licensing authority one year before the Unit 3 design life expiry. (author)

Chernobyl source term, atmospheric dispersion, and dose estimation

International Nuclear Information System (INIS)

Gudiksen, P.H.; Harvey, T.F.; Lange, R.

1988-02-01

The Chernobyl source term available for long-range transport was estimated by integration of radiological measurements with atmospheric dispersion modeling, and by reactor core radionuclide inventory estimation in conjunction with WASH-1400 release fractions associated with specific chemical groups. These analyses indicated that essentially all of the noble gases, 80% of the radioiodines, 40% of the radiocesium, 10% of the tellurium, and about 1% or less of the more refractory elements were released. Atmospheric dispersion modeling of the radioactive cloud over the Northern Hemisphere revealed that the cloud became segmented during the first day, with the lower section heading toward Scandinavia and the uppper part heading in a southeasterly direction with subsequent transport across Asia to Japan, the North Pacific, and the west coast of North America. The inhalation doses due to direct cloud exposure were estimated to exceed 10 mGy near the Chernobyl area, to range between 0.1 and 0.001 mGy within most of Europe, and to be generally less than 0.00001 mGy within the US. The Chernobyl source term was several orders of magnitude greater than those associated with the Windscale and TMI reactor accidents, while the 137 Cs from the Chernobyl event is about 6% of that released by the US and USSR atmospheric nuclear weapon tests. 9 refs., 3 figs., 6 tabs

Free Software Licenses and Other Free Licenses: Genetic Code of Digital Common Goods

OpenAIRE

Marco Ciurcina

2017-01-01

This article explores the history and describes the main features of free software licenses and other free licenses in an attempt to shed light on the reasons for their success in promoting individual behaviors converging towards the collective construction of digital commons.

Managing Licensing in a Market for Technology

DEFF Research Database (Denmark)

Arora, Ashish; Fosfuri, Andrea; Rønde, Thomas

2013-01-01

, we find that interdependency across business units may result in more, not less, decentralization. Furthermore, even though centralization results in less information, centralized licensing deals are larger. Our model conforms to the existing evidence that reports heterogeneity across firms in both......Technology licensing is an important means for companies to extract more value from their intellectual assets. We build a model that helps understand how licensing activity should be organized within large corporations. More specifically, we compare decentralization—where the business unit using...... the technology makes licensing decisions—to centralized licensing. The business unit has superior information about licensing opportunities but may not have the appropriate incentives because its rewards depend on product market performance. If licensing is decentralized, the business unit forgoes valuable...

Preparing to review the license application of the French geological disposal facility - Issues, challenges and perspectives

International Nuclear Information System (INIS)

Dandrieux, Geraldine

2014-01-01

This paper briefly describes the French context for GDR authorization, the French dedicated legislative framework (28 June 2006 Act on sustainable management of radioactive materials and waste), the challenges (regulatory issues, long-term project supervision, technical issues, procedural issues), and the preparing for the review of the DGR license application. A planning schedule is propose with Andra to submit license application for DGR in 2015

Source term identification in atmospheric modelling via sparse optimization

Science.gov (United States)

Adam, Lukas; Branda, Martin; Hamburger, Thomas

2015-04-01

Inverse modelling plays an important role in identifying the amount of harmful substances released into atmosphere during major incidents such as power plant accidents or volcano eruptions. Another possible application of inverse modelling lies in the monitoring the CO2 emission limits where only observations at certain places are available and the task is to estimate the total releases at given locations. This gives rise to minimizing the discrepancy between the observations and the model predictions. There are two standard ways of solving such problems. In the first one, this discrepancy is regularized by adding additional terms. Such terms may include Tikhonov regularization, distance from a priori information or a smoothing term. The resulting, usually quadratic, problem is then solved via standard optimization solvers. The second approach assumes that the error term has a (normal) distribution and makes use of Bayesian modelling to identify the source term. Instead of following the above-mentioned approaches, we utilize techniques from the field of compressive sensing. Such techniques look for a sparsest solution (solution with the smallest number of nonzeros) of a linear system, where a maximal allowed error term may be added to this system. Even though this field is a developed one with many possible solution techniques, most of them do not consider even the simplest constraints which are naturally present in atmospheric modelling. One of such examples is the nonnegativity of release amounts. We believe that the concept of a sparse solution is natural in both problems of identification of the source location and of the time process of the source release. In the first case, it is usually assumed that there are only few release points and the task is to find them. In the second case, the time window is usually much longer than the duration of the actual release. In both cases, the optimal solution should contain a large amount of zeros, giving rise to the

Fission product source terms and engineered safety features

International Nuclear Information System (INIS)

Malinauskas, A.P.

