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...

75 FR 52456 - Customs Broker License Examination Individual Eligibility Requirements

Science.gov (United States)

2010-08-26

... DEPARTMENT OF HOMELAND SECURITY U.S. Customs and Border Protection 19 CFR Part 111 [USCBP-2008-0059; CBP Dec. 10-28] RIN 1651-AA74 Customs Broker License Examination Individual Eligibility Requirements AGENCY: Customs and Border Protection, Department of Homeland Security. ACTION: Final rule...

10 CFR 32.61 - Ice detection devices containing strontium-90; requirements for license to manufacture or...

Science.gov (United States)

2010-01-01

...; requirements for license to manufacture or initially transfer. 32.61 Section 32.61 Energy NUCLEAR REGULATORY COMMISSION SPECIFIC DOMESTIC LICENSES TO MANUFACTURE OR TRANSFER CERTAIN ITEMS CONTAINING BYPRODUCT MATERIAL... manufacture or initially transfer. An application for a specific license to manufacture or initially transfer...

15 CFR 738.4 - Determining whether a license is required.

Science.gov (United States)

2010-01-01

... 15 Commerce and Foreign Trade 2 2010-01-01 2010-01-01 false Determining whether a license is required. 738.4 Section 738.4 Commerce and Foreign Trade Regulations Relating to Commerce and Foreign Trade (Continued) BUREAU OF INDUSTRY AND SECURITY, DEPARTMENT OF COMMERCE EXPORT ADMINISTRATION REGULATIONS...

Nuclear safety requirements for operation licensing of Egyptian research reactors

International Nuclear Information System (INIS)

Ahmed, E.E.M.; Rahman, F.A.

2000-01-01

From the view of responsibility for health and nuclear safety, this work creates a framework for the application of nuclear regulatory rules to ensure safe operation for the sake of obtaining or maintaining operation licensing for nuclear research reactors. It has been performed according to the recommendations of the IAEA for research reactor safety regulations which clearly states that the scope of the application should include all research reactors being designed, constructed, commissioned, operated, modified or decommissioned. From that concept, the present work establishes a model structure and a computer logic program for a regulatory licensing system (RLS code). It applies both the regulatory inspection and enforcement regulatory rules on the different licensing process stages. The present established RLS code is then applied to the Egyptian Research Reactors, namely; the first ET-RR-1, which was constructed and still operating since 1961, and the second MPR research reactor (ET-RR-2) which is now in the preliminary operation stage. The results showed that for the ET-RR-1 reactor, all operational activities, including maintenance, in-service inspection, renewal, modification and experiments should meet the appropriate regulatory compliance action program. Also, the results showed that for the new MPR research reactor (ET-RR-2), all commissioning and operational stages should also meet the regulatory inspection and enforcement action program of the operational licensing safety requirements. (author)

Neutral-beam requirements for compression-boosted ignited tokamak plasmas

International Nuclear Information System (INIS)

Cohn, D.R.; Jassby, D.L.; Kreischer, K.

1977-12-01

Neutral-beam energies of 200 to 500-keV D 0 may be required to insure adequate penetration into the center of ignition-sized tokamak plasmas. However, the beam energy requirement can be reduced by using a start-up scenario in which the final plasma is formed by major-radius compression of a beam-heated plasma whose density-radius product, na, is determined by satisfactory neutral-beam penetration. ''Compression boosting'' is attractive only for plasmas in which ntau/sub E/ increases with na, because a major-radius compression C increases na by C 3 / 2 . The dependence on C of beam energy and beam power for plasmas which obey ''empirical scaling laws'' of the type ntau/sub E/ varies as (na) 2 is analyzed. The dependences on C of stored magnetic energy and TF-coil power dissipation are also determined. It is found that a compression ratio of 1.5 to attain the ignited plasma permits adequate penetration by 150-keV D 0 beams

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)

Application and licensing requirements of the Framatome ANP RLBLOCA methodology

International Nuclear Information System (INIS)

Martin, R.P.; Dunn, B.M.

2004-01-01

The Framatome ANP Realistic Large-Break LOCA methodology (FANP RLBLOCA) is an analysis approach approved by the US NRC for supporting the licensing basis of 3- and 4-loop Westinghouse PWRs and CE 2x4 PWRs. It was developed consistent with the NRC's Code Scaling, Applicability, and Uncertainty (CSAU) methodology for performing best-estimate large-break LOCAs. The CSAU methodology consists of three key elements with the second and third element addressing uncertainty identification and application. Unique to the CSAU methodology is the use of engineering judgment and the Process Identification and Ranking Table (PIRT) defined in the first element to lay the groundwork for achieving the ultimate goal of quantifying the total uncertainty in predicted measures of interest associated with the large-break LOCA. It is the PIRT that not only directs the methodology development, but also directs the methodology review. While the FANP RLBLOCA methodology was generically approved, a plant-specific application is customized in two ways addressing how the unique plant characterization 1) is translated to code input and 2) relates to the unique methodology licensing requirements. Related to the former, plants are required by 10 CFR 50.36 to define a technical specification limiting condition for operation based on the following criteria: 1. Installed instrumentation that is used in the control room to detect, and indicate, a significant abnormal degradation of the reactor coolant pressure boundary. 2. A process variable, design feature, or operating restriction that is an initial condition of a design basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier. 3. A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a

12 CFR 14.60 - Qualification and licensing requirements for insurance sales personnel.

Science.gov (United States)

2010-01-01

... 12 Banks and Banking 1 2010-01-01 2010-01-01 false Qualification and licensing requirements for insurance sales personnel. 14.60 Section 14.60 Banks and Banking COMPTROLLER OF THE CURRENCY, DEPARTMENT OF... insurance product or annuity in any part of its office or on its behalf, unless the person is at all times...

Stability in licensing requirements: a technical perspective

International Nuclear Information System (INIS)

Szalay, R.A.

1978-01-01

The serious difficulties encountered in the licensing procedure for nuclear power plants in the United States have resulted in the elaboration of a Bill on the siting and licensing of nuclear installations for the purpose of reforming the present system. The author fears, however, that this Bill will not reduce the complexity of present regulations and will be unable to reach the object sought which is to reduce the length of the procedure; he analyses the technical and political reasons underlying this situation, and in particular the role of the staff of the Nuclear Regulatory Commission. (NEA) [fr

Environmental qualification design for NPP refurbishment to comply with revised licensing requirements

International Nuclear Information System (INIS)

MacBeth, M. J.; Hemmings, R. L.

2002-01-01

Recent Canadian Nuclear Regulatory decisions have imposed Environmental Qualification (EQ) requirements for twenty-four Reactor Building (RB) airlocks at the four-unit Pickering Nuclear Generating Station-B (PNGS-B) facility. This paper describes the EQ modification design work completed by CANATOM-NPM for the problematic aspects for such projects. The airlocks allow RB access while providing a containment boundary and are designed to prevent a potential breach of containment for all analysed station conditions. Each PNGS-B unit has three large equipment airlocks and three smaller personnel airlocks. The airlocks must function under postulated worst-case design basis accident(DBA) conditions for assigned mission durations. The design must ensure that accident conditions cannot spuriously initiate an un-requested door opening. CANATOM-NPM reviewed site data to specify the necessary EQ modifications required to satisfy licensing requirements while providing a correct and complete as-found record of the existing airlock installation. The design team assessed the installed airlocks configuration against environmental qualification requirements to finalize the list of necessary modifications. A comprehensive, cross-discipline review of proposed design changes was completed to identify any further changes required to satisfy the final EQ licensing goal. The design team also conducted a design review of the EQ modification installation strategy to integrate the design deliverables with the installation team requirements while attempting to minimize necessary outage time for EQ modification installations. This project was completed on schedule and within the cost limitations required by the client with comprehensive, high quality final design packages. Overall improvements were realized for OPG system drawings and the electronic documentation of design data. The EQ modifications designed by CANATOM-NPM will ensure the continued operation of the PNGS-B NPP past December 31

Specification of requirements to get a license for an Independent Spent Fuel Dry Storage Installation (ISFSI) at the site of the NPP-LV

International Nuclear Information System (INIS)

Serrano R, M. L.

2015-09-01

This article describes some of the work done in the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) to define specifically the requirements that the Federal Electricity Commission (CFE) shall meet to submit for consideration of CNSNS an operation request of an Independent Spent Fuel Dry Storage Installation (ISFSI). The project of a facility of this type arose from the need to provide storage capacity for spent nuclear fuel in the nuclear power plant of Laguna Verde (NPP-LV) and to continue the operation at the same facility in a safe manner. The licensing of these facilities in the United States of America has two modes: specific license or general license. The characteristics of these licenses are described in this article. However, in Mexico the existing national legislation is not designed for such license types, in fact there is a lack of standards or regulations in this regard. The regulatory law of Article 27 of the Constitution in the nuclear matter, only generally establishes that this type of facility requires an authorization from the Ministry of Energy. For this reason and because there is not a national legislation, was necessary to use the legislation that provides the Nuclear Regulatory Commission of USA, the US NRC. However, it cannot be applied as is established, so was necessary that the CNSNS analyze one by one the requirements of both types of license and determine what would be required to NPP-LV to submit its operating license of ISFSI. The American regulatory applicable to an ISFSI, the 10-Cfr-72 of the US NRC, establishes the requirements for both types of licenses. Chapter 10-Cfr was analyzed in all its clauses and coupled to the laws, regulations and standards as well as to the requirements established by CNSNS, all associated with a store spent fuel on site; the respective certification of containers for spent fuel dry storage was not included in this article, even though the CNSNS also performed that activity under the

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

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

Licensing and supervision of nuclear facilities in Finland; Genehmigung und Aufsicht von nuklearen Anlagen in Finnland

Energy Technology Data Exchange (ETDEWEB)

Laaksonen, J. [STUK - Radiation and Nuclear Safety Authority, Helsinki (Finland)

2006-01-01

In Finland, the licensing process of all nuclear facilities is specified in the Nuclear Energy Act. The licensing procedure comprises three steps, each of which requires a decision by the government: basic decision, construction permit, and operating license. All licensing decisions are taken upon application to the Ministry of Trade and Industry. The Ministry invites comments and opinions on a broad basis and drafts a statement for the government. The basic decision by the government is political, pre-supposing a positive statement by the Central Office for Nuclear Safety (STUK) and a positive decision by the local government of the planned plant location. The construction permit and the operating license are mainly based on points of nuclear safety. STUK is the independent nuclear supervisory agency with administrative powers; its staff has the technical and scientific competence required for safety assessments and for supervision. STUK operates under the supervision of the Ministry for Social Affairs and Health which, to demonstrate its independence, has no duties in the energy sector and, in addition, supervises STUK in administrative matters, not in scientific and technical decisions. Internal rules of STUK ensure neutrality also of its staff in matters of energy policy. The activities of STUK as a supervisory and licensing authority in Finland are described in detail for the management of spent nuclear fuel and the new Olkiluoto 3 nuclear power plant currently under construction. (orig.)

[Radiation protection in medical research : Licensing requirement for the use of radiation and advice for the application procedure].

Science.gov (United States)

Minkov, V; Klammer, H; Brix, G

2017-07-01

In Germany, persons who are to be exposed to radiation for medical research purposes are protected by a licensing requirement. However, there are considerable uncertainties on the part of the applicants as to whether licensing by the competent Federal Office for Radiation Protection is necessary, and regarding the choice of application procedure. The article provides explanatory notes and practical assistance for applicants and an outlook on the forthcoming new regulations concerning the law on radiation protection of persons in the field of medical research. Questions and typical mistakes in the application process were identified and evaluated. The qualified physicians involved in a study are responsible for deciding whether a license is required for the intended application of radiation. The decision can be guided by answering the key question whether the study participants would undergo the same exposures regarding type and extent if they had not taken part in the study. When physicians are still unsure about their decision, they can seek the advisory service provided by the professional medical societies. Certain groups of people are particularly protected through the prohibition or restriction of radiation exposure. A simplified licensing procedure is used for a proportion of diagnostic procedures involving radiation when all related requirements are met; otherwise, the regular licensing procedure should be used. The new radiation protection law, which will enter into force on the 31st of december 2018, provides a notification procedure in addition to deadlines for both the notification and the licensing procedures. In the article, the authors consider how eligible studies involving applications of radiation that are legally not admissible at present may be feasible in the future, while still ensuring a high protection level for study participants.

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

77 FR 3386 - Export and Reexport License Requirements for Certain Microwave and Millimeter Wave Electronic...

Science.gov (United States)

2012-01-24

... microwave ``monolithic integrated circuits'' power amplifiers that meet certain criteria with respect to... packaged microwave ``monolithic integrated circuits'' (MMIC) power amplifiers that meet certain criteria.... 110825537-2038-02] RIN 0694-AF38 Export and Reexport License Requirements for Certain Microwave and...

Seismic risk evaluation within the technology neutral framework

International Nuclear Information System (INIS)

Johnson, B.C.; Apostolakis, G.E.

2012-01-01

Highlights: ► We examine seismic risk within the Technology Neutral Framework (TNF). ► We find that the risk goals in the TNF to be stringent compared with current goals. ► We note that the current fleet reactors would not meet the TNF goals. ► We recommend that an initiating frequency cutoff of 10 −5 per year be use in evaluating seismic risk. - Abstract: The NRC Office of Nuclear Regulatory Research has proposed a risk-informed and performance-based licensing process that is referred to as the technology neutral framework (TNF). In the TNF, licensing basis events (LBEs), determined using probabilistic risk assessment methods, take the place of design basis accidents. These LBEs are constructed by grouping together accident sequences with similar phenomenology. All event sequences with a mean frequency greater than 10 −7 per reactor year are to be considered as part of the licensing basis. Imposing such a limit would require that earthquakes with a mean return period of ten million years be considered as part of the licensing basis. It is difficult to get seismic hazards (i.e., ground accelerations) from expert seismologists at such low frequencies. This is because it is difficult or impossible to confidently say what the seismic hazard might be at these extremely low frequencies. A linear extrapolation in log-log space of hazard curves at the Clinton site down to 10 −7 per year leads to a peak ground acceleration of about 4.5 g. A Weibull distribution is also used to fit the curve leading to a peak ground acceleration of about 2.6 g. These extrapolations demonstrate the extreme nature of rare earthquakes. Even when seismic isolation is implemented, the TNF goal is not met. The problem appears to be that there is no limit on initiating event frequency in the TNF. Demonstrating that a design meets the goals of the TNF would be nearly impossible. A frequency limit for earthquakes could be imposed at a frequency of about 10 −5 per year to focus on

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

To License or Not to License: An Examination of State Statutes Regarding Private Investigators and Digital Examiners

Directory of Open Access Journals (Sweden)

Thomas Lonardo

2008-09-01

Full Text Available In this paper the authors examine statutes that regulate, license, and enforce investigative functions in each US state. After identification and review of Private Investigator licensing requirements, the authors find that very few state statutes explicitly differentiate between Private Investigators and Digital Examiners. After contacting all state agencies the authors present a distinct grouping organizing state approaches to professional Digital Examiner licensing. The authors conclude that states must differentiate between Private Investigator and Digital Examiner licensing requirements and oversight.

Neutral Beam Injection Requirements and Design Issues for the National Compact Stellarator Experiment

International Nuclear Information System (INIS)

Kugel, H.W.; Neilson, H.; Reiersen, W.; Zarnstorff, M.

2002-01-01

The National Compact Stellarator Experiment (NCSX) will require 6 MW of 50 keV neutral beam injection (NBI) with initial pulse lengths of 500 msec and upgradeable to pulse lengths of 1.5 sec. This paper discusses the NCSX NBI requirements and design issues, and shows how these are provided by the candidate PBX-M [Princeton Beta Experiment-Modification] NBI system

Current status of the PBMR licensing project

International Nuclear Information System (INIS)

Mysen, A.; Clapisson, G.A.; Metcalf, P.E.

2000-01-01

The CNS is currently reviewing the PBMR conceptual design from a licensibility point of view. The PBMR concept is based on a High Temperature Gas Cooled Reactor - pebble bed reactor type. It is anticipated that the PBMR design will rely on inherent safety characteristics to contain fission products within fuel over the full range of design basis events. This feature combined with the high temperature integrity of the fuel and structural graphite, allows the safe use of a high coolant temperature, which allows consideration of the future development of this reactor for non-electrical applications of nuclear heat for industrial use. The CNS licensing approach requires that the licensing and design basis of the plant should respect prevailing international norms and practices and that a quantitative risk assessment should demonstrate compliance with the CNS fundamental safety standards. The first stage of the licensing process is now ongoing; this is a pre-application phase, which will result in a statement on licensibility being issued. Identification of the specific documentation requirements and information needed is required across every step of the licensing process. Top level regulatory requirements have been established for the PBMR. They include the CNS fundamental safety standard and basic licensing criteria, which describes requirements on licensees of nuclear installations regarding risk assessment and compliance with the safety criteria and define classification of licensing basis events. (author)

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

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...

Guidelines to implement the license renewal technical requirements of 10CFR54 for integrated plant assessments and time-limited aging analyses. Final report

International Nuclear Information System (INIS)

Lehnert, G.; Philpot, L.

1995-11-01

This report documents the initial results of the Nuclear Energy Institute License Renewal Implementation Guideline Task Force over the period August 1994 to July 1995 to develop guidance for complying with technical requirements of 10CFR54. The report also provided a starting point for the development of NEI 95-10, ''Industry Guideline for Implementing the Requirements of 10CCR54-The License Renewal Rule''. Information in this document can be used by utilities to prepare the technical material needed in an application for license renewal (LR) of a nuclear power unit. This guideline provides methods for identifying systems, structures, and components (SSCs) and their intended functions within the scope of license renewal. It identifies structures and components (SCs) requiring aging management review and methods for performing the aging management review. The guideline provides a process for identifying and evaluating time-limited aging analyses

International vision requirements for driver licensing and disability pensions: using a milestone approach in characterization of progressive eye disease

Directory of Open Access Journals (Sweden)

Alain M Bron

2010-11-01

Full Text Available Alain M Bron1, Ananth C Viswanathan2, Ulrich Thelen3, Renato de Natale4, Antonio Ferreras5, Jens Gundgaard6, Gail Schwartz7, Patricia Buchholz81Department of Ophthalmology, University Hospital, Dijon, France; 2Glaucoma Research Unit, Moorfields Eye Hospital NHS Foundation Trust and Department of Genetics, University College of London Institute of Ophthalmology, London, UK; 3Private Practice, Munster, Germany; 4Ospedale Civile di Monselice, Monselice, Italy; 5Ophthalmology, Miguel Servet University Hospital, Zaragoza, Spain; 6COWI, Kolding, Denmark; 7Wilmer Eye Institute, Johns Hopkins University, Glaucoma Consultants, Baltimore, MD, USA; 8Patricia Buchholz Consulting, Karlsruhe, GermanyObjective: Low vision that causes forfeiture of driver’s licenses and collection of disability pension benefits can lead to negative psychosocial and economic consequences. The purpose of this study was to review the requirements for holding a driver’s license and rules for obtaining a disability pension due to low vision. Results highlight the possibility of using a milestone approach to describe progressive eye disease.Methods: Government and research reports, websites, and journal articles were evaluated to review rules and requirements in Germany, Spain, Italy, France, the UK, and the US.Results: Visual acuity limits are present in all driver’s license regulations. In most countries, the visual acuity limit is 0.5. Visual field limits are included in some driver’s license regulations. In Europe, binocular visual field requirements typically follow the European Union standard of ≥120°. In the US, the visual field requirements are typically between 110° and 140°. Some countries distinguish between being partially sighted and blind in the definition of legal blindness, and in others there is only one limit.Conclusions: Loss of driving privileges could be used as a milestone to monitor progressive eye disease. Forfeiture could be standardized as a

Nuclear fuel licensing requirements: present status and future trends

International Nuclear Information System (INIS)

Gantchev, T.; Vitkova, M.; Gorinov, I.; Datcheva, D.; Rashkova, N.

2001-01-01

The nuclear fuel licensing process must be directed to establishing of criteria for licensing (fuel safety criteria) and relationship between safety limits, technical specifications and operational conditions. This paper discusses the fuel safety criteria as used by NRC and Russian vendor. A survey on the available fuel behavior, modeling and related computer codes is given with respect to help the licensing process including new safety features of general changes in fuel design and operational conditions. Several types of computer codes that are used in safety analysis are sensitive to fuel-related parameters. The need for further code development and verification has been stated on many occasions: new design elements, such as different cladding materials, higher burnup, different fuel microstructure and use of MOX fuel can affect the performance of these codes. Regulatory inspection practices during operation and refueling in different countries are also shown. Future trends are discussed in particular with regard to the coming high burnup and to new core management schemes

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.