1984-01-01

The author states that new, technically defensible, methodologies to establish realistic source term values for nuclear reactor accidents will soon be available. Although these methodologies will undoubtedly find widespread use in the development of accident response procedures, the author states that it is less clear that the industry is preparing to employ the newer results to develop a more rational approach to strategies for the mitigation of fission product releases. Questions concerning the performance of existing engineered safety systems are reviewed

Use of source term code package in the ELEBRA MX-850 system

International Nuclear Information System (INIS)

Guimaraes, A.C.F.; Goes, A.G.A.

1988-12-01

The implantation of source term code package in the ELEBRA-MX850 system is presented. The source term is formed when radioactive materials generated in nuclear fuel leakage toward containment and the external environment to reactor containment. The implantated version in the ELEBRA system are composed of five codes: MARCH 3, TRAPMELT 3, THCCA, VANESA and NAVA. The original example case was used. The example consists of a small loca accident in a PWR type reactor. A sensitivity study for the TRAPMELT 3 code was carried out, modifying the 'TIME STEP' to estimate the processing time of CPU for executing the original example case. (M.C.K.) [pt

7 CFR 6.28 - Transfer of license.

Science.gov (United States)

2010-01-01

... Licensing Authority will transfer to such other person the historical, nonhistorical or designated license... escrow with the sole condition for return of escrow being that the Licensing Authority determines that... to whom the historical licenses were issued during the quota year in which the sale or conveyance...

Development of Reference Source Terms for EU-APR1400

Energy Technology Data Exchange (ETDEWEB)

Kim, ByungIl; Lee, Chonghui; Lee, Dongsu; Ko, Heejin; Kang, Sangho [KEPCO Engineering and Construction Co. Inc., Yongin (Korea, Republic of)

2014-05-15

These source terms are developed for the typical U. S. NPP and do not reflect the design characteristics of EU-APR1400 (1,400 MWe PWR) which will be applied for the EUR certification in European countries. The process of developing the RST for EU-APR1400 is to undergo a similar process that NUREG-1465 had gone through when it came out with its proposed source terms. The purpose of this study is to develop the EU-APR1400 design-specific RST complied with the EUR. The Large LOCA is the reference equence used in the NUREG-1465 evaluation, whereas the EUAPR1400 risk-significant sequences are dominated by small LOCA and non-LOCA sequences. Moreover, when considering the EU-APR1400 has many design features to mitigate the consequences of severe accident phenomena, it is not surprising that the aspects of both release fractions and durations are distinctly different from NUREG-1465. This RST will be continuously updated to reflect to the design features of EU-APR1400, and then, be used as the reference for design purposes such as criteria satisfaction of radioactivity releases, equipment survivability, control room habitability for severe accident, and so on.

Semi-implicit and fully implicit shock-capturing methods for hyperbolic conservation laws with stiff source terms

International Nuclear Information System (INIS)

Yee, H.C.; Shinn, J.L.

1986-12-01

Some numerical aspects of finite-difference algorithms for nonlinear multidimensional hyperbolic conservation laws with stiff nonhomogenous (source) terms are discussed. If the stiffness is entirely dominated by the source term, a semi-implicit shock-capturing method is proposed provided that the Jacobian of the source terms possesses certain properties. The proposed semi-implicit method can be viewed as a variant of the Bussing and Murman point-implicit scheme with a more appropriate numerical dissipation for the computation of strong shock waves. However, if the stiffness is not solely dominated by the source terms, a fully implicit method would be a better choice. The situation is complicated by problems that are higher than one dimension, and the presence of stiff source terms further complicates the solution procedures for alternating direction implicit (ADI) methods. Several alternatives are discussed. The primary motivation for constructing these schemes was to address thermally and chemically nonequilibrium flows in the hypersonic regime. Due to the unique structure of the eigenvalues and eigenvectors for fluid flows of this type, the computation can be simplified, thus providing a more efficient solution procedure than one might have anticipated

Semi-implicit and fully implicit shock-capturing methods for hyperbolic conservation laws with stiff source terms

International Nuclear Information System (INIS)

Yee, H.C.; Shinn, J.L.