47 CFR 80.13 - Station license required.

Science.gov (United States)

2010-10-01

... signals using a marine radio operating in the 156-162 MHz band, any type of AIS, any type of EPIRB, and any type of radar installation. All other transmissions must be authorized under a ship station... paragraph (c) of this section, stations in the maritime service must be licensed by the FCC either...

47 CFR 25.262 - Licensing and domestic coordination requirements for 17/24 GHz BSS space stations.

Science.gov (United States)

2010-10-01

... 47 Telecommunication 2 2010-10-01 2010-10-01 false Licensing and domestic coordination requirements for 17/24 GHz BSS space stations. 25.262 Section 25.262 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) COMMON CARRIER SERVICES SATELLITE COMMUNICATIONS Technical Standards § 25.262...

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)

Neutral Beam Injection Requirements and Design Issues for the National Compact Stellarator Experiment; TOPICAL

International Nuclear Information System (INIS)

H.W. Kugel; H. Neilson; W. Reiersen; M. Zarnstorff

2002-01-01

The National Compact Stellarator Experiment (NCSX) will require 6 MW of 50 keV neutral beam injection (NBI) with initial pulse lengths of 500 msec and upgradeable to pulse lengths of 1.5 sec. This paper discusses the NCSX NBI requirements and design issues, and shows how these are provided by the candidate PBX-M[Princeton Beta Experiment-Modification] NBI system

License to Learn

DEFF Research Database (Denmark)

Leone, Maria Isabella; Boccardelli, Paolo; Reichstein, Toke

2016-01-01

the technology. Drawing on a sample of 133 licensees and an equal number of matched nonlicensees, we present empirical evidence that thick contracts propel the licensees' likelihood of introducing new inventions. It is also found that thick contracts act as a substitute for licensees' absorptive capacity....... Licensees that are more familiar with the licensed technology are in less need of assistance from the licensors to assimilate and integrate the knowledge. However, this substitution effect is neutralized once the hurdle of invention has been overcome, meaning that the licensees have succeeded to ignite...... the invention process, suggesting the exploitation of the learning curve, triggered by their mutual understanding....

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

Adaptive evolutionary walks require neutral intermediates in RNA fitness landscapes.

Science.gov (United States)

Rendel, Mark D

2011-01-01

In RNA fitness landscapes with interconnected networks of neutral mutations, neutral precursor mutations can play an important role in facilitating the accessibility of epistatic adaptive mutant combinations. I use an exhaustively surveyed fitness landscape model based on short sequence RNA genotypes (and their secondary structure phenotypes) to calculate the minimum rate at which mutants initially appearing as neutral are incorporated into an adaptive evolutionary walk. I show first, that incorporating neutral mutations significantly increases the number of point mutations in a given evolutionary walk when compared to estimates from previous adaptive walk models. Second, that incorporating neutral mutants into such a walk significantly increases the final fitness encountered on that walk - indeed evolutionary walks including neutral steps often reach the global optimum in this model. Third, and perhaps most importantly, evolutionary paths of this kind are often extremely winding in their nature and have the potential to undergo multiple mutations at a given sequence position within a single walk; the potential of these winding paths to mislead phylogenetic reconstruction is briefly considered. Copyright © 2010 Elsevier Inc. All rights reserved.

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

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

Meeting United States re-licensing requirements related to environmental protection using innovative technologies

International Nuclear Information System (INIS)

Taft, E.P.; Winchell, F.C.; Cook, T.C.

1998-01-01

Procedure for meeting re-licensing requirements related to environmental protection and an overview of several new and emerging technologies regarding the development of ways to prevent fish passage through hydraulic turbines at hydroelectric power dams is described. Fish mortality and injury has long been a concern in the hydroelectric industry and research and development efforts have been ongoing since the 1970s to prevent fish passage through turbines. Several new and emerging technologies are examined that have the potential for wide-spread cost-effective applications

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.

10 CFR 32.22 - Self-luminous products containing tritium, krypton-85 or promethium-147: Requirements for license...

Science.gov (United States)

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Self-luminous products containing tritium, krypton-85 or... containing tritium, krypton-85 or promethium-147: Requirements for license to manufacture, process, produce... self-luminous products containing tritium, krypton-85, or promethium-147, or to initially transfer such...

Teacher License Reciprocity. 50-State Review

Science.gov (United States)

Aragon, Stephanie

2017-01-01

This policy report defines and provides a 50-state review of teacher license reciprocity, explores how state-specific licensing requirements impact the teacher labor market, and includes examples of national and state efforts to facilitate reciprocity.

47 CFR 25.137 - Application requirements for earth stations operating with non-U.S. licensed space stations.

Science.gov (United States)

2010-10-01

... space stations. (a) Earth station applicants or entities filing a “letter of intent” or “Petition for... Union. (d) Earth station applicants requesting authority to operate with a non-U.S.-licensed space... 47 Telecommunication 2 2010-10-01 2010-10-01 false Application requirements for earth stations...

Licensing evaluation of CANDU-PHW nuclear power plants relative to U.S. regulatory requirements

International Nuclear Information System (INIS)

Erp, J.B. van

1978-01-01

Differences between the U.S. and Canadian approach to safety and licensing are discussed. U.S. regulatory requirements are evaluated as regards their applicability to CANDU-PHW reactors; vice-versa the CANDU-PHW reactor is evaluated with respect to current Regulatory Requirements and Guides. A number of design modifications are proposed to be incorporated into the CANDU-PHW reactor in order to facilitate its introduction into the U.S. These modifications are proposed solely for the purpose of maintaining consistency within the current U.S. regulatory system and not out of a need to improve the safety of current-design CANDU-PHW nuclear power plants. A number of issues are identified which still require resolution. Most of these issues are concerned with design areas not (yet) covered by the ASME code. (author)

Licensing of ''grandfather's'' facilities: Ukrainian experience

International Nuclear Information System (INIS)

Mikolaitchouk, H.; Bogdan, L.; Steinberg, N.

1995-01-01

In the former USSR, unlike most countries, radioactive waste management activities including waste disposal needed no license. But after the USSR breakdown the Ukrainian Parliament -- Verkhovna Rada -- invoked the revised Law on Business activities. According to Article 4 of the Law, in order to treat or to dispose radioactive waste every enterprise has to get a special permission or license. In compliance with the Law, the Cabinet of Ministers by its Ordinance of January 13, 1993, authorized the Ukrainian State Committee for Nuclear and Radiation Safety (UkrSCNRS) to issue special permissions or licenses for waste treatment and disposal. And that requirement was valid not only for future activities but also for existing facilities in operation. Taking into account the undergoing legislative process, SCNRS began to develop its licensing process without waiting for the special nuclear laws to be passed. On the basis of the legislation already in effect, first of all the Law on Enterprises (full responsibility of enterprises for their activities) and Law on Business activities (requirement to have a license for special types of activities), the newly formed national regulatory body had to identify all the enterprises that needed to be licensed, to establish relevant procedures, to develop related regulatory documents, to implement these procedures and documents at operating enterprises, and for each case to make a decision concerning feasibility of issuing a license, period of validity and license conditions

Regulatory guidance for license renewal

International Nuclear Information System (INIS)

Thoma, John A.

1991-01-01

The proposed 10 CFR Part 54 rule proceduralizes the process for license renewal by identifying both the administrative and technical requirements for a renewal application. To amplify and support this regulation, written guidance has been provided in the form of a draft Regulatory Guide (DG 1009) and a draft Standard Review Plan for License Renewal (NUREG 1299). This guidance is scheduled to be finalized in 1992. Similar guidance will be provided for the proposed revisions to 10 CFR Part 51 concerning the environmental aspects of license renewal. (author)

Scallop License Limitation Program (SLLP) Permit Program

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — A federal Scallop License Limitation Program (SLLP) license is required onboard any vessel deployed in scallop fisheries in Federal waters off Alaska (except for...

Licensing plan for UMTRA project disposal sites

International Nuclear Information System (INIS)

1993-09-01

The Uranium Mill Tailings Remedial Action (UMTRA) Project Office developed a plan to define UMTRA Project licensing program objectives and establish a process enabling the DOE to document completion of remedial actions in compliance with 40 CFR 1 92 and the requirements of the NRC general license. This document supersedes the January 1987 Project Licensing Plan (DOE, 1987). The plan summarizes the legislative and regulatory basis for licensing, identifies participating agencies and their roles and responsibilities, defines key activities and milestones in the licensing process, and details the coordination of these activities. This plan provides an overview of the UMTRA Project from the end of remedial actions through the NRC's acceptance of a disposal site under the general license. The licensing process integrates large phases of the UMTRA Project. Other programmatic UMTRA Project documents listed in Section 6.0 provide supporting information

Nuclear power plant operator licensing

International Nuclear Information System (INIS)

1997-01-01

The guide applies to the nuclear power plant operator licensing procedure referred to the section 128 of the Finnish Nuclear Energy Degree. The licensing procedure applies to shift supervisors and those operators of the shift teams of nuclear power plant units who manipulate the controls of nuclear power plants systems in the main control room. The qualification requirements presented in the guide also apply to nuclear safety engineers who work in the main control room and provide support to the shift supervisors, operation engineers who are the immediate superiors of shift supervisors, heads of the operational planning units and simulator instructors. The operator licensing procedure for other nuclear facilities are decided case by case. The requirements for the basic education, work experience and the initial, refresher and complementary training of nuclear power plant operating personnel are presented in the YVL guide 1.7. (2 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

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)

Cost and risk reduction using upfront licensing in Canada. Annex 15

International Nuclear Information System (INIS)

Snell, V.G.

2002-01-01

The paper summarizes the use of 'up-front' licensing in Canada - how licensing requirements are defined, and met - in advance of a project commitment. The approach to licensing in Canada has allowed flexibility in development of new designs. Since licensing was originally risk-based, and current regulatory policy allows cost-benefit considerations as part of the decision making, risk can be and should be used in novel circumstances as a licensing tool. Since the licensing framework is non-prescriptive, innovative approaches to design can be introduced and dispositioned without changing the legal structure. This flexibility has been used in several up-front licensing reviews: a small urban heating reactor, repeat CANDU 6 generating station units, and the single unit CANDU 9 generating station. In the future we expect to apply it to advanced designs, as an essential part of risk reduction and customer confidence in the product. The important lessons learned in Canada include: Up-front licensing is essential to reduce the risk of licensing-related delays once a project has been committed. It requires a significant investment in time and effort from both the designer and the regulator; The most effective scope for up-front licensing is for the regulator to thoroughly assess novel concepts, test the design against changed domestic requirements, and follow-up on known difficult areas; and for the designer to ensure foreign requirements are incorporated. There is little benefit in certifying the design in detail; Although it would be satisfying to have legally-binding certification, in the end there can be no legal obligation on the regulator, and agreement is pursued on the basis of good faith that the regulator will not make arbitrary decisions and that the designer will meet agreed targets or requirements; In almost all circumstances, issues will arise that are beyond the current 'rules', however expressed. Rather than rushing to create new rules, one reaches a

Licensing and Environmental Issues of Wave Energy Projects

DEFF Research Database (Denmark)

Neumann, Frank; Tedd, James; Prado, Miguel

2006-01-01

a special standing or facilitated access to operating licenses due to their experimental character, the move of wave energy projects towards commercial applications implies complex procedures for obtaining licenses both with respect to the construction and deployment and operation phases, as well......The major non-technical barrier for large-scale wave energy implementation is the wide range of licensing issues and potential environmental concerns, in addition to significant National/regional differences in licensing procedures and permit requirements. Whereas some pilot plants have had...... as concerning ocean space use and environmental concerns. Despite recent efforts to streamline European EIA (Environmental Impact Assessment) in general, potential project developers are far from having a clear view of present and future requirements concerning these barriers on a trans-national level...

Neutral beam energy and power requirements for expanding radius and full bore startup of tokamak reactors

International Nuclear Information System (INIS)

Houlberg, W.A.; Mense, A.T.; Attenberger, S.E.

1979-09-01

Natural beam power and energy requirements are compared for full density full bore and expanding radius startup scenarios in an elongated plasma, The Next Step (TNS), as a function of beam pulse time and plasma density. Because of the similarity of parameters, the results should also be applicable to Engineering Test Facility (ETF) and International Tokamak Reactor (INTOR) studies. A transport model consisting of neoclassical ion conduction and anomalous electron conduction and diffusion based on ALCATOR scaling leads to average densities in the range approx. 0.8 to 1.2 x 10 14 cm -3 being sufficient for ignition. Neutral deuterium beam energies in the range 120 to 180 keV are adequate for penetration, with the required power injected into the plasma decreasing with increasing beam energy. The neutral beam power decreases strongly with increasing beam pulse length b/sub b/ until t/sub b/ exceeds a few total energy confinement times, yielding b/sub b/ approx. = 4 to 6 s for the TNS plasma

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

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

Survey of extreme load design regulatory agency licensing requirements for nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Stevenson, J D

1976-04-01

Since 1965, when extreme load requirements began to be considered explicitly in nuclear power plant design, there has been a gradual divergence in requirements imposed by national regulatory agencies. However, nuclear plant safety is an international problem because of the potential international effects of any postulated plant failure. For this reason this paper has been prepared in an attempt to highlight the differences in national criteria currently used in the extreme load design of nuclear plant facilities. No attempt has been made to evaluate the relative merit of the criteria established by the various national regulatory agencies. This paper presents the results of a recent survey made of national atomic energy regulatory agencies and major nuclear steam supply design agencies, which requested a summary of current licensing criteria associated with earthquake, extreme wind (tornado), flood, airplane crash and accident (pipe break) loads applicable within the various national jurisdictions. Also presented are a number of comparisons which are meant to illustrate the differences in national regulatory criteria.

Survey of extreme load design regulatory agency licensing requirements for nuclear power plants

International Nuclear Information System (INIS)

Stevenson, J.D.

1976-01-01

Since 1965, when extreme load requirements began to be considered explicitly in nuclear power plant design, there has been a gradual divergence in requirements imposed by national regulatory agencies. However, nuclear plant safety is an international problem because of the potential international effects of any postulated plant failure. For this reason this paper has been prepared in an attempt to highlight the differences in national criteria currently used in the extreme load design of nuclear plant facilities. No attempt has been made to evaluate the relative merit of the criteria established by the various national regulatory agencies. This paper presents the results of a recent survey made of national atomic energy regulatory agencies and major nuclear steam supply design agencies, which requested a summary of current licensing criteria associated with earthquake, extreme wind (tornado), flood, airplane crash and accident (pipe break) loads applicable within the various national jurisdictions. Also presented are a number of comparisons which are meant to illustrate the differences in national regulatory criteria. (Auth.)

Licensing and advanced fuel designs

International Nuclear Information System (INIS)

Davidson, S.L.; Novendstern, E.H.

1991-01-01

For the past 15 years, Westinghouse has been actively involved in the development and licensing of fuel designs that contain major advanced features. These designs include the optimized fuel assembly, The VANTAGE 5 fuel assembly, the VANTAGE 5H, and most recently the VANTAGE+ fuel assembly. Each of these designs was supported by extensive experimental data, safety evaluations, and design efforts and required intensive interaction with the US Nuclear Regulatory Commission (NRC) during the review and approval process. This paper presents a description of the licensing approach and how it was utilized by the utilities to facilitate the licensing applications of the advanced fuel designs for their plants. The licensing approach described in this paper has been successfully applied to four major advanced fuel design changes ∼40 plant-specific applications, and >350 cycle-specific reloads in the past 15 years

Overview of the Yucca Mountain Licensing Process

International Nuclear Information System (INIS)

M. Wisenburg

2004-01-01

This paper presents an overview of the licensing process for a Yucca Mountain repository for high-level radioactive waste and spent nuclear fuel. The paper discusses the steps in the licensing proceeding, the roles of the participants, the licensing and hearing requirements contained in the Code of Federal Regulations. A description of the Nuclear Regulatory Commission (NRC) staff acceptance and compliance reviews of the Department of Energy (DOE) application for a construction authorization and a license to receive and possess high-level radioactive waste and spent nuclear fuel is provided. The paper also includes a detailed description of the hearing process

Review of the first partial licence for the Muelheim-Kaerlich reactor on the basis of the licensing requirements under nuclear law

International Nuclear Information System (INIS)

Hahn, L.; Wimmer, J.

1990-11-01

The expert opinion is restricted in the main to the licensing requirements in connection with the latest state-of-the-art precautionary measures against damage, i.e. subsection 3 of paragraph 7 section 2 Atomic Energy Act. Subject of the evaluations regarding the required new scope of licensing were the cancelled first partial licence, subsequent partial licences, the TUEV (Technical Control Board) expert opinion, the safety report with its continuations as well as the judgments of the Higher Administrative Court in Koblenz and the Federal Administrative Court. For determining the state-of-the-art, the expert opinion refers to the valid body of regulations, the latest concepts for PWRs in particular in the Federal Republic of Germany, and more recent results in reactor safety research. (orig./DG) [de

Site Specific Vendor's License

Data.gov (United States)

Montgomery County of Maryland — This dataset contains information of a site-specific vendor's license which is required if an individual sells or offers to sell goods or services from a stationary...

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

Groundfish/Crab License Limitation Program (LLP) Permit Program

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — As of January 1, 2000 a Federal License Limitation Program (LLP) license is required for vessels participating in directed fishing for LLP groundfish species in the...

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

48 CFR 1852.225-70 - Export Licenses.

Science.gov (United States)

2010-10-01

... writing, that the Contracting Officer authorizes it to export ITAR-controlled technical data (including... licenses or other approvals, if required, for exports of hardware, technical data, and software, or for the provision of technical assistance. (b) The Contractor shall be responsible for obtaining export licenses, if...

48 CFR 227.7009 - Patent releases, license agreements, and assignments.

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false Patent releases, license... ACQUISITION REGULATIONS SYSTEM, DEPARTMENT OF DEFENSE GENERAL CONTRACTING REQUIREMENTS PATENTS, DATA, AND COPYRIGHTS Infringement Claims, Licenses, and Assignments 227.7009 Patent releases, license agreements, and...

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

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.

Atomic Safety and Licensing Board Panel annual report

International Nuclear Information System (INIS)

1991-09-01

In Fiscal Year 1990, The Atomic Safety and Licensing Board Panel (Panel) handled 40 proceedings involving the construction, operation, and maintenance of commercial nuclear power reactors or other activities requiring a license from the Nuclear Regulatory Commission. This report summarizes, highlights, and analyzes how the judges and licensing boards of the Panel addressed the wide-ranging issues raised in these proceedings during the year

Main features of licensing requirements for nuclear installations in several OECD member countries

International Nuclear Information System (INIS)

Reyners, P.

1977-01-01

The present paper contains a brief description of the main features of the above-mentioned six countries' licensing systems, namely the legal regime applicable, the appropriate licensing bodies, the general frame and scope of the respective national regimes, the involvement of the public and technical safety bodies as well as the inspection procedures. This description is supplemented by some introductory remarks. (orig.) [de

Main features of licensing requirements for nuclear installations in several OECD member countries

International Nuclear Information System (INIS)

Reyners, P.

1975-01-01

The present paper contains a brief description of the main features of the above-mentioned six countries' licensing systems, namely the legal regime applicable, the appropriate licensing bodies, the general frame and scope of the respective national regimes, the involvement of the public and technical safety bodies as well as the inspection procedures. This description is supplemented by some introductory remarks. (orig.) [de

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

A meta-analytic review of moral licensing.

Science.gov (United States)

Blanken, Irene; van de Ven, Niels; Zeelenberg, Marcel

2015-04-01

Moral licensing refers to the effect that when people initially behave in a moral way, they are later more likely to display behaviors that are immoral, unethical, or otherwise problematic. We provide a state-of-the-art overview of moral licensing by conducting a meta-analysis of 91 studies (7,397 participants) that compare a licensing condition with a control condition. Based on this analysis, the magnitude of the moral licensing effect is estimated to be a Cohen's d of 0.31. We tested potential moderators and found that published studies tend to have larger moral licensing effects than unpublished studies. We found no empirical evidence for other moderators that were theorized to be of importance. The effect size estimate implies that studies require many more participants to draw solid conclusions about moral licensing and its possible moderators. © 2015 by the Society for Personality and Social Psychology, Inc.

47 CFR 25.117 - Modification of station license.

Science.gov (United States)

2010-10-01

... 47 Telecommunication 2 2010-10-01 2010-10-01 false Modification of station license. 25.117 Section 25.117 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) COMMON CARRIER SERVICES SATELLITE COMMUNICATIONS Applications and Licenses General Application Filing Requirements § 25.117...

45 CFR 1321.75 - Licenses and safety.

Science.gov (United States)

2010-10-01

... 45 Public Welfare 4 2010-10-01 2010-10-01 false Licenses and safety. 1321.75 Section 1321.75... AND COMMUNITY PROGRAMS ON AGING Service Requirements § 1321.75 Licenses and safety. The State shall... that the facility complies with all applicable State and local health, fire, safety, building, zoning...

Licensing and supervision of nuclear facilities in Finland; Genehmigung und Aufsicht von nuklearen Anlagen in Finnland

Energy Technology Data Exchange (ETDEWEB)

Laaksonen, J. [Finnish Centre for Radiation and Nuclear Safety (STUK), Helsinki (Finland)

2005-07-01

STUK is the independent nuclear supervisory agency in Finland with administrative powers; its staff has the technical and scientific competence required for safety assessments and for supervision. STUK operates under the supervision of the Ministry for Social Affairs and Health which, to demonstrate its independence, has no duties in the energy sector and, in addition, supervises STUK in administrative matters, not in scientific and technical decisions. Internal rules of STUK ensure neutrality also of its staff in matters of energy policy. The activities of STUK as a supervisory and licensing authority in Finland are described in detail for the management of spent nuclear fuel and the new Olkiluoto 3 nuclear power plant currently under construction. (orig./GL)

Looking at the licensability of System 80+ in the UK

International Nuclear Information System (INIS)

Molnar, C.M.

1993-01-01

There are today no internationally-sanctioned nuclear power plant design or licensing guidelines, or acceptance criteria, available for a standard plant design that would have multi-national regulatory acceptability. On the contrary, a diversity of national regulations govern the design and licensing of nuclear power stations around the world. When licensing a nuclear facility in this environment, it is important for all parties (utility, designer and regulator) to recognise consciously that there are numerous solutions available to satisfy varying safety requirements. There is no one right-way - there are only trade-offs justified on safety, performance benefit and cost, which, taken together, fashion designs that conform to national licensing requirements. (Author)

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)

Safety and licensing requirements in the Republic of South Africa

International Nuclear Information System (INIS)

Simpson, D.M.; Langford, E.L.

1986-01-01

The principles for licensing of nuclear installations in South Africa are based on the control of mortality risk to the operators of an installation and the population resident in the vicinity of the site. This paper describes the development of this safety philosophy, and the nuclear licensing process used in this country. The structure of the nuclear regulatory function is briefly described, including the respective roles of the Atomic Energy Corporation, Licencing Branch and the Council for Nuclear Safety. The development of risk criteria and quantitative release magnitude-probability criteria for radioactive material is outlined. Tasks that have to be undertaken by a potential waste disposal site licensee before a site licence is issued are described. Once the facility is commissioned periodic monitoring procedures will have to be adopted throughout the lifetime of the facility. The scope of typical monitoring activities is outlined and the ongoing analyses to be performed and the records to be kept are discussed

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

Integration of MGDS design into the licensing process

International Nuclear Information System (INIS)

1997-12-01

This paper presents an overview of how the Mined Geologic Disposal System (MGDS) design for a potential repository is integrated into the licensing process. The integration process employs a two-told approach: (1) ensure that the MGDS design complies with applicable Nuclear Regulatory Commission (NRC) licensing requirements, and (2) ensure that the MGDS design is appropriately reflected in a license application that is acceptable to the NRC for performing acceptance and compliance reviews

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

NPP long term operation in Spain - First application for license renewal

International Nuclear Information System (INIS)

Francia, L.; Gorrochategui, I.; Marcos, R.

2007-01-01

Full text: In the operation of the Spanish nuclear power plants (NPP), safety is always the prime consideration. Plant Life Management Programmes have been set up with the strategic objective to operate the NPPs as long as they are considered safe and reliable. The safety of each NPP is reviewed by the Spanish nuclear regulatory authority (CSN) under a continuous process. In addition, experience is gained from operating the plants and from exchanges with operators of similar units. Current Spanish regulatory framework for renewing NPP operating licenses requires performing a Periodic Safety Review (PSR) to be performed every 10 years and submitted when applying for a new renewal of the NPP operating license. A few years ago, CSN issued a document regarding the licensing requirements that nuclear power plants should meet in order to be granted with an operating license for long term operation (i.e, operation beyond the original plant design life, typically 40 years). Besides the traditional PSR requirements, specific requirements regarding to long term operation (LTO) include: - An Aging Management and Evaluation Program, including the identification and evaluation of Time Limited Aging Analysis (TLAA). - An updated Radiological Impact Study. - A review and assessment of regulation/standard applicability. Garona NPP (GE, BWR/3 design) operated by Spanish utility Nuclenor from 1971 has a current operating license up to 2009. A decision was made to apply for a new operating license, being Garona plant the first one in Spain to face with the new long term operation requirements. The paper will provide an overview of the methodology used in Spain to address and perform the required analyses to support the LTO application for the operating license renewal. In particular, focus will be paid on the project developed in Garona (2002-2006) whose result has been the first Spanish application for License Renewal for LTO. Also it will be reported the ongoing work necessary to

Operating reactors licensing actions summary. Vol. 3, No. 6

International Nuclear Information System (INIS)

1983-07-01

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. Volume 5, No. 6

International Nuclear Information System (INIS)

1985-08-01

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 Resource Management. This summary report is published for internal NRC use in managing the Operating Reactors Licensing Actions Program. Its content will change based on NRC management informational requirements

Neutral-point current modeling and control for Neutral-Point Clamped three-level converter drive with small DC-link capacitors

DEFF Research Database (Denmark)

Maheshwari, Ram Krishan; Munk-Nielsen, Stig; Busquets-Monge, Sergio

2011-01-01

A Neutral-Point-Clamped (NPC) three-level inverter with small DC-link capacitors is presented in this paper. This inverter requires zero average neutral-point current for stable neutral-point potential. A simple carrier based modulation strategy is proposed for achieving zero average neutral...... drive with only 14 μF DC-link capacitors. A fast and stable performance of the neutral-point voltage controller is achieved and verified by experiments....

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)

Modeling of the lithium based neutralizer for ITER neutral beam injector

Energy Technology Data Exchange (ETDEWEB)

Dure, F., E-mail: franck.dure@u-psud.fr [LPGP, Laboratoire de Physique des Gaz et Plasmas, CNRS-Universite Paris Sud, Orsay (France); Lifschitz, A.; Bretagne, J.; Maynard, G. [LPGP, Laboratoire de Physique des Gaz et Plasmas, CNRS-Universite Paris Sud, Orsay (France); Simonin, A. [IRFM, Institut de Recherche sur la Fusion Magnetique, CEA Cadarache, 13108 Saint-Paul lez Durance (France); Minea, T. [LPGP, Laboratoire de Physique des Gaz et Plasmas, CNRS-Universite Paris Sud, Orsay (France)

2012-04-04

Highlights: Black-Right-Pointing-Pointer We compare different lithium based neutraliser configurations to the deuterium one. Black-Right-Pointing-Pointer We study characteristics of the secondary plasma and the propagation of the 1 MeV beam. Black-Right-Pointing-Pointer Using lithium increases the neutralisation effiency keeping correct beam focusing. Black-Right-Pointing-Pointer Using lithium also reduces the backstreaming effect in direction of the ion source. - Abstract: To achieve thermonuclear temperatures necessary to produce fusion reactions in the ITER Tokamak, additional heating systems are required. One of the main method to heat the plasma ions in ITER will be the injection of energetic neutrals (NBI). In the neutral beam injector, negative ions (D{sup -}) are electrostatically accelerated to 1 MeV, and then stripped of their extra electron via collisions with a target gas, in a structure known as neutralizer. In the current ITER specification, the target gas is deuterium. It has been recently proposed to use lithium vapor instead of deuterium as target gas in the neutralizer. This would allow to reduce the gas load in the NBI vessel and to improve the neutralization efficiency. A Particle-in-Cell Monte Carlo code has been developed to study the transport of the beams and the plasma formation in the neutralizer. A comparison between Li and D{sub 2} based neutralizers made with this code is presented here, as well as a parametric study on the geometry of the Li based neutralizer. Results demonstrate the feasibility of a Li based neutralizer, and its advantages with respect to the deuterium based one.

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

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)

License renewal demonstration program: NRC observations and lessons learned

International Nuclear Information System (INIS)

Prato, R.J.; Kuo, P.T.; Newberry, S.F.

1996-12-01

This report summarizes the Nuclear Regulatory Commission staff's observations and lessons learned from the five License Renewal Demonstration Program (LRDP) site visits performed by the staff from March 25, 1996, through August 16, 1996. The LRDP was a Nuclear Energy Institute (NEI) program intended to assess the effectiveness of the guidance provided by NEI 95-10, Revision 0, open-quotes Industry Guideline for Implementing the Requirements of 10 CFR Part 54 - The License Renewal Rule,close quotes to implement the requirements of Title 10 of the Code of Federal Regulations, Part 54 (10 CFR Part 54), open-quotes Requirements for Renewal of Operating Licenses for Nuclear Power Plants.close quotes In general, NEI 95-10 appeared to contain the basic guidance needed for scoping, screening, identifying aging effects, developing aging management programs, and performing time-limited aging analyses. However, inconsistent implementation of this guidance in some areas was an indication that clarification of existing guidance and/or the inclusion-of some new guidance may be needed for applicants to develop a license renewal program that is consistent with the intent of the rule

To License or Not to License Revisited: An Examination of State Statutes Regarding Private Investigators and Digital Examiners

OpenAIRE

Thomas Lonardo; Doug White; Alan Rea

2009-01-01

In this update to the previous year's study, the authors examine statutes that regulate, license, and enforce investigative functions in each US state. After identification and review of Private Investigator licensing requirements, the authors find that very few state statutes explicitly differentiate between Private Investigators and Digital Examiners. After contacting all state agencies the authors present a distinct grouping organizing state approaches to professional Digital Examiner lice...

Postulated licensing schedule for an independent spent-fuel-storage installation

International Nuclear Information System (INIS)

Ludwick, J.D.

1982-11-01

A review of licensing requirements, processes, and anticipated actions for independent spent fuel storage installations (ISFSIs) was conducted in order to develop an estimated schedule and sequence of events for licensing a new ISFSI. This estimate will be useful to potential ISFSI owners in planning for the licensing of their facilities. It is concluded that, although many uncertainties exist with respect to such things as legal appeals, about 29 months are estimated to elapse between license application and license issuance for an ISFSI. This estimate is in reasonable agreement with a previous time estimate for licensing an ISFSI, and, taking into account the special circumstances involved, with the actual licensing schedule for the GE-Morris ISFSI. However, individual portions of the licensing schedule from each case studied sometimes vary significantly

Licensing process characteristics of Small Modular Reactors and spent nuclear fuel repository

Energy Technology Data Exchange (ETDEWEB)

Söderholm, Kristiina, E-mail: kristiina.soderholm@fortum.com [Fortum Power (Finland); Tuunanen, Jari, E-mail: jari.tuunanen@fortum.com [Fortum Power (Finland); Amaba, Ben, E-mail: baamaba@us.ibm.com [IBM Complex Systems (United States); Bergqvist, Sofia, E-mail: sofia.bergqvist@se.ibm.com [IBM Rational Software (Sweden); Lusardi, Paul, E-mail: plusardi@nuscalepower.com [NuScale Power (United States)

2014-09-15

Highlights: • We examine the licensing process challenges of modular nuclear facilities. • We compare the features of Small Modular Reactors and spent nuclear fuel repository. • We present the need of nuclear licensing simplification. • Part of the licensing is proposed to be internationally applicable. • Systems engineering and requirements engineering benefits are presented. - Abstract: This paper aims to increase the understanding of the licensing processes characteristics of Small Modular Reactors (SMR) compared with licensing of spent nuclear fuel repository. The basis of the SMR licensing process development lies in licensing processes used in Finland, France, the UK, Canada and the USA. These countries have been selected for this study because of their various licensing processes and recent actions in the new NPP construction. Certain aspects of the aviation industry licensing process have also been studied and selected practices have been investigated as possibly suitable for use in nuclear licensing. Suitable features for SMR licensing are emphasized and suggested. The licensing features of the spent nuclear fuel deep repository along with similar features of SMR licensing are discussed. Since there are similar types of challenges of lengthy licensing time frames, as well as modular features to be taken into account in licensing, these two different nuclear industry fields can be compared. The main SMR features to take into account in licensing are: • Standardization of the design. • Modularity. • Mass production. • Serial construction. Modularity can be divided into two different categories: the first category is simply a single power plant unit constructed of independently engineered modules (e.g. construction process for Westinghouse AP-1000 NPP) and the second one a power plant composed of many reactor modules, which are manufactured in factories and installed as needed (e.g. NuScale Power SMR design). The deep underground repository

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

Software licenses: Stay honest!

CERN Multimedia

Computer Security Team

2012-01-01

Do you recall our article about copyright violation in the last issue of the CERN Bulletin, “Music, videos and the risk for CERN”? Now let’s be more precise. “Violating copyright” not only means the illegal download of music and videos, it also applies to software packages and applications.   Users must respect proprietary rights in compliance with the CERN Computing Rules (OC5). Not having legitimately obtained a program or the required licenses to run that software is not a minor offense. It violates CERN rules and puts the Organization at risk! Vendors deserve credit and compensation. Therefore, make sure that you have the right to use their software. In other words, you have bought the software via legitimate channels and use a valid and honestly obtained license. This also applies to “Shareware” and software under open licenses, which might also come with a cost. Usually, only “Freeware” is complete...

Nuclear power plant licensing in Canada

International Nuclear Information System (INIS)

Tong, J.S.C.; Waddington, J.G.

1997-01-01

The Canadian nuclear power plant licensing practice which has evolved over three decades provides a regulatory framework that promotes safe design and operation of CANDU power plants. From the very outset, it recognizes the need for simple and reliable safety systems which are separate from the systems that are normally used to produce electricity. Further, it requires the reliability of safety systems be demonstrated by routine tests during plant operation. Over the three decades, the analysis requirements to demonstrate the performance and reliability of plant systems that have a role in the detection and mitigating of accidents have also evolved. Today's requirements are defined in consultative documents C-6 and C-98. One recurring theme throughout the evolution of the licensing practice is the maxim of prescribing only basic safety requirements and rules so that designers and operators have the freedom to devise the best possible design features and operating practices

75 FR 32983 - Commercial Driver's License (CDL) Standards: Exemption

Science.gov (United States)

2010-06-10

...-28480] Commercial Driver's License (CDL) Standards: Exemption AGENCY: Federal Motor Carrier Safety... commercial driver's license (CDL) as required by current regulations. FMCSA reviewed NAAA's application for... demonstrate alternatives its members would employ to ensure that their commercial motor vehicle (CMV) drivers...

47 CFR 25.113 - Station licenses and launch authority.

Science.gov (United States)

2010-10-01

... 47 Telecommunication 2 2010-10-01 2010-10-01 false Station licenses and launch authority. 25.113 Section 25.113 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) COMMON CARRIER SERVICES SATELLITE COMMUNICATIONS Applications and Licenses General Application Filing Requirements § 25.113 Station...

TFTR neutral beam injection system conceptual design

International Nuclear Information System (INIS)

1975-01-01

Three subsystems are described in the following chapters: (1) Neutral Beam Injection Line; (2) Power Supplies; and (3) Controls. Each chapter contains two sections: (1) Functions and Design Requirements; this is a brief listing of the requirements of components of the subsystem. (2) Design Description; this section describes the design and cost estimates. The overall performance requirements of the neutral beam injection system are summarized. (MOW)

10 CFR 40.34 - Special requirements for issuance of specific licenses.

Science.gov (United States)

2010-01-01

... license to manufacture industrial products and devices containing depleted uranium, or to initially....32; (2) The applicant submits sufficient information relating to the design, manufacture, prototype... industrial product or device to provide reasonable assurance that possession, use, or transfer of the...

The role the safety analysis report and other documents in the licensing procedure in the Federal Republic of Germany

International Nuclear Information System (INIS)

Albrecht, E.; Ballhaus, S.

1975-01-01

Legal requirements for the licensing procedure, requirements for and preparation of licensing documents, authorities and experts participating in the licensing procedure, course of the atomic licensing procedure e.g. application for construction and operation, public hearing, site and concept license, partial licenses. (HP) [de

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

Nuclear licensing and supervision in Germany

International Nuclear Information System (INIS)

1996-06-01

The legal instrument for implementing the licensing and supervisory procedure is specified by statutory ordinances, guidelines and provisions. The licensing requirements for nuclear power plants on the final storage of radioactive wastes in the federal republic of germany are described. The nuclear facilities are subject to continuous state supervision after they have been granted. The appendix gives a brief account of the most important ordinances relating to the AtG and extracts from the Nuclear Safety Convention. (HP)

Licensing of the proposed PBMR-SA

International Nuclear Information System (INIS)

Clapisson, G.A.; Henderson, N.R.; Hill, T.F.; Keenan, N.H.; Metcalf, P.E.; Mysenkov, A.

1997-01-01

This paper describes the preliminary criteria, which are intended to be used by the South African regulatory authority (CNS), for licensing of the ESKOM proposed - South African high temperature gas-cooled Pebble Bed Modular Reactor (PBMR-SA). The CNS intends to apply the existing CNS licensing approach together with some international design criteria used for advanced reactors as well as international experience gained from the safety evaluation of the MHTGR, THTR, etc. A major requirement to this type of reactor is that it should comply with the current CNS risk criteria and provide, as a minimum, the same degree of protection to the operator, public and environment that is required for the current generation of nuclear reactors. (author)

The Atomic Energy Control Board requirements for the radioisotope licensing of a radiopharmaceutical facility

International Nuclear Information System (INIS)

Kennedy, P.

1980-01-01

Items that must be addressed by an applicant for a radioisotope license in Canada are described. Site, design and operating conditions, safety assessment, organization, emergency procedures and operating policies and procedures must be described to the Atomic Energy Control Board (AECB), in support of any license application. All information submitted in support of the application is subject to AECB's policy on public access to that information. (OT)

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

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

Two Approaches to Reactor Decommissioning: 10 CFR Part 50 License Termination and License Amendment, Lessons Learned from the Regulatory Perspective

International Nuclear Information System (INIS)

Watson, B.A.; Buckley, J.T.; Craig, C.M.

2006-01-01

Trojan Nuclear Plant (Trojan) and Maine Yankee Nuclear Plant (Maine Yankee) were the first two power reactors to complete decommissioning under the U. S. Nuclear Regulatory Commission's (NRC's) License Termination Rule (LTR), 10 CFR Part 20, Subpart E. The respective owners' decisions to decommission the sites resulted in different approaches to both the physical aspects of the decommissioning, and the approach for obtaining approval for completing the decommissioning in accordance with regulations. Being in different States, the two single-unit pressurized water reactor sites had different State requirements and levels of public interest that impacted the decommissioning approaches. This resulted in significant differences in decommissioning planning, conduct of decommissioning operations, volumes of low- level radioactive waste disposed, and the final status survey (FSS) program. While both licensees have Independent Spent Fuel Storage Installations (ISFSIs), Trojan obtained a separate license for the ISFSI in accordance with the requirements of 10 CFR Part 72 and terminated their 10 CFR Part 50 license. Maine Yankee elected to obtain a general license under 10 CFR Part 50 for the ISFSI and reduce the physical site footprint to the ISFSI through a series of license amendments. While the NRC regulations are flexible and allow different approaches to ISFSI licensing there are separate licensing requirements that must be addressed. In 10 CFR 50.82, the NRC mandates public participation in the decommissioning process. For Maine Yankee, public input resulted in the licensee entering into an agreement with a concerned citizen group and resulted in State legislation that significantly lowered the dose limit below the NRC radiological criteria of 25 mrem (0.25 mSv) per year (yr) in 10 CFR 20.1402 for unrestricted use. The lowering of the radiological criteria resulted in a significant dose modeling effort using site-specific Derived Concentrations Guideline Levels (DCGLs

Licensing of simple digital devices

International Nuclear Information System (INIS)

Jackson, T. W.