1987-01-01

Some numerical aspects of finite-difference algorithms for nonlinear multidimensional hyperbolic conservation laws with stiff nonhomogeneous (source) terms are discussed. If the stiffness is entirely dominated by the source term, a semi-implicit shock-capturing method is proposed provided that the Jacobian of the source terms possesses certain properties. The proposed semi-implicit method can be viewed as a variant of the Bussing and Murman point-implicit scheme with a more appropriate numerical dissipation for the computation of strong shock waves. However, if the stiffness is not solely dominated by the source terms, a fully implicit method would be a better choice. The situation is complicated by problems that are higher than one dimension, and the presence of stiff source terms further complicates the solution procedures for alternating direction implicit (ADI) methods. Several alternatives are discussed. The primary motivation for constructing these schemes was to address thermally and chemically nonequilibrium flows in the hypersonic regime. Due to the unique structure of the eigenvalues and eigenvectors for fluid flows of this type, the computation can be simplified, thus providing a more efficient solution procedure than one might have anticipated. 46 references

Free Software Licenses and Other Free Licenses: Genetic Code of Digital Common Goods

Directory of Open Access Journals (Sweden)

Marco Ciurcina

2017-06-01

Full Text Available This article explores the history and describes the main features of free software licenses and other free licenses in an attempt to shed light on the reasons for their success in promoting individual behaviors converging towards the collective construction of digital commons.

Generic evaluation of feedwater transients and small break loss-of-coolant accidents in GE-designed operating plants and near-term operating license applications

International Nuclear Information System (INIS)

1980-01-01

The results are presented of a generic evaluation of feedwater transients, small-break loss-of-coolant accidents (LOCAs), and other TMI-2-related events for General Electric Company (GE)-designed operating plants and near-term operating license applications to confirm or establish the bases for the continued safe operation of the operating plants. The results of this evaluation are presented in this report in the form of a set of findings and recommendations in each of the principal review areas. Additional review of the accident is continuing and further information is being obtained and evaluated. Any new information will be reviewed and modifications will be made as appropriate

75 FR 3261 - Powertech (USA) Inc.; Dewey-Burdock Project; New Source Material License Application; Notice of...

Science.gov (United States)

2010-01-20

... NUCLEAR REGULATORY COMMISSION [Docket No. 40-9075; NRC-2009-0575] Powertech (USA) Inc.; Dewey... review process related to the Dewey- Burdock Uranium Project application, please contact the NRC... documents associated with the Dewey-Burdock Uranium Project, including the license application, are...

Licensing Teachers: Lessons from Other Professions.

Science.gov (United States)

Haberman, Martin

1986-01-01

The licensing of teachers should be modeled against professions similar to teaching rather than professions like medicine and architecture that are vastly different. Applying similar licensing practices can raise the status of teaching. Ignoring these licensing practices will prevent teachers from functioning as professionals. (MD)

Recent changes in UK legislation and the licensing of radiopharmacies

Energy Technology Data Exchange (ETDEWEB)

Monger, P N [Medicines Inspectorate, London (United Kingdom). Medicine Control Agency

1992-06-01

The implications of the recent loss of Crown Immunity to radiopharmacy in the NHS are reviewed. The options available are that the preparation of radiopharmaceuticals within a hospital will either be under the control of a pharmacist or be an activity licensed as 'Specials' manufacture. In the latter case requirements for inspection by the Medicines Control Agency, fees payable and the need for involvement of a pharmacist are reviewed. Requirements for the grant of a Specials Manufacturing Licence are presented in some detail. Reference is made to established and published sources of guidance, official and otherwise. Consideration is given to: staffing and personnel, open and closed procedures, environmental standards, handling of blood products, use of isolators, quality control and quality assurance, licensed and unlicensed materials, sterility testing, broth transfer tests, environmental monitoring and documentation. (author).

Evaluation of Long-term Performance of Enhanced Anaerobic Source Zone Bioremediation using mass flux

Science.gov (United States)

Haluska, A.; Cho, J.; Hatzinger, P.; Annable, M. D.