2008-01-01

The inability to guarantee error-free software gave rise to the potential for common-cause failure of digital safety systems in nuclear power plants. To address this vulnerability, the U. S. Nuclear Regulatory Commission (NRC) required a quality software development process and a defense-in-depth and diversity analysis for digital safety systems. As a result of recent interim [NRC] staff guidance in the digital instrumentation and control (I and C) area, licensing of simple digital devices decreases some regulatory burden with respect to demonstrating a quality software development process and defense-in-depth and diversity analysis. This paper defines simple digital devices and addresses the interim staff guidance that applies to such devices. The paper also highlights the technical aspects that affect the licensing of such devices and incorporates licensing experience in the U.S. to date. (authors)

ITER Neutral Beam Injection System

International Nuclear Information System (INIS)

Ohara, Yoshihiro; Tanaka, Shigeru; Akiba, Masato

1991-03-01

A Japanese design proposal of the ITER Neutral Beam Injection System (NBS) which is consistent with the ITER common design requirements is described. The injection system is required to deliver a neutral deuterium beam of 75MW at 1.3MeV to the reactor plasma and utilized not only for plasma heating but also for current drive and current profile control. The injection system is composed of 9 modules, each of which is designed so as to inject a 1.3MeV, 10MW neutral beam. The most important point in the design is that the injection system is based on the utilization of a cesium-seeded volume negative ion source which can produce an intense negative ion beam with high current density at a low source operating pressure. The design value of the source is based on the experimental values achieved at JAERI. The utilization of the cesium-seeded volume source is essential to the design of an efficient and compact neutral beam injection system which satisfies the ITER common design requirements. The critical components to realize this design are the 1.3MeV, 17A electrostatic accelerator and the high voltage DC acceleration power supply, whose performances must be demonstrated prior to the construction of ITER NBI system. (author)

The U.S. Nuclear Regulatory Commission's antitrust review of nuclear power plants: the conditioning of licenses

International Nuclear Information System (INIS)

Penn, D.W.; Delaney, J.B.; Honeycutt, T.C.

1976-04-01

The 1970 amendments to Section 105 of the Atomic Energy Act require the Nuclear Regulatory Commission to conduct a prelicensing antitrust review of applications for licenses to construct and operate nuclear power plants. The Commission must make a finding as to whether the granting of a license 'would create or maintain a situation inconsistent with the antitrust laws,' and it has the authority to issue or continue a license, to refuse to issue a license, to rescind or amend a license, and to issue a license with conditions that it deems appropriate. This report provides information about the antitrust license conditions that have resulted from the NRC's antitrust review process. The process itself is described and a catalog of the applications requiring antitrust license conditions is presented. For each application, the license conditions are put into the general categories of unit access, transmission services, coordination, and contractual provisions. For completeness, the report also catalogs applications requiring no antitrust license conditions, and lists applications that were exempted from the 1970 amendments, are the subject of litigation, or have been withdrawn

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

49 CFR 385.605 - New entrant registration driver's license and drug and alcohol testing requirements.

Science.gov (United States)

2010-10-01

... America-Domiciled Carriers § 385.605 New entrant registration driver's license and drug and alcohol... carrier must subject each of the drivers described in paragraph (a) of this section to drug and alcohol... 49 Transportation 5 2010-10-01 2010-10-01 false New entrant registration driver's license and drug...

Effective Continuing Education for Licensed Real Estate Professionals

Science.gov (United States)

Tilton, Wendy A.

2004-01-01

Mandatory real estate education has been intensely debated for many years. New Jersey is the only state in the nation that does not require licensed real estate agents to attend an ongoing educational event after securing a license to practice. A bill was proposed to the legislature to mandate real estate education in June of 2001. (It was…

Electrical design requirements for electrode boilers for nuclear plants

International Nuclear Information System (INIS)

Kempker, M.J.

1979-01-01

Medium-voltage steam electrode boilers, in the 20- to 50-MW range, have become an attractive alternative to comparable fossil-fueled boilers as a source of auxiliary steam during the startup and normal shutdown of nuclear power plants. The electrode boiler represents a favorable option because of environmental, fire protection, and licensing considerations. However, this electrical option brings some difficult design problems for which solutions are required in order to integrate the electrode boiler into the plant low resistance grounded power system. These considerations include the effects of an unbalanced electrode boiler on the performance of polyphase induction motors, boiler grounding for personnel safety, boiler neutral grounding, and ground relaying

Licensing schedule for away-from-reactor (AFR) spent fuel storage facilities

International Nuclear Information System (INIS)

Gray, P.L.

1981-08-01

The Nuclear Regulatory Commission has authority to issue licenses for Away-From-Reactor (AFR) installations for the storage of spent nuclear fuel. This report presents a detailed estimate of the time required to prosecute a licensing action. 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

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

Dry spent fuel storage licensing

International Nuclear Information System (INIS)

Sturz, F.C.

1995-01-01

In the US, at-reactor-site dry spent fuel storage in independent spent fuel storage installations (ISFSI) has become the principal option for utilities needing storage capacity outside of the reactor spent fuel pools. Delays in the geologic repository operational date at or beyond 2010, and the increasing uncertainty of the US Department of Energy's (DOE) being able to site and license a Monitored Retrievable Storage (MRS) facility by 1998 make at-reactor-site dry storage of spent nuclear fuel increasingly desirable to utilities and DOE to meet the need for additional spent fuel storage capacity until disposal, in a repository, is available. The past year has been another busy year for dry spent fuel storage licensing. The licensing staff has been reviewing 7 applications and 12 amendment requests, as well as participating in inspection-related activities. The authors have licensed, on a site-specific basis, a variety of dry technologies (cask, module, and vault). By using certified designs, site-specific licensing is no longer required. Another new cask has been certified. They have received one new application for cask certification and two amendments to a certified cask design. As they stand on the brink of receiving multiple applications from DOE for the MPC, they are preparing to meet the needs of this national program. With the range of technical and licensing options available to utilities, the authors believe that utilities can meet their need for additional spent fuel storage capacity for essentially all reactor sites through the next decade

Managing the high level waste nuclear regulatory commission licensing process

International Nuclear Information System (INIS)

Baskin, K.P.

1992-01-01

This paper reports that the process for obtaining Nuclear Regulatory Commission permits for the high level waste storage facility is basically the same process commercial nuclear power plants followed to obtain construction permits and operating licenses for their facilities. Therefore, the experience from licensing commercial reactors can be applied to the high level waste facility. Proper management of the licensing process will be the key to the successful project. The management of the licensing process was categorized into four areas as follows: responsibility, organization, communication and documentation. Drawing on experience from nuclear power plant licensing and basic management principles, the management requirement for successfully accomplishing the project goals are discussed

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

ISO 14000 and the nuclear licensing

International Nuclear Information System (INIS)

Martins, Nadia Soido Falcao

1999-01-01

As concern grows for maintaining and improving the quality of the environment and protecting human health, all the world is turning its attention to the potential environmental in pact of their industrial activities. One of the most important contribution in that way is the International Standard ISO 14000 series. In the utilization of nuclear energy, right from the inception, the safety of personnel, environment and the population has been the basic consideration. Over the years well established licenses criteria have been proposed to limit and control the environmental impact of the plant operation and emergencies situation. In this paper are discussed some specific requirements for implementation of the environmental management system specified by ISO 14000 compared to the environmental requirements for nuclear licensing. (author)

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,

Neutrality in mediation: an ambiguous ethical value

OpenAIRE

Bailey, Paul

2014-01-01

Mediator neutrality would appear, by definition, to be a necessary and required ethical principle for all mediators to practice. But what is meant by neutrality in mediation? Is it practically possible to be completely neutral between parties in mediation while at the same time being fair to both of them? This paper attempts to answer these two questions.

The strategy of experimental power reactor licensing in Indonesia

International Nuclear Information System (INIS)

Moch Djoko Birmano

2015-01-01

Currently, BATAN has being planned to develop Experimental Power Reactor (EPR), that is the research nuclear reactor that can generate power (electricity or heat). The EPR is planned will be built in the National Center for Research of Science and Technology (Puspiptek) area at Serpong, South Tangerang, Banten Province, with the choice of reactor types is HTGR with the power size of 10 MWth. As stated in the Act No. 10 year 1997 on Nuclear Power, that every construction and operation of nuclear reactors and other nuclear installations and decommissioning of nuclear reactors required to have a permit. Furthermore, the its implementation arrangements is regulated in Government Regulation (GR) No. 2 year 2014 on Licensing of Nuclear Installations and Nuclear Material Utilization, which contains the requirements and procedures for the licensing process since site, construction, commissioning, operation, and decommissioning, it means licensing is implemented during the activity of construction, operation and decommissioning of NPPs.While, for the more detailed licensing arrangements available in the guidelines of BAPETEN Chairman Regulation (BCR). This study was conducted to understand the legal and institutional aspects, types and stages, and the licensing process of RDE, and identify licensing strategy so that timely as planned. Methodologies used include the literature study, consultation with experts in BAPETEN, discussions in the national seminar including FGD. (author)

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...

Neutral-beam-heating applications and development

International Nuclear Information System (INIS)

Menon, M.M.

1981-01-01

The technique of heating the plasma in magnetically confined fusion devices by the injection of intense beams of neutral atoms is described. The basic principles governing the physics of neutral beam heating and considerations involved in determining the injection energy, power, and pulse length required for a fusion reactor are discussed. The pertinent experimental results from various fusion devices are surveyed to illustrate the efficacy of this technique. The second part of the paper is devoted to the technology of producing the neutral beams. A state-of-the-art account o the development of neutral injectors is presented, and the prospects for utilizing neutral injection to heat the plasma in a fusion reactor are examined

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

23 CFR 635.110 - Licensing and qualification of contractors.

Science.gov (United States)

2010-04-01

... licensing contractors, who may bid for, be awarded, or perform Federal-aid highway contracts, shall be... competition, to prevent submission of a bid by, or to prohibit the consideration of a bid submitted by, any...) No contractor shall be required by law, regulation, or practice to obtain a license before submission...

Licensing the First Nuclear Power Plant. INSAG-26. A report by the International Nuclear Safety Group

International Nuclear Information System (INIS)

2012-01-01

nuclear power plant that is already licensed by an experienced regulator. Consequently, an option is to start development of national regulations by adopting or adapting regulations from a country that has licensed the same type of nuclear power plant. However, if the intention is to have an open technology selection process, care should be taken to establish a set of technology neutral regulations, such as by using the IAEA safety standards as the foundation. This set of technology neutral regulations can then be complemented by more design specific regulations after the technology is chosen. Since the development of technical competences requires considerable time, the regulatory body needs to plan for human resources development at a very early stage. As a first step, the essential competences required for the different phases of the nuclear power programme should be identified. Thereafter, formal training arrangements should be established between the regulatory body and one or more experienced regulators that have licensed a similar facility. This should include early interaction between senior managers of the two regulators followed by detailed training of selected staff who will form the technical core of the regulatory body. The regulatory body should also identify outside organizations that will act as its technical support organizations (TSOs) and should provide for conduct of nuclear safety R and D by these TSOs, including the appropriate research facilities and expertise. If additional nuclear power plants will be constructed in the new entrant country in the future, the new nuclear power plant units may not be of the same design as the first plant. This aspect should be kept in mind when developing both the licensing methodologies and staff. Regulatory staff can also obtain significant benefit from participation in international cooperation activities such as the Convention on Nuclear Safety, technical cooperation forums of regulatory bodies of countries

Net Neutrality and Inflation of Traffic

NARCIS (Netherlands)

Peitz, M.; Schütt, F.

2015-01-01

Under strict net neutrality Internet service providers (ISPs) are required to carry data without any differentiation and at no cost to the content provider. We provide a simple framework with a monopoly ISP to evaluate different net neutrality rules. Content differs in its sensitivity to delay.

Testing, licensing, and code requirements for seismic isolation systems (for nuclear power plants)

International Nuclear Information System (INIS)

Seidensticker, R.W.

1987-01-01

The use of seismic isolation as an earthquake hazard mitigation strategy for nuclear reactor power plants is rapidly receiving interest throughout the world. Seismic isolation has already been used on at least two French PWR plants, was to have been used for plants to be built in Iran, and is under serious consideration for advanced LMR plants (in the US, UK, France, and Japan). In addition, there is a growing use of seismic isolation throughout the world for other critical facilities such as hospitals, emergency facilities, buildings with very high-cost equipment (e.g., computers) and as a strategy to reduce loss of life and expensive equipment in earthquakes. Such a design approach is in complete contrast to the conventional seismic design strategy in which the structure and components are provided with sufficient strength and ductility to resist the earthquake forces and to prevent structural collapses or failure. The use of seismic isolation for nuclear plants can, therefore, be expected to be a significant licensing issue. For isolation, the licensing process must shift away in large measure from the superstructure and concentrate on the behavior of the seismic isolation system. This paper is not intended to promote the advantages of seismic isolation system, but to explore in some detail those technical issues which must be satisfactorily addressed to achieve full licensability of the use of seismic isolation as a viable, attractive and economical alternative to current traditional design approaches. Special problems and topics associated with testing and codes and standards development are addressed. A positive program for approach or strategy to secure licensing is presented

Testing, licensing, and code requirements for seismic isolation systems (for nuclear power plants)

Energy Technology Data Exchange (ETDEWEB)

Seidensticker, R.W.

1987-01-01

The use of seismic isolation as an earthquake hazard mitigation strategy for nuclear reactor power plants is rapidly receiving interest throughout the world. Seismic isolation has already been used on at least two French PWR plants, was to have been used for plants to be built in Iran, and is under serious consideration for advanced LMR plants (in the US, UK, France, and Japan). In addition, there is a growing use of seismic isolation throughout the world for other critical facilities such as hospitals, emergency facilities, buildings with very high-cost equipment (e.g., computers) and as a strategy to reduce loss of life and expensive equipment in earthquakes. Such a design approach is in complete contrast to the conventional seismic design strategy in which the structure and components are provided with sufficient strength and ductility to resist the earthquake forces and to prevent structural collapses or failure. The use of seismic isolation for nuclear plants can, therefore, be expected to be a significant licensing issue. For isolation, the licensing process must shift away in large measure from the superstructure and concentrate on the behavior of the seismic isolation system. This paper is not intended to promote the advantages of seismic isolation system, but to explore in some detail those technical issues which must be satisfactorily addressed to achieve full licensability of the use of seismic isolation as a viable, attractive and economical alternative to current traditional design approaches. Special problems and topics associated with testing and codes and standards development are addressed. A positive program for approach or strategy to secure licensing is presented.

The Licensing of New Nuclear Power Plants in Europe

International Nuclear Information System (INIS)

Raetzke, C.

2008-01-01

After an introduction dealing with the nuclear Renaissance in Europe and the specific situation of Germany and of Italy, the article focuses on the question of licensing processes for new reactors. New nuclear power plant projects involve a substantial investment and electric utilities will only take this decision if the licensing and regulatory risk can be adequately managed. Licensing processes should be predictable and efficient in order to give sufficient assurance to applicants. The article discusses best practice in licensing by giving some examples of suitable licensing processes of other countries. It also highlights international initiatives aimed at harmonizing safety requirements for new reactors and a multinational cooperation in reactor design review. These issues should be carefully considered by any country wanting to get new nuclear started. [it

Cytomegalovirus neutralization by hyperimmune and standard intravenous immunoglobulin preparations.

Science.gov (United States)

Planitzer, Christina B; Saemann, Marcus D; Gajek, Hartwig; Farcet, Maria R; Kreil, Thomas R

2011-08-15

Cytomegalovirus (CMV) remains one of the most important pathogens after transplantation, potentially leading to CMV disease, allograft dysfunction, acute, and chronic rejection and opportunistic infections. Immunoglobulin G (IgG) preparations with high antibody titers against CMV are a valuable adjunctive prevention and treatment option for clinicians and apart from standard intravenous immunoglobulin (IVIG), CMV hyperimmune preparations are available. The CMV antibody titer of these preparations is typically determined by Enzyme-linked immunosorbent assay (ELISA), also used for the selection of high titer plasma donors for the production of the CMV Hyperimmune product. However, CMV ELISA titers do not necessarily correlate with CMV antibody function which is determined by virus neutralization tests. CMV antibody titers were determined by both ELISA and virus neutralization assay and the IgG subclass distribution was compared between a CMV hyperimmune licensed in Europe and standard IVIG preparations. Although the expected high CMV IgG ELISA antibody titers were confirmed for three lots of a CMV hyperimmune preparation, the functionally more relevant CMV neutralizing antibody titers were significantly higher for 31 lots of standard IVIG preparations. Moreover, considerably lower IgG3 levels were found for the CMV hyperimmune preparation compared with standard IVIG preparations. The higher functional CMV neutralization titers of standard IVIG preparations and the better availability of these preparations, suggest that these products could be a valuable alternative to the CMV hyperimmune preparation.

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

Lifescience Database Archive (English)

Full Text Available List Contact us RGP gmap98 License License to Use This Database Last updated : 2015/02/12 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 2.1 Japan . If you use data from this database, please be sure attribute this database as foll...on-Share Alike 2.1 Japan is found here . With regard to this database, you are licensed to: freely access part or whole of this datab

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

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)

ISO and software quality assurance - licensing and certification of software professionals

Energy Technology Data Exchange (ETDEWEB)

Hare, J.; Rodin, L.

1997-11-01

This report contains viewgraphs on licensing and certifing of software professionals. Discussed in this report are: certification programs; licensing programs; why became certified; certification as a condition of empolyment; certification requirements; and examination structures.

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

Licensing procedures for Low-Level Waste disposal facilities

International Nuclear Information System (INIS)

Roop, R.D.; Van Dyke, J.W.

1985-09-01

This report describes the procedures applicable to siting and licensing of disposal facilities for low-level radioactive wastes. Primary emphasis is placed on those procedures which are required by regulations, but to the extent possible, non-mandatory activities which will facilitate siting and licensing are also considered. The report provides an overview of how the procedural and technical requirements for a low-level waste (LLW) disposal facility (as defined by the Nuclear Regulatory Commission's Rules 10 CFR Parts 2, 51, and 61) may be integrated with activities to reduce and resolve conflict generated by the proposed siting of a facility. General procedures are described for site screening and selection, site characterization, site evaluation, and preparation of the license application; specific procedures for several individual states are discussed. The report also examines the steps involved in the formal licensing process, including docketing and initial processing, preparation of an environmental impact statement, technical review, hearings, and decisions. It is concluded that development of effective communication between parties in conflict and the utilization of techniques to manage and resolve conflicts represent perhaps the most significant challenge for the people involved in LLW disposal in the next decade. 18 refs., 6 figs

Environmental licensing issues for cogeneration plants

International Nuclear Information System (INIS)

Lipka, G.S.; Bibbo, R.V.

1990-01-01

The siting and licensing of cogeneration and independent power production (IPP) facilities is a complex process involving a number of interrelated engineering, economic, and environmental impact considerations. Important considerations for the siting and licensing of such facilities include air quality control and air quality impacts, water supply and wastewater disposal, and applicable noise criteria and noise impact considerations. Air quality control and air quality impact considerations for power generation facilities are commonly reviewed in the public forum, and most project developers are generally aware of the key air quality licensing issues. These issues include Best Available Control Technology (BACT) demonstration requirements, and air quality modeling requirements. BACT is a case-by-case determination, which causes uncertainty, in that developers have difficulty in projecting the cost of required control systems. Continuing developments in control technology may cause this problem to continue in the 1990's. Air quality modeling can be a problem in hilly terrain or within or near an urban environment, which could delay or preclude permitting of a new cogeneration or IPP facility in such locations. This paper discusses several environmental issues which are less frequently addressed than air quality issues, namely water/wastewater and noise. The design features of typical cogeneration and IPP facilities that affect water supply requirements, wastewater volumes, and noise emissions are discussed. Then, the site selection and impact review process are examined to identify typical constraints and trade-offs that can develop relative to water, wastewater, and noise issues. Trends in permit review requirements for water, wastewater, and noise are examined. Finally, innovative approaches that can be used to resolve potential development constraints for water, wastewater, and noise issues are discussed

Net neutrality and inflation of traffic

NARCIS (Netherlands)

Peitz, M.; Schütt, Florian

Under strict net neutrality Internet service providers (ISPs) are required to carry data without any differentiation and at no cost to the content provider. We provide a simple framework with a monopoly ISP to evaluate the short-run effects of different net neutrality rules. Content differs in its

19 CFR 147.24 - Merchandise subject to licensing.

Science.gov (United States)

2010-04-01

... the U.S. Government, may be entered for a fair only upon the presentation of the required license, or... OF THE TREASURY (CONTINUED) TRADE FAIRS Requirements of Other Laws § 147.24 Merchandise subject to...

ALCBEAM - Neutral beam formation and propagation code for beam-based plasma diagnostics

Science.gov (United States)

Bespamyatnov, I. O.; Rowan, W. L.; Liao, K. T.

2012-03-01

ALCBEAM is a new three-dimensional neutral beam formation and propagation code. It was developed to support the beam-based diagnostics installed on the Alcator C-Mod tokamak. The purpose of the code is to provide reliable estimates of the local beam equilibrium parameters: such as beam energy fractions, density profiles and excitation populations. The code effectively unifies the ion beam formation, extraction and neutralization processes with beam attenuation and excitation in plasma and neutral gas and beam stopping by the beam apertures. This paper describes the physical processes interpreted and utilized by the code, along with exploited computational methods. The description is concluded by an example simulation of beam penetration into plasma of Alcator C-Mod. The code is successfully being used in Alcator C-Mod tokamak and expected to be valuable in the support of beam-based diagnostics in most other tokamak environments. Program summaryProgram title: ALCBEAM Catalogue identifier: AEKU_v1_0 Program summary URL:http://cpc.cs.qub.ac.uk/summaries/AEKU_v1_0.html Program obtainable from: CPC Program Library, Queen's University, Belfast, N. Ireland Licensing provisions: Standard CPC licence, http://cpc.cs.qub.ac.uk/licence/licence.html No. of lines in distributed program, including test data, etc.: 66 459 No. of bytes in distributed program, including test data, etc.: 7 841 051 Distribution format: tar.gz Programming language: IDL Computer: Workstation, PC Operating system: Linux RAM: 1 GB Classification: 19.2 Nature of problem: Neutral beams are commonly used to heat and/or diagnose high-temperature magnetically-confined laboratory plasmas. An accurate neutral beam characterization is required for beam-based measurements of plasma properties. Beam parameters such as density distribution, energy composition, and atomic excited populations of the beam atoms need to be known. Solution method: A neutral beam is initially formed as an ion beam which is extracted from

Coupled plasma-neutral transport model for the scrape-off region

International Nuclear Information System (INIS)

Galambos, J.D.; Peng, Y.K.M.; Heifetz, D.

1985-03-01

Analysis of the scrape-off region requires treatment of the plasma transport along and across the field lines and inclusion of the neutral transport effects. A method for modeling the scrape-off region that is presented here uses separate models for each of these aspects that are coupled together through an iteration procedure that requires only minimal numerical effort. The method is applied here to estimate the neutral pumping rates in the pump-limiter and divertor options for a proposed deuterium-tritium (D-T) ignition experiment. High neutral recycling in the vicinity of the neutralizer plate dramatically affects pumping rates for both the pump-limiter and divertor. In both cases, the plasma flow into the channel surrounding the neutralizer plate is greatly reduced by the neutral recycling. The fraction of this flow that is pumped can be large (> 50%), but in general it is dependent on the particular geometry and plasma conditions. It is estimated that pumping speeds approximately greater than 10 5 L/s are adequate for the exhaust requirements in the pump-limiter and the divertor cases. Also, high neutral recycling on the front surface of the limiter tends to increase the neutral pumping rate

Presentation of reports for licensing of industrial irradiators

International Nuclear Information System (INIS)

2000-04-01

This Regulation refers to the requirements of the Regulation CNEN-NE.6.02. 'Licensing of Radioactive Facilities', expressed in the section 6 related to the information for Previous Approval, in the subsection 7.2 related to the information for the Construction Licensing and in the subsection 9.2, related to the information for the Authorization for operation, for the specific case of industrial irradiators

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.

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Reassessing Occupational Licensing Of Tour Guides (Opinion Piece

Directory of Open Access Journals (Sweden)

Amir SHANI

2017-06-01

Full Text Available It is conventionally held that to protect tourists from incompetent and/or unscrupulous tour guides, governments should require guides to be licensed in order to legally practice their profession. Despite the implementation of such regulatory statutes in many countries, it is argued in this opinion paper that the severe drawbacks of licensing demands should be re-evaluated by both policy-makers and tourism scholars. The licensing of guides is not only an ineffective means of quality assurance, with negative consequences for many of those involved, but it also undermines the ethical foundations of a free society. Furthermore, licensing is an archaic practice for ensuring standardization among the members of a profession in a way that is no longer suitable for addressing the challenges of the tourism industry in the 21st century, in which a wide variety of specialized and innovative guided tours are offered to tourists. Although this commentary presents a firm stand against the compulsory licensing of tour guides, it should be seen as an invitation for open discussion among tourism researchers regarding the necessity of licensing tour guides in particular, and of government tourism regulation in general. Moreover, further research is needed to clarify key points on the issue of the professional licensing of tour guides.

License plate recognition using DTCNNs

NARCIS (Netherlands)

ter Brugge, M.H; Stevens, J.H; Nijhuis, J.A G; Spaanenburg, L; Tavsanonoglu, V

1998-01-01

Automatic license plate recognition requires a series of complex image processing steps. For practical use, the amount of data to he processed must be minimized early on. This paper shows that the computationally most intensive steps can be realized by DTCNNs. Moreover; high-level operations like

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.

Gas cell neutralizers (Fundamental principles)

International Nuclear Information System (INIS)

Fuehrer, B.

1985-06-01

Neutralizing an ion-beam of the size and energy levels involved in the neutral-particle-beam program represents a considerable extension of the state-of-the-art of neutralizer technology. Many different mediums (e.g., solid, liquid, gas, plasma, photons) can be used to strip the hydrogen ion of its extra electron. A large, multidisciplinary R and D effort will no doubt be required to sort out all of the ''pros and cons'' of these various techniques. The purpose of this particular presentation is to discuss some basic configurations and fundamental principles of the gas type of neutralizer cell. Particular emphasis is placed on the ''Gasdynamic Free-Jet'' neutralizer since this configuration has the potential of being much shorter than other type of gas cells (in the beam direction) and it could operate in nearly a continuous mode (CW) if necessary. These were important considerations in the ATSU design which is discussed in some detail in the second presentation entitled ''ATSU Point Design''

License - MicrobeDB.jp | 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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77 FR 73684 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

Science.gov (United States)

2012-12-11

... in accordance with the Commission's ``Rules of Practice for Domestic Licensing Proceedings'' in 10... emergency diesel generator, and the stored lube oil inventory will also continue to require that a 7-day supply be available for each diesel generator. The changes are consistent with NRC-approved Technical...

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

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

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Atomic Safety and Licensing Board Panel annual report, fiscal year 1989

International Nuclear Information System (INIS)

Cotter, B.P. Jr.

1990-07-01

In Fiscal Year 1989, the Atomic Safety and Licensing Board Panel (ASLBP) handled 40 proceedings involving the construction, operation and maintenance of commercial nuclear power reactors or other activities requiring a license from the Nuclear Regulatory Commission. This report summarizes, highlights and analyzes how the wide-ranging issues raised in these proceedings were addressed by the Judges and Licensing Boards of the ASLBP during the year. 5 figs., 3 tabs

Benchmark for license plate character segmentation

Science.gov (United States)

Gonçalves, Gabriel Resende; da Silva, Sirlene Pio Gomes; Menotti, David; Shwartz, William Robson

2016-09-01

Automatic license plate recognition (ALPR) has been the focus of many researches in the past years. In general, ALPR is divided into the following problems: detection of on-track vehicles, license plate detection, segmentation of license plate characters, and optical character recognition (OCR). Even though commercial solutions are available for controlled acquisition conditions, e.g., the entrance of a parking lot, ALPR is still an open problem when dealing with data acquired from uncontrolled environments, such as roads and highways when relying only on imaging sensors. Due to the multiple orientations and scales of the license plates captured by the camera, a very challenging task of the ALPR is the license plate character segmentation (LPCS) step, because its effectiveness is required to be (near) optimal to achieve a high recognition rate by the OCR. To tackle the LPCS problem, this work proposes a benchmark composed of a dataset designed to focus specifically on the character segmentation step of the ALPR within an evaluation protocol. Furthermore, we propose the Jaccard-centroid coefficient, an evaluation measure more suitable than the Jaccard coefficient regarding the location of the bounding box within the ground-truth annotation. The dataset is composed of 2000 Brazilian license plates consisting of 14000 alphanumeric symbols and their corresponding bounding box annotations. We also present a straightforward approach to perform LPCS efficiently. Finally, we provide an experimental evaluation for the dataset based on five LPCS approaches and demonstrate the importance of character segmentation for achieving an accurate OCR.

Methodology and findings of the NRC's materials licensing process redesign

International Nuclear Information System (INIS)

Rathbun, P.A.; Brown, K.D.; Madera, J.R.; Moriarty, M.; Pelchat, J.M.; Usilton, W.K.; Whitten, J.E.; Vacca, P.C.

1996-04-01

This report describes the work and vision of the team chartered to redesign the process for licensing users of nuclear materials. The Business Process Redesign team was chartered to improve the speed of the existing licensing process while maintaining or improving public safety and to achieve required resource levels. The report describes the team's methods for acquiring and analyzing information about the existing materials licensing process and the steps necessary to radically change this process to the envisioned future process

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

Lifescience Database Archive (English)

Full Text Available List Contact us BodyParts3D License License to Use This Database Last updated : 2011/08/25 You may use this database...he 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 Attributi...on-Share Alike 2.1 Japan. If you use data from this database, please be sure attribute this database as foll...here . With regard to this database, you are licensed to: freely access part or whole of this database, and

Licensing procedures for Low-Level Waste disposal facilities

Energy Technology Data Exchange (ETDEWEB)

Roop, R.D.; Van Dyke, J.W.

1985-09-01

This report describes the procedures applicable to siting and licensing of disposal facilities for low-level radioactive wastes. Primary emphasis is placed on those procedures which are required by regulations, but to the extent possible, non-mandatory activities which will facilitate siting and licensing are also considered. The report provides an overview of how the procedural and technical requirements for a low-level waste (LLW) disposal facility (as defined by the Nuclear Regulatory Commission's Rules 10 CFR Parts 2, 51, and 61) may be integrated with activities to reduce and resolve conflict generated by the proposed siting of a facility. General procedures are described for site screening and selection, site characterization, site evaluation, and preparation of the license application; specific procedures for several individual states are discussed. The report also examines the steps involved in the formal licensing process, including docketing and initial processing, preparation of an environmental impact statement, technical review, hearings, and decisions. It is concluded that development of effective communication between parties in conflict and the utilization of techniques to manage and resolve conflicts represent perhaps the most significant challenge for the people involved in LLW disposal in the next decade. 18 refs., 6 figs.

The comparison of license management procedure for nuclear power plant in China and United States

International Nuclear Information System (INIS)

Yu Zusheng

2006-01-01

'Tow steps' license management procedure for nuclear power plant has been performed bas- ted on the requirement of 10CFR Part50-DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES in United States since last century fifties. In order to ulterior reduce the risk of investment and technical for new construction nuclear power plants, new regulations 'One step' license management procedure-10CFR Part52-EARLY SITE PERMITS; STANDARD DESIGN CERTIFICATIONS; AND COMBINED LICENSES FOR NUCLEAR POWER PLANTS issued in 1989. The new regulations has been adopted by new design of nuclear power plant, for example AP1000. ‘The similar tow steps’ license management procedure for nuclear power plant has been performed basted on the requirement of HAFO01/01 Rules for the Implementation of Regulations on the Safety Regulation for Civilian Nuclear Installations of the People's Re- public of China Part One: Application and Issuance of Safety License for Nuclear Power Plant (December 1993) in China since last century nineties. This article introduces and compares the requirements and characteristics of above license management procedure for nuclear power plant in China and United States. (author)

77 FR 70837 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

Science.gov (United States)

2012-11-27

... intervene shall be filed in accordance with the Commission's ``Rules of Practice for Domestic Licensing... request: The proposed change will delete Function 14, SG [Steam Generator] Water Level--Low, Coincident... capability to shut down the reactor when required on Low--Low Steam Generator water level. The ability to...

77 FR 67679 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

Science.gov (United States)

2012-11-13

... diesel generator surveillance requirements. Margin of safety is related to the ability of the fission... evaluated; or (3) involve a significant reduction in a margin of safety. The basis for this proposed... accordance with the Commission's ``Rules of Practice for Domestic Licensing Proceedings'' in 10 CFR Part 2...

Licensing and regulatory control of nuclear power plants in the Federal Republic of Germany

International Nuclear Information System (INIS)

Schnurer, H.

1975-01-01

Legal basis; licensing requirements by the Atomic Energy Act, national law, international law and recommendations, and by technical rules and standards; licensing process: types of licences, responsibilities, sequence of the procedure; role of technical advisory bodies, enforcement of licensing actions. (HP) [de

SSM's licensing review of a spent nuclear fuel repository in Sweden

International Nuclear Information System (INIS)

Dverstorpand, Bjoern; Stroemberg, Bo

2014-01-01

On 16 March 2011 the Swedish Nuclear Fuel and Waste Management Co. (SKB) submitted license applications for a general license to construct, possess and operate a KBS-3 type spent nuclear fuel repository at the Forsmark site, in Oesthammar municipality, and an encapsulation plant in Oskarshamn municipality. The KBS-3 method, which has been developed by SKB over a period of more than 30 years, entails disposing of the spent fuel in copper canisters, surrounded by a swelling bentonite clay, at about 500 m depth in crystalline basement rock. SKB's applications are being evaluated in parallel by the Swedish Radiation Safety Authority (SSM) according to the Act on Nuclear Activities and by the Land and Environmental Court according to the Environmental Code. During the review SSM will act as an expert review body to the Land and Environmental Court in the areas of radiation protection, safety and security/non-proliferation. Both SSM and the court will produce a statement with a recommendation regarding a licensing decision and licensing conditions to the government. The government will make the final decision after consulting the municipalities concerned by SKB's facilities (municipal veto applies). The current licensing decision is just one of several licensing decisions that will be required for the repository. However it is arguably the most important one, because it is the last licensing stage with a broad societal involvement including an environmental impact assessment (EIA) process, national consultations and municipal veto for the concerned municipalities. The licensing steps to follow, should SKB be granted a license by the government, only require approval by SSM. These steps include application for start of actual construction work, test operation and routine operation. (authors)

Atomic Safety and Licensing Board Panel annual report, Fiscal year 1992

International Nuclear Information System (INIS)

1993-09-01

In Fiscal Year 1992, the Atomic Safety and Licensing Board Panel (''the Panel'') handled 38 proceedings. The cases addressed issues in the construction, operation, and maintenance of commercial nuclear power reactors and other activities requiring a license from the Nuclear Regulatory Commission. This reports sets out the Panel's caseload during the year and summarizes, highlights, and analyzes how the wide-ranging issues raised in those proceedings were addressed by the Panel's judges and licensing boards

Licensing the First Nuclear Power Plant. INSAG-26. A report by the International Nuclear Safety Group (Russian Edition)

International Nuclear Information System (INIS)

2016-01-01

features as a nuclear power plant that is already licensed by an experienced regulator. Consequently, an option is to start development of national regulations by adopting or adapting regulations from a country that has licensed the same type of nuclear power plant. However, if the intention is to have an open technology selection process, care should be taken to establish a set of technology neutral regulations, such as by using the IAEA safety standards as the foundation. This set of technology neutral regulations can then be complemented by more design specific regulations after the technology is chosen. Since the development of technical competences requires considerable time, the regulatory body needs to plan for human resources development at a very early stage. As a first step, the essential competences required for the different phases of the nuclear power programme should be identified. Thereafter, formal training arrangements should be established between the regulatory body and one or more experienced regulators that have licensed a similar facility. This should include early interaction between senior managers of the two regulators followed by detailed training of selected staff who will form the technical core of the regulatory body. The regulatory body should also identify outside organizations that will act as its technical support organizations (TSOs) and should provide for conduct of nuclear safety R and D by these TSOs, including the appropriate research facilities and expertise. If additional nuclear power plants will be constructed in the new entrant country in the future, the new nuclear power plant units may not be of the same design as the first plant. This aspect should be kept in mind when developing both the licensing methodologies and staff. Regulatory staff can also obtain significant benefit from participation in international cooperation activities such as the Convention on Nuclear Safety, technical cooperation forums of regulatory bodies of

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

Lifescience Database Archive (English)

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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)

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.

Electromagnetic trapping of neutral atoms

International Nuclear Information System (INIS)

Metcalf, H.J.

1986-01-01

Cooling and trapping of neutral atoms is a new branch of applied physics that has potential for application in many areas. The authors present an introduction to laser cooling and magnetic trapping. Some basic ideas and fundamental limitations are discussed, and the first successful experiments are reviewed. Trapping a neutral object depends on the interaction between an inhomogeneous electromagnetic field and a multiple moment that results in the exchange of kinetic for potential energy. In neutral atom traps, the potential energy must be stored as internal atomic energy, resulting in two immediate and extremely important consequences. First, the atomic energy levels will necessarily shift as the atoms move in the trap, and, second, practical traps for ground state neutral atoms atr necessarily very shallow compared to thermal energy. This small depth also dictates stringent vacuum requirements because a trapped atom cannot survive a single collision with a thermal energy background gas molecule. Neutral trapping, therefore, depends on substantial cooling of a thermal atomic sample and is inextricably connected with the cooling process

Technology licensing in China

DEFF Research Database (Denmark)

Wang, Yuandi; Li-Ying, Jason; Chen, Jin

2015-01-01

We explore the landscape of technology licensing among Chinese entities in the period 2000–12, using a unique database on technological licensing from the State Intellectual Property Office of China. We find that: first, among Chinese licensee organizations, firms have dominated in terms...... of the number of licensed technologies; second, the geographical distribution of licensed technologies among the provinces has gradually reached a new quantitative balance; third, utility models are the most popular technologies to be licensed and the majority of technology licensing in China has been between...... Chinese entities, and most transactions have been local within provinces; and finally, Chinese firms have gradually in-licensed newer and newer technologies, but the technologies in-licensed from foreign sources are by no means state-of-the-art. We make several suggestions for innovation policy...

MARSSIM guidelines for non-impacted area identification in support of partial site release prior to license termination

International Nuclear Information System (INIS)

Parish, D.

1999-01-01

Regulations are in place which allow plants undergoing decommissioning to remove obsolete requirements from their licenses. Large buffer areas to the site boundary, needed for emergency planning purposes during power operation, are not required for permanently defueled facilities. It is important that non-impacted areas be removed from license restrictions as soon as possible post shutdown to allow rapid asset recovery and return the large environmental resources these areas represent to beneficial use. License termination surveys are not required for non-impacted areas in accordance with the guidance of US Nuclear Regulatory Commission (NRC) NUREG-1575 (MARSSIM), and NRC Draft Regulatory Guide DG-4006. Thus, such areas do not fall under the license termination requirements of 10CFR50.82 (US Code of Federal Regulations). This report describes methods of classifying areas as non-impacted in accordance with MARRSIM and other NRC guidance, and the licensing options for release of non-impacted areas prior to license termination. The status of Big Rock Point's efforts toward early release of non-impacted areas also is provided. (author)

14 CFR 1274.942 - Export licenses.

Science.gov (United States)

2010-01-01

... writing, that the Agreement Officer authorize it to export ITAR-controlled technical data (including... appropriate licenses or other approvals, if required, for exports of hardware, technical data, and software, or for the provision of technical assistance. (b) The Recipient shall be responsible for obtaining...

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

Compliance of the Vaalputs national radioactive waste disposal facility to a frequency-magnitude release criterion as required for licensing

International Nuclear Information System (INIS)

Adrian, H.W.W.; Gerber, H.H.; Kruger, J.; Weygand, J.

1986-01-01

Accidental releases of radioactivity from the Vaalputs nuclear waste repository have been quantified and release frequencies have been attached to a number of accident scenarios of human or natural origin. These have then been compared to a frequency-magnitude release criterion according to South African licensing requirements. It was shown that the criterion was applicable in three release bands. In two of these the criterion was met by some orders of magnitude. In the third band the permitted release frequency was a factor 55 below the limit in spite of pessimistic release assumptions

License application approach for the California LLRW disposal facility

International Nuclear Information System (INIS)

Gaynor, R.K.; Romano, S.A.; Hanrahan, T.P.