2017-12-01

Chlorinated ethene DNAPL source zones in groundwater act as potential long term sources of contamination as they dissolve yielding concentrations well above MCLs, posing an on-going public health risk. Enhanced bioremediation has been applied to treat many source zones with significant promise, but long-term sustainability of this technology has not been thoroughly assessed. This study evaluated the long-term effectiveness of enhanced anaerobic source zone bioremediation at chloroethene contaminated sites to determine if the treatment prevented contaminant rebound and removed NAPL from the source zone. Long-term performance was evaluated based on achieving MCL-based contaminant mass fluxes in parent compound concentrations during different monitoring periods. Groundwater concertation versus time data was compiled for 6-sites and post-remedial contaminant mass flux data was then measured using passive flux meters at wells both within and down-gradient of the source zone. Post-remedial mass flux data was then combined with pre-remedial water quality data to estimate pre-remedial mass flux. This information was used to characterize a DNAPL dissolution source strength function, such as the Power Law Model and the Equilibrium Stream tube model. The six-sites characterized for this study were (1) Former Charleston Air Force Base, Charleston, SC; (2) Dover Air Force Base, Dover, DE; (3) Treasure Island Naval Station, San Francisco, CA; (4) Former Raritan Arsenal, Edison, NJ; (5) Naval Air Station, Jacksonville, FL; and, (6) Former Naval Air Station, Alameda, CA. Contaminant mass fluxes decreased for all the sites by the end of the post-treatment monitoring period and rebound was limited within the source zone. Post remedial source strength function estimates suggest that decreases in contaminant mass flux will continue to occur at these sites, but a mass flux based on MCL levels may never be exceeded. Thus, site clean-up goals should be evaluated as order

Comparative assessment of licensing processes of uranium mines in Brazil

International Nuclear Information System (INIS)

Silva, K.M.; Menezes, R.M.; Mezrahi, A.

2002-01-01

Commercial operation of uranium mining and milling started in Brazil, at the Pocos de Caldas Unit, State of Minas Gerais, in 1982. The Pocos de Caldas Unit was licensed by the Brazilian Regulatory Body (CNEN) and its is now in the decommissioning process. In 2000, a new mining and milling installation, the Caetite Unit, located in State of Bahia, started operation. This paper will discuss how Brazilian Nuclear Energy Commission is licensing the Caetite Unit based on the lessons learned from the Pocos de Caldas Unit. The objective is to draw attention to the importance of the safety assessment for a new unit, specially considering that some wrong decisions were taken for the Pocos de Caldas unit. These decisions lead to less effective long term solutions to protect the environment. Notwithstanding the differences between the two units, it is of great value to use the acquired experience to avoid or minimize the short, medium and long term impacts to the environment and population in the new operation. (author)

The licensing processes influence on nuclear market

International Nuclear Information System (INIS)

Locatelli, Giorgio; Mancini, Mauro; Sainati, Tristano; Sallinen, Liisa

2011-01-01

The paper deals with the licensing nuclear power plants; it focuses primarily on the licensing process implications into the international nuclear market. Nowadays there are twenty-six countries that are planning to build new nuclear facilities, and thirty-seven where nuclear reactors are proposed; on the other hand, there are mainly ten international reactor vendors. At international level, there are few vendors that have sufficient resources, capabilities and experience to carry out the design and delivering of a nuclear power plant in the international market; On the other hand, the licensing processes are strictly dependent on national law frameworks, and on the nuclear policies. The paper proposes a comparison of six licensing processes (the ones established in Finland, France, Italy, South Korea, USA and UK), and analyzes its main features and implications; the IAEA licensing process is taken as reference point. The objective of the paper is to propose a systemic approach for considering the licensing procedures. The framework proposed enables facilitating the licensing management and inferring the main features of licensing contexts. The paper concludes with a forecast of the nuclear licensing context, especially with respect to the fourth generation of nuclear reactors. (author)

Whom to Choose as License Partner?

DEFF Research Database (Denmark)

Laursen, Keld; Reichstein, Toke; Trombini, Giulia

2013-01-01

between technology and market forces: if partners are market distant, the likelihood of technology license contractual partnership decreases with partners’ technological distance. Using data on the formation of license partnerships in the global biopharmaceutical industry over the period 1994......This paper investigates the matching of firms on the market for technology. The paper forwards two dimensions along which license formation occurs: technology and product-market. Both sides of the market search for a partner representing potential for high technology synergies to maximize licensing...