1990-01-01

US Ecology, Inc. is the State of California's license designee to site, develop and operate a low-level radioactive waste (LLRW) disposal facility to serve member states of the Southwestern Compact. US Ecology identified a proposed site in the Ward Valley of southeastern California in March 1988. Following proposed site selection, US Ecology undertook studies required to prepare a license application. US Ecology's license application for this desert site was deemed complete for detailed regulatory review by the California Department of Health Services (DHS) in December 1989. By mutual agreement, disposal of mixed waste is not proposed pending the State of California's decision on appropriate management of this small LLRW subset

Are "Market Neutral" Hedge Funds Really Market Neutral?

OpenAIRE

Andrew J. Patton

2009-01-01

Using a variety of different definitions of "neutrality," this study presents significant evidence against the neutrality to market risk of hedge funds in a range of style categories. I generalize standard definitions of "market neutrality," and propose five different neutrality concepts. I suggest statistical tests for each neutrality concept, and apply these tests to a database of monthly returns on 1423 hedge funds from five style categories. For the "market neutral" style, approximately o...

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

Role of fission gas release in reactor licensing

International Nuclear Information System (INIS)

1975-11-01

The release of fission gases from oxide pellets to the fuel rod internal voidage (gap) is reviewed with regard to the required safety analysis in reactor licensing. Significant analyzed effects are described, prominent gas release models are reviewed, and various methods used in the licensing process are summarized. The report thus serves as a guide to a large body of literature including company reports and government documents. A discussion of the state of the art of gas release analysis is presented

Methodology and findings of the NRC`s materials licensing process redesign

Energy Technology Data Exchange (ETDEWEB)

Rathbun, P.A.; Brown, K.D.; Madera, J.R.; Moriarty, M.; Pelchat, J.M.; Usilton, W.K.; Whitten, J.E.; Vacca, P.C.

1996-04-01

This report describes the work and vision of the team chartered to redesign the process for licensing users of nuclear materials. The Business Process Redesign team was chartered to improve the speed of the existing licensing process while maintaining or improving public safety and to achieve required resource levels. The report describes the team`s methods for acquiring and analyzing information about the existing materials licensing process and the steps necessary to radically change this process to the envisioned future process.

47 CFR 13.17 - Replacement license.

Science.gov (United States)

2010-10-01

... 47 Telecommunication 1 2010-10-01 2010-10-01 false Replacement license. 13.17 Section 13.17 Telecommunication FEDERAL COMMUNICATIONS COMMISSION GENERAL COMMERCIAL RADIO OPERATORS General § 13.17 Replacement... request a replacement. The application must be accompanied by the required fee and submitted to the...

Advanced CANDU reactor pre-licensing progress

International Nuclear Information System (INIS)

Popov, N.K.; West, J.; Snell, V.G.; Ion, R.; Archinoff, G.; Xu, C.

2005-01-01

The Advanced CANDU Reactor (ACR) is an evolutionary advancement of the current CANDU 6 reactor, aimed at producing electrical power for a capital cost and at a unit-energy cost significantly less than that of the current reactor designs. The Canadian Nuclear Safety Commission (CNSC) staff are currently reviewing the ACR design to determine whether, in their opinion, there are any fundamental barriers that would prevent the licensing of the design in Canada. This CNSC licensability review will not constitute a licence, but is expected to reduce regulatory risk. The CNSC pre-licensing review started in September 2003, and was focused on identifying topics and issues for ACR-700 that will require a more detailed review. CNSC staff reviewed about 120 reports, and issued to AECL 65 packages of questions and comments. Currently CNSC staff is reviewing AECL responses to all packages of comments. AECL has recently refocused the design efforts to the ACR-1000, which is a larger version of the ACR design. During the remainder of the pre-licensing review, the CNSC review will be focused on the ACR-1000. AECL Technologies Inc. (AECLT), a wholly-owned US subsidiary of AECL, is engaged in a pre-application process for the ACR-700 with the US Nuclear Regulatory Commission (USNRC) to identify and resolve major issues prior to entering a formal process to obtain standard design certification. To date, the USNRC has produced a Pre-Application Safety Assessment Report (PASAR), which contains their reviews of key focus topics. During the remainder of the pre-application phase, AECLT will address the issues identified in the PASAR. Pursuant to the bilateral agreement between AECL and the Chinese nuclear regulator, the National Nuclear Safety Administration (NNSA) and its Nuclear Safety Center (NSC), NNSA/NSC are reviewing the ACR in seven focus areas. The review started in September 2004, and will take three years. The main objective of the review is to determine how the ACR complies

Licensing of New Nuclear Power Plants in Canada

International Nuclear Information System (INIS)

Schwarz, Garry; Miller, Doug

2011-01-01

The regulatory process for new power plant licensing in Canada, from receipt of the initial application to commercial operation, can be divided into three phases: - Environmental Assessment (EA) and License to Prepare Site; - License to Construct; and - License to Operate. The Nuclear Safety and Control Act (NSCA) does not have provisions for combined licenses for site preparation, construction, or operation. Separate licenses must, therefore, be granted for each phase, and would be issued in sequence. However, applications to prepare a site, to construct and to operate a new nuclear power plant could be assessed in parallel. The total duration from the application for the License to Prepare Site to the issuance of the License to Operate (which is a prerequisite for first fuel load) has been established as 9 years subject to certain factors. To help facilitate this timeline, the CNSC has undertaken an aggressive program of documenting regulatory practices, requirements and guidance to assist applicants in submitting complete applications. Working level procedures to assist CNSC staff in their review of submissions are also under development. Extensive program and project management has been introduced to ensure that timelines will be achieved. In parallel with the above activities, regulatory oversight measures to be employed during site preparation activities and plant construction and commissioning are also being developed. On the international front, the CNSC is participating in the MDEP program to leverage the resources and knowledge of other national regulatory authorities in reviews the CNSC is undertaking. The CNSC also participates in IAEA and other international activities to utilize/adapt international practices as appropriate in Canada. (authors)

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.

Improvement suggestions on license extension management for civil nuclear safety equipment activities

International Nuclear Information System (INIS)

Sun Xingjian; Liu Hongji; Han Guoli; Jia Fengcai

2013-01-01

Based on the concepts of Clear Requirements, Comprehensive Review, Objective Assessment, Dynamic Management, this paper gives improvement suggestions on license extension management for civil nuclear safety equipment design, manufacture, installation and non-destructive examination activities, which include establishing a relatively unified license extension review standard, combining multi-views and close linking license review and supervision, full utilizing the daily supervision and inspection results, as well as further improving motivation and elimination mechanism. (authors)

Management of the licensing of users of radioactive materials should be improved

International Nuclear Information System (INIS)

1976-01-01

Radioactive material licenses are required for manufacturing nuclear fuel for reactors and for industrial, commercial, medical, and educational uses of radioactive materials. This type of license is not for constructing or operating nuclear power reactors and facilities for processing used nuclear fuels. This report discusses the need for better management improvements in the NRC's program for licensing the users. As of December 31, 1974, there were 8,253 active NRC-issued material licenses held by 6,310 licensees. The study reviewed NRC's policies, procedures, and practices, and examined recent evaluations of state programs to identify problems encountered by the states

A review of electric cable aging effects and monitoring programs for plant license renewal

International Nuclear Information System (INIS)

Lofaro, R.J.

1999-01-01

As commercial nuclear power plants approach the end of their original license period, some utilities are considering the possibility of license renewal. The requirements for applying for license renewal are specified in the License Renewal Rule, which is in Title 10 of the Code of Federal Regulations, Part 54 (10 CFR54). Among the requirements specified in the rule is the performance of an Integrated Plant Assessment (IPA) which identifies and lists structures and components subject to an aging management review. The intent of this requirement is to ensure that aging degradation will not adversely affect plant safety during the license renewal period. The aging management review includes an identification of the aging effects and monitoring programs for components within the scope of the rule. Among the components within the scope are electric cables since they are passive, long-lived components that are not replaced on a periodic basis. This paper examines the aging causes and effects of electric cables, along with the programs that are typically used to ensure that proper aging management practices are in place to monitor and mitigate the effects of aging on electric cables

Image simulation for automatic license plate recognition

Science.gov (United States)

Bala, Raja; Zhao, Yonghui; Burry, Aaron; Kozitsky, Vladimir; Fillion, Claude; Saunders, Craig; Rodríguez-Serrano, José

2012-01-01

Automatic license plate recognition (ALPR) is an important capability for traffic surveillance applications, including toll monitoring and detection of different types of traffic violations. ALPR is a multi-stage process comprising plate localization, character segmentation, optical character recognition (OCR), and identification of originating jurisdiction (i.e. state or province). Training of an ALPR system for a new jurisdiction typically involves gathering vast amounts of license plate images and associated ground truth data, followed by iterative tuning and optimization of the ALPR algorithms. The substantial time and effort required to train and optimize the ALPR system can result in excessive operational cost and overhead. In this paper we propose a framework to create an artificial set of license plate images for accelerated training and optimization of ALPR algorithms. The framework comprises two steps: the synthesis of license plate images according to the design and layout for a jurisdiction of interest; and the modeling of imaging transformations and distortions typically encountered in the image capture process. Distortion parameters are estimated by measurements of real plate images. The simulation methodology is successfully demonstrated for training of OCR.

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

The role of ground-water travel time in suitability and licensing

International Nuclear Information System (INIS)

Murphy, M.R.

1995-01-01

This paper examines the Department of Energy (DOE) guidelines and Nuclear Regulatory Commission (NRC) licensing criteria pertaining to groundwater travel time, and their impact on obtaining a license for Yucca Mountain. DOE will be able to obtain a license for Yucca Mountain even if it is determined that there are some fast pathways along which groundwater travel time to the accessible environment is less than 1000 years. However, this will require DOE to gather and analyze a significant amount of firm data, rather than relying primarily on conservative assumptions and bounding calculations

Final environmental statement concerning rule making. Exemption from licensing requirements for spark-gap irradiators that contain cobalt-60. Docket No. PRM 30-54

International Nuclear Information System (INIS)

1977-12-01

The potential environmental impacts and adverse environmental effects from distribution, use only in commercial-sized oil burners, and disposal of 6000 spark-gap irradiators per year that contain 60 Co are summarized. On the basis of the analysis and evaluation set forth in this statement and after weighing the environmental, economic, technical, and other benefits against environmental costs and after considering available alternatives, it is concluded that the action called for under the National Environmental Policy Act of 1969 (NEPA) and 10 CFR Part 51 is the issuance of an exemption from licensing requirements for spark-gap irradiators that contain 60 Co, subject to the following conditions for the protection of the environment: persons who apply 60 Co to, or persons who incorporate 60 Co into, spark-gap irradiators or persons who import for sale or distribution spark-gap irradiators containing 60 Co are not exempt from the requirements for a license; each spark-gap irradiator shall contain no more than 1 μCi of 60 Co; and the 60 Co shall be applied to the spark-gap irradiators for use in electrically ignited fuel-oil burners having a firing rate of at least 3 gal/h

Identifying the Role of E2 Domains on Alphavirus Neutralization and Protective Immune Responses.

Directory of Open Access Journals (Sweden)

James Weger-Lucarelli

Full Text Available Chikungunya virus (CHIKV and other alphaviruses are the etiologic agents of numerous diseases in both humans and animals. Despite this, the viral mediators of protective immunity against alphaviruses are poorly understood, highlighted by the lack of a licensed human vaccine for any member of this virus genus. The alphavirus E2, the receptor-binding envelope protein, is considered to be the predominant target of the protective host immune response. Although envelope protein domains have been studied for vaccine and neutralization in flaviviruses, their role in alphaviruses is less characterized. Here, we describe the role of the alphavirus E2 domains in neutralization and protection through the use of chimeric viruses.Four chimeric viruses were constructed in which individual E2 domains of CHIKV were replaced with the corresponding domain from Semliki Forest virus (SFV (ΔDomA/ΔDomB/ΔDomC/ ΔDomA+B. Vaccination studies in mice (both live and inactivated virus revealed that domain B was the primary determinant of neutralization. Neutralization studies with CHIKV immune serum from humans were consistent with mouse studies, as ΔDomB was poorly neutralized.Using chimeric viruses, it was determined that the alphavirus E2 domain B was the critical target of neutralizing antibodies in both mice and humans. Therefore, chimeric viruses may have more relevance for vaccine discovery than peptide-based approaches, which only detect linear epitopes. This study provides new insight into the role of alphavirus E2 domains on neutralization determinants and may be useful for the design of novel therapeutic technologies.

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

Finnish experiences on licensing and using of programmable digital systems in nuclear power plants

International Nuclear Information System (INIS)

Haapanen, P.; Maskuniitty, M.; Heimburger, H.; Hall, L.E.; Manninen, T.

1993-01-01

Finnish utility companies, Imatran Voima Oy (IVO) and Teollisuuden Voima (TVO), and the licensing authority, the Finnish Centre for Radiation and Nuclear Safety (STUK), are preparing for a new nuclear power plant in Finland. Plant vendors are proposing programmable digital automation systems for both the safety-related and the operational I and C (instrumentation and control) systems in this new unit. Also in existing plant units the replacement of certain old analog systems with state-of-the-art digital ones will become necessary in the years to come. Licensing of programmable systems for safety critical applications requires a new approach due to the special properties and failure modes of these systems. The major difficulties seem to be in the assessment and quantification of software reliability. The Technical Research Centre of Finland has in co-operation with the authority and the utilities conducted a project (AJA) to develop domestically applicable licensing requirements, guidelines and practices. International standards, guidelines and licensing practices have been analyzed in order to specify national licensing requirements. The paper describes and discusses the findings and experiences of the AJA project so far. The experience in introducing advanced programmable digital control and computer systems in the operating nuclear power plants will be covered briefly. Although these systems are not safety-related but systems of more general interest regarding nuclear safety, some routines regarding the licensing of safety- related systems have been followed. In these backfitting and replacement projects some experience have been gained in how to license safety-related programmable systems. (Author) 31 refs., 2 figs

Licensing of ANSTO's Replacement Research Reactor

International Nuclear Information System (INIS)

Summerfield, M.W.; Garea, V.

2003-01-01

This paper presents a general description of the licensing of the 20 MW Pool-type Replacement Research Reactor (RRR) currently being built by the Australian Nuclear Science and Technology Organisation (ANSTO) at their Lucas Heights site. The following aspects will be addressed: 1) The influence of ARPANSA's (the Australian regulator) Regulatory Assessment Principles and Design Criteria on the design of the RRR. 2) The Site Licence Application, including the EIS and the supporting siting documentation. 3) The Construction Licence Application, including the PSAR and associated documentation. 4) The review process, including the IAEA Peer Review and the Public Submissions as well as ARPANSA's own review. 5) The interface between ANSTO, INVAP and ARPANSA in relation to the ongoing compliance with ARPANS Regulation 51 and 54. 6) The future Operating Licence Application, including the draft FSAR and associated documentation. These aspects are all addressed from the point of view of the licensee ANSTO and the RRR Project. Particular emphasis will be given to the way in which the licensing process is integrated into the overall project program and how the licensing and regulatory regime within Australia influenced the design of the RRR. In particular, the safety design features that have been incorporated as a result of the specific requirements of ANSTO and the Australian regulator will be briefly described. The paper will close with a description of how the RRR meets, and in many aspects exceeds the requirements of ANSTO and the Australian regulator. (author)

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

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.

Why operators fail licensing examinations

International Nuclear Information System (INIS)

Roth, D.R.; Zerbo, J.N.

1975-01-01

A survey was conducted among nuclear utility operators who have taken NRC licensing examinations to determine which factors they considered important in their success or failure. The operators also compared the actual NRC examination with their expectations prior to taking the examination. The results of the survey supplement NRC statistics with regard to failure rates. Over 350 operators and 20 utilities participated in the survey and a good cross section of the nuclear community is represented. Reactor theory and emergency procedures are important areas in which operators found NRC emphasis to be different than expected. Observation Training and Design Lecture Series are two training segments which appear to require improvement. Recommendations are made for the use of data collected through this survey and for continuation of the effort to give operators a mechanism of supplying feedback to the training and licensing process

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

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)

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...

Reactor licensing process: a status report

International Nuclear Information System (INIS)

Long, J.A.

1977-01-01

The Nuclear Regulatory Commission (NRC), in its review of applications for licenses to construct and operate nuclear power plants, is required to consider those measures necessary to ensure the protection of the health and safety of the public and the environment. The article discusses the NRC staff procedures and policies for conducting the detailed safety, environmental, and antitrust reviews that provide the basis for these assurances. Included is a discussion of the improvements to the licensing process currently being proposed or implemented to enhance its stability and predictability for the benefit of all involved with the regulation of nuclear power. The views and opinions expressed in the article are those of the author alone and do not represent positions of the NRC

Aspects of the licensing procedures for enrichment reduction in research reactors

International Nuclear Information System (INIS)

Krull, W.

1983-01-01

The enrichment reduction for research reactors requires a licensing procedure. For this purpose the qualification of the new fuel has to be demonstrated and changes in reactor safety have to be investigated like reactivity values, form-factors, Pu- and fission product inventory, safety margins and accidents. Calculations should be partly experimentally verified. The possible extent of the licensing procedure is discussed. (orig.) [de

Welding for fusion grade neutral beam components - requirements, challenges, experiences and learnings

International Nuclear Information System (INIS)

Joshi, Jaydeep; Patel, Hitesh; Yadav, Ashish; Rotti, Chandramouli; Bandyopadhyay, Mainak; Chakraborty, Arun

2016-01-01

Negative ion based Neutral Beam Injectors (NBI) are the integral part of large size fusion devices where Neutral Beams of Hydrogen/Deuterium atoms are injected into the fusion reactor to heat the plasma, drive a plasma current, provide fuel to the plasma and also help to diagnose the plasma through spectroscopic measurements. The presentation shares the experiences of handling, some of special welding activities applicable for fusion prototypes developments, experiments, methodology developed for the inspection/tests, criteria considered with the appropriate justifications. This also shares the view point of authors code should further be supplement and incorporate the fusion specific applications considering future needs. In addition, explorations to meet our future needs of welding with specific attention to indigenous developments have been described

A General Nonlinear Fluid Model for Reacting Plasma-Neutral Mixtures

Energy Technology Data Exchange (ETDEWEB)

Meier, E T; Shumlak, U

2012-04-06

A generalized, computationally tractable fluid model for capturing the effects of neutral particles in plasmas is derived. The model derivation begins with Boltzmann equations for singly charged ions, electrons, and a single neutral species. Electron-impact ionization, radiative recombination, and resonant charge exchange reactions are included. Moments of the reaction collision terms are detailed. Moments of the Boltzmann equations for electron, ion, and neutral species are combined to yield a two-component plasma-neutral fluid model. Separate density, momentum, and energy equations, each including reaction transfer terms, are produced for the plasma and neutral equations. The required closures for the plasma-neutral model are discussed.

24 CFR 3286.207 - Process for obtaining installation license.

Science.gov (United States)

2010-04-01

... installation license must submit verification of the experience required in § 3286.205(a). This verification may be in the form of statements by past or present employers or a self-certification that the applicant meets those experience requirements, but HUD may contact the applicant for additional verification...

On the reform of nuclear licensing procedures for plants and operation

International Nuclear Information System (INIS)

Lecheler, H.

1977-01-01

The nuclear licensing procedures require basic reforming. In doing so, there must be a differentiation between (concrete) licensing of plants and (abstract) decisions on site provision. The provision of sites is exercised directly by the diets of the Laender. For this purpose they enact planning laws on sites for nuclear power plants of different sizes. As far as the Federal law is touched upon (especially the Federal act on construction), the Federal legislator has to concede competences to the Laender. No. 6 of section 7 II of the Atomic Energy Act would have to be deleted. The plant licensing procedure is to be limited to a mere safety check-up of a concrete plant. Licensing prerequisites of the Atomic Energy Act are to be made more precise by the Federal legislator, namely by deciding unequivocally the purpose of the law, whether priority is given to promotion or to protection, and by making the enacting of tangible regulations a duty. When these licensing prerequisites exist, the law has to concede the applicant a plain title to licensing. (orig.) [de

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...

Initial operation and performance of the PDX neutral-beam injection system

International Nuclear Information System (INIS)

Kugel, H.W.; Eubank, H.P.; Kozub, T.A.; Rossmassler, J.E.; Schilling, G.; van Halle, A.; Williams, M.D.

1982-01-01

In 1981, the joint ORNL/PPPL PDX neutral beam heating project succeeded in reliably injecting 7.2 MW of D 0 into the PDX plasma, at nearly perpendicular angles, and achieved ion temperatures up to 6.5 keV. The expeditious achievement of this result was due to the thorough conditioning and qualification of the PDX neutral beam ion sources at ORNL prior to delivery coupled with several field design changes and improvements in the injection system made at PPPL as a result of neutral beam operating experience with the PLT tokamak. It has been found that the operation of high power neutral beam injection systems in a tokamak-neutral beam environment requires procedures and performance different from those required for development operation on test stands. In this paper, we review the installatin of the PDX neutral beam injection system, and its operation and performance during the initial high power plasma heating experiments with the PDX tokamak

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

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)

37 CFR 370.2 - Notice of use of sound recordings under statutory license.

Science.gov (United States)

2010-07-01

... BOARD, LIBRARY OF CONGRESS NOTICE AND RECORDKEEPING REQUIREMENTS FOR STATUTORY LICENSES NOTICE AND... gain access to the online Web site or homepage of the Service, or where information may be posted under... obtained from the Copyright Office or to: Library of Congress, Copyright Office, Licensing Division, 101...

Environmental impact studies of projects be licensed under the Atomic Law

International Nuclear Information System (INIS)

Heuel-Fabianek, Burkhard; Lennartz, Reinhard

2009-01-01

The German Law on Environmental Impact Assessment (UVPG) defines projects to be licensed under the Atomic Law that require an environmental impact study (EIS). Since the project concepts as defined in the UVPG are often not the same as those defined in the Atomic Law (AtG), the licensing authority has to decide which project should be subjected to an EIA. Additionally, Article 37 of the EURATOM Treaty obliges every Member State to communicate certain data relating to the impact of emissions of radioactive substances to the Commission. This is independent of the EIA. A licence may only be granted by the competent authorities if an opinion has been received from the Commission pursuant to Article 37. In either case, the licensing authority is the first point of contact for the applicant if the question arises of whether a project has to be subjected to an EIA. A ''voluntary'' EIA should be regarded with caution because of the complexity of such a procedure within the licensing process requiring considerable resources of time and manpower, and the danger of a loss of credibility of the EIA. (orig.)

Antihypertensive neutral lipid

Science.gov (United States)

Snyder, F.L.; Blank, M.L.

1984-10-26

The invention relates to the discovery of a class of neutral acetylated either-linked glycerolipids having the capacity to lower blood presure in warm-blooded animals. This physiological effect is structure sensitive requiring a long chain alkyl group at the sn-1 position and a short carbon chain acyl group (acetyl or propionyl) at the sn-2 position, and a hydroxyl group at the sn-3 position.

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....

Validation, acceptance and licensing

International Nuclear Information System (INIS)

Wene, C.O.

1992-01-01

The licensing process requires communication of complex scientific and technical information. In this paper transfer of such information is discussed using concepts and ideas from systems analysis, cybernetics and argumentation theory. A simple model for the decision process is developed. The analysis stresses the need for careful design of the communication channels between the three systems involved: the political system, the judicial-regulatory system and the scientific-technical community. The Dialogue - Scenario project initiated by the Swedish nuclear Inspectorate is briefly presented

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

Apparatus for neutralization of accelerated ions

International Nuclear Information System (INIS)

Fink, J.H.; Frank, A.M.

1979-01-01

Apparatus is described for neutralization of a beam of accelerated ions, such as hydrogen negative ions (H - ), using relatively efficient strip diode lasers which emit monochromatically at an appropriate wavelength (lambda = 8000 A for H - ions) to strip the excess electrons by photodetachment. A cavity, formed by two or more reflectors spaced apart, causes the laser beams to undergo multiple reflections within the cavity, thus increasing the efficiency and reducing the illumination required to obtain an acceptable percentage (approx. 85%) of neutralization

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

Optimal neutral beam heating scenario for FED

International Nuclear Information System (INIS)

Hively, L.M.; Houlberg, W.A.; Attenberger, S.E.

1981-01-01

Optimal neutral beam heating scenarios are determined for FED based on a 1/one-half/-D transport analysis. Tradeoffs are examined between neutral beam energy, power, and species mix for positive ion systems. A ramped density startup is found to provide the most economical heating. The resulting plasma power requirements are reduced by 10-30% from a constant density startup. For beam energies between 100 and 200 keV, the power needed to heat the plasma does not decrease significantly as beam energy is increased. This is due to reduced ion heating, more power in the fractional energy components, and rising power supply requirements as beam energy increases

Applications of neutral beam and rf technologies

International Nuclear Information System (INIS)

Haselton, H.H.

1987-04-01

This presentation provides an update on the applications of neutral beams and radiofrequency (rf) power in the fusion program; highlights of the ion cyclotron heating (ICH) experiments now in progress, as well as the neutral beam experiments; and heating requirements of future devices and some of the available options. Some remarks on current drive are presented because this area of technology is one that is being considered for future devices

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

On becoming neutral: effects of experimental neutralizing reconsidered.

Science.gov (United States)

van den Hout, M; van Pol, M; Peters, M

2001-12-01

Behaviour Research and Therapy 34 (1996) 889-898 found that writing out a negative thought produced anxiety and an urge to neutralize the thought, that instructing participants to neutralize the thought reduced anxiety/neutralization urge in the short run (i.e. within 2 min), but that in the control group 20 min without instruction was attended by the same reduction in anxiety/urge to neutralize ("natural decay"). The observations were made with pariticipants who scored high on "thought action fusion" and the experiment was set up as exerimental model of obsessions. We repeated the study with participants that were not selected on thought action fusion. All the findings reported by Behaviour Research and Therapy 34 (1996) 889-898 were replicated. Correlational analysis indicated that the strength of the effect was not related to scores on scales measuring "thought action fusion". Behaviour Research and Therapy 34 (1996) 889-898 did not assess whether non-neutralizing was followed by immediate reductions in distress. We did assess this and found that the larger part of the immediate reduction of distress after neutralization also occurs when no neutralization instruction is given. The effects of neutralization instructions in the present type of experiment are considerably less powerful than suggested earlier.

Neutral beam systems for the magnetic fusion program

International Nuclear Information System (INIS)

Beal, J.W.; Staten, H.S.

1977-01-01

The attainment of economic, safe fusion power has been described as the most sophisticated scientific problem ever attacked by mankind. The presently established goal of the magnetic fusion program is to develop and demonstrate pure fusion central electric power stations for commercial applications. Neutral beam heating systems are a basic component of the tokamak and mirror experimental fusion plasma confinement devices. The requirements placed upon neutral beam heating systems are reviewed. The neutral beam systems in use or being developed are presented. Finally, the needs of the future are discussed

The changing shape of U.S. licensing philosophy

International Nuclear Information System (INIS)

Remick, F.J.

1992-01-01

The shape of U.S. nuclear licensing and regulatory philosophy and process has already changed. The new process requires NRC review and approval of the vendor designs before a prospective utility license applicant purchases the design and begins construction. The new philosophy has resulted from the lessons learned from extensive operating experience accumulated in the United States. New criteria established for judging reactor designs include the capability of future designs to be more tolerant of accidents beyond the traditional design basis events. Qualitative and quantitative goals have been chosen as a guide for allocating resources for regulation of the currently operating plants. The changing shape of nuclear licensing and regulatory philosophy is also a result of economic circumstances in the United States. All will have a better opportunity to take part in the process which is most likely to encourage further development of safe nuclear energy in the United States. (author)

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.

Charge neutralization of small ion beam clumps

Energy Technology Data Exchange (ETDEWEB)

Welch, D R [Mission Research Corp., Albuquerque, NM (United States); Olson, C L; Hanson, D L [Sandia National Labs., Albuquerque, NM (United States)

1997-12-31

The mega-ampere currents associated with light ion fusion (LIF) require excellent charge neutralization to prevent divergence growth. As the size and space-charge potential of a beam clump or `beamlet` become small (submillimeter size and kilovolt potentials), the neutralization becomes increasingly difficult. Linear theory predicts that plasma electrons cannot neutralize potentials < {phi}{sub crit} = (1/2)m{sub e}v{sub i}{sup 2}/e, where m{sub e} is the electron mass and v{sub i} is the ion beam velocity. A non-uniform beam would, therefore, have regions with potentials sufficient to add divergence to beam clumps. The neutralization of small beamlets produced on the SABLE accelerator and in numerical simulation has supported the theory, showing a plateau in divergence growths as the potential in the beamlet exceeds {phi}{sub crit}. (author). 1 tab., 2 figs., 4 refs.

Specification of requirements to get a license for an Independent Spent Fuel Dry Storage Installation (ISFSI) at the site of the NPP-LV; Especificacion de los requerimientos para tramitar una licencia de una instalacion independiente de almacenamiento temporal en seco de combustible gastado (ISFSI) en el sitio de la CNLV

Energy Technology Data Exchange (ETDEWEB)

Serrano R, M. L., E-mail: mlserrano@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan 779, Col. Narvarte, 03020 Ciudad de Mexico (Mexico)

2015-09-15

This article describes some of the work done in the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) to define specifically the requirements that the Federal Electricity Commission (CFE) shall meet to submit for consideration of CNSNS an operation request of an Independent Spent Fuel Dry Storage Installation (ISFSI). The project of a facility of this type arose from the need to provide storage capacity for spent nuclear fuel in the nuclear power plant of Laguna Verde (NPP-LV) and to continue the operation at the same facility in a safe manner. The licensing of these facilities in the United States of America has two modes: specific license or general license. The characteristics of these licenses are described in this article. However, in Mexico the existing national legislation is not designed for such license types, in fact there is a lack of standards or regulations in this regard. The regulatory law of Article 27 of the Constitution in the nuclear matter, only generally establishes that this type of facility requires an authorization from the Ministry of Energy. For this reason and because there is not a national legislation, was necessary to use the legislation that provides the Nuclear Regulatory Commission of USA, the US NRC. However, it cannot be applied as is established, so was necessary that the CNSNS analyze one by one the requirements of both types of license and determine what would be required to NPP-LV to submit its operating license of ISFSI. The American regulatory applicable to an ISFSI, the 10-Cfr-72 of the US NRC, establishes the requirements for both types of licenses. Chapter 10-Cfr was analyzed in all its clauses and coupled to the laws, regulations and standards as well as to the requirements established by CNSNS, all associated with a store spent fuel on site; the respective certification of containers for spent fuel dry storage was not included in this article, even though the CNSNS also performed that activity under the

Status of safety issues at licensed power plants

International Nuclear Information System (INIS)

1991-03-01

As part of ongoing US Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, a program has been established whereby an annual NUREG series report will be published on the status of licensee implementation and NRC verification of safety issues in major NRC requirement areas. The data contained in this report are a product of the NRC's Safety Issues Management System database, which is maintained by the Project Management Staff in the Office of Nuclear Reactor Regulation and by personnel in the NRC regions. This report has been prepared in order to provide a comprehensive description of the implementation and verification status of all the TMI Action Plan requirements at licensed reactors, and to make this information available to other interested parties, including the public. A corollary purpose of this report is for it to serve as a follow-on to NUREG-0933, ''A Prioritization of Safety Issues,'' which tracks safety issues up until requirements are approved for imposition at licensed facilities

Status of the Monticello nuclear generating plant lead plant license renewal program

International Nuclear Information System (INIS)

Pickens, T.A.

1992-01-01

In 1988, the Monticello nuclear generating plant was chosen by the US Department of Energy through Sandia National Laboratories and the Electric Power Research Institute to serve as the lead boiling water reactor in the lead plant license renewal program. The purpose of the lead plant license renewal program is to provide insights during the development of and to demonstrate the license renewal regulatory process with the US Nuclear Regulatory Commission (NRC). The work being performed in three phases: (1) preparation of the technical basis for license renewal; (2) development of the technical basis into a formal license renewal application; and (3) review of the application by the NRC. This paper discusses the systems and structures identified as important to license renewal in accordance with 10CFR54 as well as the plant documents and programs that were used in going through the identification process. The systems and structures important to license renewal will then provide insights into how structures and components were identified that are required to be evaluated for aging, the elements of the aging evaluations, and the effective programs used to manage potentially significant aging

Quality Assessment of Compressed Video for Automatic License Plate Recognition

DEFF Research Database (Denmark)

Ukhanova, Ann; Støttrup-Andersen, Jesper; Forchhammer, Søren

2014-01-01

Definition of video quality requirements for video surveillance poses new questions in the area of quality assessment. This paper presents a quality assessment experiment for an automatic license plate recognition scenario. We explore the influence of the compression by H.264/AVC and H.265/HEVC s...... recognition in our study has a behavior similar to human recognition, allowing the use of the same mathematical models. We furthermore propose an application of one of the models for video surveillance systems......Definition of video quality requirements for video surveillance poses new questions in the area of quality assessment. This paper presents a quality assessment experiment for an automatic license plate recognition scenario. We explore the influence of the compression by H.264/AVC and H.265/HEVC...... standards on the recognition performance. We compare logarithmic and logistic functions for quality modeling. Our results show that a logistic function can better describe the dependence of recognition performance on the quality for both compression standards. We observe that automatic license plate...

Status of safety issues at licensed power plants: TMI Action Plan requirements, unresolved safety issues, generic safety issues, other multiplant action issues

International Nuclear Information System (INIS)

1992-12-01

This report is to provide a comprehensive description of the implementation and verification status of Three Mile Island (TMI) Action Plan requirements, safety issues designated as Unresolved Safety Issues (USIs), Generic Safety Issues(GSIs), and other Multiplant Actions (MPAs) that have been resolved and involve implementation of an action or actions by licensees. This report makes the information available to other interested parties, including the public. An additional purpose of this NUREG report is to serve as a follow-on to NUREG-0933, ''A Prioritization of Generic Safety Issues,'' which tracks safety issues up until requirements are approved for imposition at licensed plants or until the NRC issues a request for action by licensees

Design of a negative ion neutral beam system for TNS

International Nuclear Information System (INIS)

Easoz, J.R.

1978-05-01

A conceptual design of a neutral beam line based on the neutralization of negative deuterium ions is presented. This work is a detailed design of a complete neutral beam line based on using negative ions from a direct extraction source. Anticipating major technological advancements, beam line components have been scaled including the negative ion sources and components for the direct energy recovery of charged beams and high speed cryogenic pumping. With application to the next step in experimental fusion reactors (TNS), the neutral beam injector system that has been designed provides 10 MW of 200 keV neutral deuterium atoms. Several arms are required for plasma ignition

Licensing of spent fuel storage facility including its physical protection in the Czech Republic

International Nuclear Information System (INIS)

Fajman, V.; Sedlacek, J.

1992-01-01

The current spent fuel management policies as practised in the Czech Republic are described, and the conception of the fuel cycle back end is outlined. The general principles and the legislative framework are explained of the licensing process concerning spent fuel interim storage facilities, including the environmental impact assessment component. The history is outlined of the licensing process for the spent fuel storage facility at the Dukovany NPP site, including the licensing of the transport and storage cask. The basic requirements placed on the physical safeguarding of the facility and on the licensing process are given. (J.B.). 13 refs

Methodology for LOCA analysis and its qualification procedures for PWR reload licensing

International Nuclear Information System (INIS)

Serrano, M.A.B.

1986-01-01

The methodology for LOCA analysis developed by FURNAS and its qualification procedure for PWR reload licensing are presented. Digital computer codes developed by NRC and published collectively as the WREM package were modified to get versions that comply to each requirement of Brazilian Licensing Criteria. This metodology is applied to Angra-1 basic case to conclude the qualification process. (Author) [pt

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

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...

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

Conceptual design of a neutral-beam injection system for the TFTR

International Nuclear Information System (INIS)

Ehlers, K.W.; Berkner, K.H.; Cooper, W.S.; Hooper, E.B.; Pyle, R.V.; Stearns, J.W.

1975-11-01

The neutral-beam injection requirements for heating and fueling the next generation of fusion reactor experiments far exceed those of present devices; the neutral-beam systems needed to meet these requirements will be large and complex. A conceptual design of a TFTR tokamak injection system to produce 120 keV deuterium-ion beams with a total power of about 80 MW is given

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)

Neutral beam injection in 2XIIB

International Nuclear Information System (INIS)

Hibbs, S.M.

1975-01-01

Integrated into the operation of the 2XIIB controlled fusion experiment is a 600-A, 20-keV neutral injection system: the highest neutral-beam current capacity of any existing fusion machine. This paper outlines the requirements of the injection system and the design features to which they led. Both mechanical and electrical aspects are discussed. Also included is a brief description of some operational aspects of the system and some of the things we have learned along the way, as well as a short history of the most significant developments

Serbia's Military Neutrality: Origins, effects and challenges

Directory of Open Access Journals (Sweden)

Ejdus Filip

2014-10-01

Full Text Available Serbia is the only state in the Western Balkans that is not seeking NATO membership. In December 2007, Serbia declared military neutrality and in spite of its EU membership aspirations, developed very close relations with Moscow. The objective of this paper is threefold. First, I argue that in order to understand why Serbia declared military neutrality, one has to look both at the discursive terrain and domestic power struggles. The key narrative that was strategically used by mnemonic entrepreneurs, most importantly by the former Prime Minister Vojislav Koštunica, to legitimize military neutrality was the trauma of NATO intervention in 1999 and the ensuing secession of Kosovo. In the second part of the paper, I discuss the operational consequences of the military neutrality policy for Serbia's relations with NATO and Russia, as well as for military reform and EU accession. Finally, I spell out the challenges ahead in Serbia's neutrality policy and argue that its decision makers will increasingly be caught between pragmatic foreign policy requirements on the one hand and deeply entrenched traumatic memories on the other.

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

Feline Immunodeficiency Virus (FIV Neutralization: A Review

Directory of Open Access Journals (Sweden)

Margaret J. Hosie

2011-10-01

Full Text Available One of the major obstacles that must be overcome in the design of effective lentiviral vaccines is the ability of lentiviruses to evolve in order to escape from neutralizing antibodies. The primary target for neutralizing antibodies is the highly variable viral envelope glycoprotein (Env, a glycoprotein that is essential for viral entry and comprises both variable and conserved regions. As a result of the complex trimeric nature of Env, there is steric hindrance of conserved epitopes required for receptor binding so that these are not accessible to antibodies. Instead, the humoral response is targeted towards decoy immunodominant epitopes on variable domains such as the third hypervariable loop (V3 of Env. For feline immunodeficiency virus (FIV, as well as the related human immunodeficiency virus-1 (HIV-1, little is known about the factors that lead to the development of broadly neutralizing antibodies. In cats infected with FIV and patients infected with HIV-1, only rarely are plasma samples found that contain antibodies capable of neutralizing isolates from other clades. In this review we examine the neutralizing response to FIV, comparing and contrasting with the response to HIV. We ask whether broadly neutralizing antibodies are induced by FIV infection and discuss the comparative value of studies of neutralizing antibodies in FIV infection for the development of more effective vaccine strategies against lentiviral infections in general, including HIV-1.

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...

A comparative analysis of the domestic and foreign licensing processes for power and non-power reactors

International Nuclear Information System (INIS)

Joe, J. C.; Youn, Y. K.; Kim, W. S.; Kim, H. J.

2003-01-01

The System-integrated Modular Advanced Reactor (SMART), a small to medium sized integral type Pressurized Water Reactor (PWR) has been developed in Korea. Now, SMART-P, a 1/5 scaled-down of the SMART, is being developed for the purpose of demonstrating the safety and performance of SMART design. The SMART-P is a first-of-a-kind reactor which is utilized for the research and development of a power reactor. Since the licensing process of such a reactor is not clearly specified in the current Atomic Energy Act, a comparative survey and analysis of domestic and foreign licensing processes for power and non-power reactors has been carried out to develop the rationale and technical basis for establishing the licensing process of such a reactor. The domestic and foreign licensing processes of power and non-power reactors have been surveyed and compared, including those of the U.S.A., Japan, France, U.K., Canada, and IAEA. The general trends in nuclear reactor classification, licensing procedures, regulatory technical requirements, and other licensing requirements and regulations have been investigated. The results of this study will be used as the rationale and technical basis for establishing the licensing process of reactors at development stage such as SMART-P

Neutral-beam systems for magnetic-fusion reactors

International Nuclear Information System (INIS)

Fink, J.H.

1981-01-01

Neutral beams for magnetic fusion reactors are at an early stage of development, and require considerable effort to make them into the large, reliable, and efficient systems needed for future power plants. To optimize their performance to establish specific goals for component development, systematic analysis of the beamlines is essential. Three ion source characteristics are discussed: arc-cathode life, gas efficiency, and beam divergence, and their significance in a high-energy neutral-beam system is evaluated

Safety aspects of nuclear plant licensing in Canada

International Nuclear Information System (INIS)

Jennekens, J.H.F.

1975-01-01

The legislative authority is laid down in the Atomic Energy Control Act, 1946, declaring atomic energy a matter of national interest and establishing the Atomic Energy Control Board (AECB) as the competent body for regulating all aspects of atomic energy. The Act also vests a Minister designated by the Government with research and exploitation functions; thus, by Ministerial order, Atomic Energy of Canada Limited was established in 1952 as a State-owned company. The Nuclear Liability Act, 1970, channels all liability for nuclear damage to the operator of a nuclear installation and requires him to obtain insurance in the amount of $75 million, part of which may be re-insured by the Government. The licensing requirements comprise the issuance of a site approval, a construction licence and an operating licence. The AECB is assisted in its licensing functions by its Nuclear Plant Licensing Directorate and by the Reactor Safety Advisory Committee co-operating with each other in making extensive safety assessments of a licence application. A site evaluation report, a preliminary safety report and a final safety report are required in relation to the siting, construction and operation of a nuclear power plant. The Canadian reactor safety philosophy is based on the concept of defence in depth, implemented through a multi-step approach, which includes avoidance of malfunctions, provision of special safety systems, periodic inspection and testing, and avoidance of human errors. Specific criteria and principles have evolved in applying this basic safety philosophy and radiation protection standards are derived from international recommendations. Stringent control is exercised over the management of radioactive waste and management facilities must meet the engineering and procedural requirements of AECB before they can be placed in operation. (author)

Better Demand Signal, Better Decisions? Evaluation of Big Data in a Licensed Remanufacturing Supply Chain with Environmental Risk Considerations.

Science.gov (United States)

Niu, Baozhuang; Zou, Zongbao

2017-08-01

Big data ability helps obtain more accurate demand signal. However, is better demand signal always beneficial for the supply chain parties? To answer this question, we investigate a remanufacturing supply chain (RSC), where demand uncertainty is significant, and the value to reduce environmental risk is large. Specifically, we focus on a licensed RSC comprising an original equipment manufacturer (OEM) and a third-party remanufacturer (3PR). The latter pays a unit license fee to the former, and can be risk averse to the demand of remanufactured products. We show that the OEM and the risk-neutral 3PR always have incentives to improve their big data abilities to increase their profits. However, when the 3PR is risk averse, big data might hurt its profit: the value of big data is positive if its demand signal accuracy is sufficiently low. Interestingly, we find that while information sharing hurts the 3PR, it benefits the OEM as well as the supply chain. Thus, if costly information sharing is allowed, a win-win situation can be achieved. We also find that information sharing generates more valuation when the 3PR is risk averse than that when the 3PR is risk neutral. More importantly, we find that the 3PR's risk attitude and demand signal accuracy can significantly mitigate the negative environmental impact (measured by the amount of the waste): (1) the more risk neutral the 3PR is, the better the environment is; (2) the more accurate demand signal is, the better the environment is. © 2017 Society for Risk Analysis.

Licensing of MAPLE reactors in Canada

International Nuclear Information System (INIS)

Lee, A.G.; Labrie, J.P.; Langman, V.J.

1999-01-01

Full text: The Operating Licence for a MAPLE reactor (i.e., a 10 MW(th), pool-type reactor), has been approved by the Atomic Energy Control Board (AECB) on August 16th, 1999. This Operating Licence has been obtained within three years of the initiation of the MDS Nordion Medical Isotopes Reactor (MMIR) project, which entails the design, construction and commissioning of two 10 MW MAPLE reactors at AECL's Chalk River Laboratories. The scope and nature of the information required by the AECB, the licensing process and highlights of the events which led to successfully obtaining the Operating Licence for the MAPLE reactor are discussed. These discussions address all phases of the licensing process (i.e., the environmental assessment in support of siting, the Preliminary Safety Analysis Report, PSAR, in support of design, procurement and construction, the Final Safety Analysis Report, FSAR, in support of commissioning and operations, and the development of suitable quality assurance subprograms for each phase). An overview of some of the unique technical aspects associated with the MAPLE reactors, and how they have been addressed during the licensing process are also provided (e.g., applying CSA N285.0, General Requirements for Pressure-Retaining Systems and Components in CANDU Nuclear Power Plants, to a small, low pressure, low temperature research reactor, confirmation of the performance of the driver fuel via laboratory and/or in-reactor testing, validation of the computer codes used to perform the safety analyses, critical parameter uncertainty assessment, full scale hydraulic testing of the performance of the design, fuel handling, human factors validation, operator training and certification). (author)

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...

ICAN: High power neutral beam generation

International Nuclear Information System (INIS)

Moustaizis, S.D.; Lalousis, P.; Perrakis, K.; Auvray, P.; Larour, J.; Ducret, J.E.; Balcou, P.

2015-01-01

During the last few years there is an increasing interest on the development of alternative high power new negative ion source for Tokamak applications. The proposed new neutral beam device presents a number of advantages with respect to: the density current, the acceleration voltage, the relative compact dimension of the negative ion source, and the coupling of a high power laser beam for photo-neutralization of the negative ion beam. Here we numerically investigate, using a multi- fluid 1-D code, the acceleration and the extraction of high power ion beam from a Magnetically Insulated Diode (MID). The diode configuration will be coupled to a high power device capable of extracting a current up to a few kA with an accelerating voltage up to MeV. An efficiency of up to 92% of the coupling of the laser beam, is required in order to obtain a high power, up to GW, neutral beam. The new high energy, high average power, high efficiency (up to 30%) ICAN fiber laser is proposed for both the plasma generation and the photo-neutralizer configuration. (authors)

76 FR 45695 - Notice and Recordkeeping for Use of Sound Recordings Under Statutory License

Science.gov (United States)

2011-08-01

... operating under these licenses are required to, among other things, pay royalty fees and report to copyright... LIBRARY OF CONGRESS Copyright Royalty Board 37 CFR Parts 370 and 382 [Docket No. RM 2011-5] Notice and Recordkeeping for Use of Sound Recordings Under Statutory License AGENCY: Copyright Royalty Board...

6 CFR 37.19 - Machine readable technology on the driver's license or identification card.

Science.gov (United States)

2010-01-01

... 6 Domestic Security 1 2010-01-01 2010-01-01 false Machine readable technology on the driver's..., Verification, and Card Issuance Requirements § 37.19 Machine readable technology on the driver's license or identification card. For the machine readable portion of the REAL ID driver's license or identification card...

A licensing discussion: SMRs in Canada

International Nuclear Information System (INIS)

De Vos, M.

2013-01-01

The CNSC (Canadian AECB) is ready to regulate Small Modular Reactors (SMR) facilities in Canada. The CNSC is well situated to engage with proponents of SMR reactors in design reviews or licensing discussions. A risk-informed (graded) approach is possible in many instances for reactors but it is not a relaxation of requirements. The vendor design review process helps reduce regulatory risks by encouraging early engagement.

32 CFR 746.7 - Limited exclusive license.

Science.gov (United States)

2010-07-01

... the market and recoup his reasonable costs in so doing. (4) The license shall require the licensee to... within a longer period as approved by the Chief of Naval Research, and to continue to make the benefits... expend a specified minimum amount of money and/or take other specified actions, within a specified period...

Siting Practices and Site Licensing Process for New Reactors in Canada

International Nuclear Information System (INIS)

Vos, Marcel de

2011-01-01

'Siting' in Canada is composed of Site Evaluation and Site Selection. As outlined in CNSC Regulatory Document RD-346 Site Evaluation for New Nuclear Power Plants (based on IAEA NS-R-3), prior to the triggering of the Environmental Assessment (EA) and licensing processes, the proponent is expected to use a robust process to characterize proposed sites over the full life cycle of the facility, and then develop a fully documented defense of the site selection case. This case forms the backbone for submissions in support of the EA and the application for a License to Prepare Site which will be reviewed by the CNSC and other applicable federal authorities. The Environmental Assessment process and License to Prepare Site in Canada do not require a proponent to select a specific design; however, CNSC does not accept a 'black box' approach to siting. CNSC balances the level of design information required with the extent of safety assurance desired for any designs being contemplated for the proposed site. Nevertheless, the design information submitted must be sufficient to justify the site as suitable for all future licensing stages. The depth of plant design information contributes significantly to the credibility of the applicant's case for both the EA and application for License to Prepare Site. The review process utilizes an assessment plan with defined review stages and timelines. The outcome of these reviews is a series of recommendations to a federal government appointed Joint Review Panel (which also serves as a panel of the 'Commission') which, following public hearings, renders a decision regarding the EA, and subsequently, the application for a License to Prepare Site. (author)

Nitrogen-neutrality: a step towards sustainability

Science.gov (United States)

Leip, Adrian; Leach, Allison; Musinguzi, Patrick; Tumwesigye, Trust; Olupot, Giregon; Tenywa, John Stephen; Mudiope, Joseph; Hutton, Olivia; Cordovil, Claudia M. d. S.; Bekunda, Mateete; Galloway, James

2014-11-01

We propose a novel indicator measuring one dimension of the sustainability of an entity in modern societies: Nitrogen-neutrality. N-neutrality strives to offset Nr releases an entity exerts on the environment from the release of reactive nitrogen (Nr) to the environment by reducing it and by offsetting the Nr releases elsewhere. N-neutrality also aims to increase awareness about the consequences of unintentional releases of nitrogen to the environment. N-neutrality is composed of two quantified elements: Nr released by an entity (e.g. on the basis of the N footprint) and Nr reduction from management and offset projects (N offset). It includes management strategies to reduce nitrogen losses before they occur (e.g., through energy conservation). Each of those elements faces specific challenges with regard to data availability and conceptual development. Impacts of Nr releases to the environment are manifold, and the impact profile of one unit of Nr release depends strongly on the compound released and the local susceptibility to Nr. As such, N-neutrality is more difficult to conceptualize and calculate than C-neutrality. We developed a workable conceptual framework for N-neutrality which was adapted for the 6th International Nitrogen Conference (N2013, Kampala, November 2013). Total N footprint of the surveyed meals at N2013 was 66 kg N. A total of US 3050 was collected from the participants and used to offset the conference’s N footprint by supporting the UN Millennium Village cluster Ruhiira in South-Western Uganda. The concept needs further development in particular to better incorporate the spatio-temporal variability of impacts and to standardize the methods to quantify the required N offset to neutralize the Nr releases impact. Criteria for compensation projects need to be sharply defined to allow the development of a market for N offset certificates.

Nitrogen-neutrality: a step towards sustainability

International Nuclear Information System (INIS)

Leip, Adrian; Leach, Allison; Hutton, Olivia; Galloway, James; Musinguzi, Patrick; Tumwesigye, Trust; Olupot, Giregon; Stephen Tenywa, John; Mudiope, Joseph; Cordovil, Claudia M d S; Bekunda, Mateete

2014-01-01

We propose a novel indicator measuring one dimension of the sustainability of an entity in modern societies: Nitrogen-neutrality. N-neutrality strives to offset Nr releases an entity exerts on the environment from the release of reactive nitrogen (Nr) to the environment by reducing it and by offsetting the Nr releases elsewhere. N-neutrality also aims to increase awareness about the consequences of unintentional releases of nitrogen to the environment. N-neutrality is composed of two quantified elements: Nr released by an entity (e.g. on the basis of the N footprint) and Nr reduction from management and offset projects (N offset). It includes management strategies to reduce nitrogen losses before they occur (e.g., through energy conservation). Each of those elements faces specific challenges with regard to data availability and conceptual development. Impacts of Nr releases to the environment are manifold, and the impact profile of one unit of Nr release depends strongly on the compound released and the local susceptibility to Nr. As such, N-neutrality is more difficult to conceptualize and calculate than C-neutrality. We developed a workable conceptual framework for N-neutrality which was adapted for the 6th International Nitrogen Conference (N2013, Kampala, November 2013). Total N footprint of the surveyed meals at N2013 was 66 kg N. A total of US$ 3050 was collected from the participants and used to offset the conference’s N footprint by supporting the UN Millennium Village cluster Ruhiira in South-Western Uganda. The concept needs further development in particular to better incorporate the spatio-temporal variability of impacts and to standardize the methods to quantify the required N offset to neutralize the Nr releases impact. Criteria for compensation projects need to be sharply defined to allow the development of a market for N offset certificates. (paper)

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

10 CFR 51.22 - Criterion for categorical exclusion; identification of licensing and regulatory actions eligible...

Science.gov (United States)

2010-01-01

... requirements. (11) Issuance of amendments to licenses for fuel cycle plants and radioactive waste disposal.... (xii) Acceptance of packaged radioactive wastes from others for transfer to licensed land burial... the following types of activities: (i) Distribution of radioactive material and devices or products...

EVA Development and Verification Testing at NASA's Neutral Buoyancy Laboratory

Science.gov (United States)

Jairala, Juniper C.; Durkin, Robert; Marak, Ralph J.; Sipila, Stepahnie A.; Ney, Zane A.; Parazynski, Scott E.; Thomason, Arthur H.

2012-01-01

As an early step in the preparation for future Extravehicular Activities (EVAs), astronauts perform neutral buoyancy testing to develop and verify EVA hardware and operations. Neutral buoyancy demonstrations at NASA Johnson Space Center's Sonny Carter Training Facility to date have primarily evaluated assembly and maintenance tasks associated with several elements of the International Space Station (ISS). With the retirement of the Shuttle, completion of ISS assembly, and introduction of commercial players for human transportation to space, evaluations at the Neutral Buoyancy Laboratory (NBL) will take on a new focus. Test objectives are selected for their criticality, lack of previous testing, or design changes that justify retesting. Assembly tasks investigated are performed using procedures developed by the flight hardware providers and the Mission Operations Directorate (MOD). Orbital Replacement Unit (ORU) maintenance tasks are performed using a more systematic set of procedures, EVA Concept of Operations for the International Space Station (JSC-33408), also developed by the MOD. This paper describes the requirements and process for performing a neutral buoyancy test, including typical hardware and support equipment requirements, personnel and administrative resource requirements, examples of ISS systems and operations that are evaluated, and typical operational objectives that are evaluated.

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)

Licensing fees in the district heating industry; Gestattungsentgelte in der Fernwaermewirtschaft

Energy Technology Data Exchange (ETDEWEB)

Fricke, Norman [Jena Univ. (Germany)

2009-10-15

By means of licensing agreements municipalities grant the right to the district heating suppliers to use their properties with or without fees for the construction of district heating pipelines. Contrary to the power industry or gas industry, this type of contract is not regulated by special legal and price-legal regulations. Often an uncertainty exists whether and in which amount the municipalities may require a return for the right of utilization. In particular, this is valid if municipalities make the extension of discontinued licensing agreements dependent on the agreement of higher license fees. The general review under consideration reports on any legal limits of the amount of the licence fees. At the same time, a reference to licence fees in the power sector and gas sector is performed. In addition, the author reports on the law historical and law political background of license fees.

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

Optimized baffle and aperture placement in neutral beamlines

International Nuclear Information System (INIS)

Stone, R.; Duffy, T.; Vetrovec, J.

1983-01-01

Most neutral beamlines contain an iron-core ion-bending magnet that requires shielding between the end of the neutralizer and this magnet. This shielding allows the gas pressure to drop prior to the beam entering the magnet and therefore reduces beam losses in this drift region. We have found that the beam losses can be reduced even further by eliminating the iron-core magnet and the magnetic shielding altogether. The required bending field can be supplied by current coils without the iron poles. In addition, placement of the baffles and apertures can affect the cold gas entering the plasma region and the losses in the neutral beam due to re-ionization. In our study we varied the placement of the baffles, which determine the amount of pumping in each chamber, and the apertures, which determine the beam loss. Our results indicate that a baffle/aperture configuration can be set for either minimum cold gas into the plasma region or minimum beam losses, but not both

6 CFR 37.17 - Requirements for the surface of the driver's license or identification card.

Science.gov (United States)

2010-01-01

... Driver's license or identification card number. This cannot be the individual's SSN, and must be unique... University Street, Montreal, Quebec, Canada H3C 5H7, e-mail: [email protected] You may inspect a copy of the...

Report of the Task Force on bonding and perpetual care of nuclear licensed activities

International Nuclear Information System (INIS)

Snellings, D.D. Jr.

1975-01-01

The primary concern was to consider the bonding and perpetual care requirements of state-licensed shallow land burial sites used for the disposal of radioactive wastes. The specific charge of the task force was to examine in detail the requirements for establishing bonding and perpetual care programs for all types of licensed nuclear activities and to report the findings of the task force as guidance to assist states in program development. Goals and recommendations of the task force are discussed

ITER neutral beam system US conceptual design

International Nuclear Information System (INIS)

Purgalis, P.

1990-09-01

In this document we present the US conceptual design of a neutral beam system for International Thermonuclear Experimental Reactor (ITER). The design incorporates a barium surface conversion D - source feeding a linear array of accelerator channels. The system uses a dc accelerator with electrostatic quadrupoles for strong focusing. A high voltage power supply that is integrated with the accelerator is presented as an attractive option. A gas neutralizer is used and residual ions exiting the neutralizer are deflected to water-cooled dumps. Cryopanels are located at the accelerator exit to pump excess gas from the source and the neutralizer, and in the ion dump cavity to pump re-neutralized ions and neutralizer gas. All the above components are packaged in compact identical, independent modules which can be removed for remote maintenance. The neutral beam system delivers 75 MW of DO at 1.3 MeV, into three ports with a total of 9 modules arranged in stacks of three modules per port . To increase reliability each module is designed to deliver up to 10 MW; this allows eight modules operating at partial capacity to deliver the required power in the event one module is out of service, and provides 20% excess capacity to improve availability. Radiation protection is provided by shielding and by locating critical components in the source and accelerator 46.5 m from the torus centerline. Neutron shielding in the drift duct and neutralizer provides the added feature of limiting conductance and thus reducing gas flow to and from the torus

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

Operator licensing examination standards for power reactors. Interim revision 8

International Nuclear Information System (INIS)

1997-01-01

These examination standards are intended to assist NRC examiners and facility licensees to better understand the processes associated with initial and requalification examinations. The standards also ensure the equitable and consistent administration of examinations for all applicants. These standards are for guidance purposes and are not a substitute for the operator licensing regulations (i.e., 10 CFR Part 55), and they are subject to revision or other changes in internal operator licensing policy. This interim revision permits facility licensees to prepare their initial operator licensing examinations on a voluntary basis pending an amendment to 10 CFR Part 55 that will require facility participation. The NRC intends to solicit comments on this revision during the rulemaking process and to issue a final Revision 8 in conjunction with the final rule

Development of KSTAR Neutral Beam Heating System

Energy Technology Data Exchange (ETDEWEB)

Oh, B. H.; Song, W. S.; Yoon, B. J. (and others)

2007-10-15

The prototype components of a neutral beam injection (NBI) system have been developed for the KSTAR, and a capability of the manufactured components has been tested. High power ion source, acceleration power supply, other ion source power supplies, neutralizer, bending magnet for ion beam separation, calorimeter, and cryo-sorption pump have been developed by using the domestic technologies and tested for a neutral beam injection of 8 MW per beamline with a pulse duration of 300 seconds. The developed components have been continuously upgraded to achieve the design requirements. The development technology of high power and long pulse neutral beam injection system has been proved with the achievement of 5.2 MW output for a short pulse length and 1.6 MW output for a pulse length of 300 seconds. Using these development technologies, the domestic NB technology has been stabilized under the development of high power ion source, NB beamline components, high voltage and current power supplies, NB diagnostics, NB system operation and control.

Shutdown requirements in licensing of research reactors and consequences for operation

International Nuclear Information System (INIS)

Roegler, H.-J.; Stein, J.

1983-01-01

Most countries start their nuclear life with the setup of a research reactor. Most countries have at this time no licensing authority established which can act on existing laws, rules and regulations. Thus, most countries have during this starting phase to rely on the regulations fixed by international institutions such as the IAEA (or by national institutions as the former NRC in US, which happens to take place more often from reasons below). This implies a specific responsibility for international regulations since they have to be very clear and unique. Moreover they have to be applicable to all plants they are set forth for and they have to give no unavoidable restrictions on the use of the plant. Additionally some recheck of the rules based on national rules in forth will be of help. The enrichment reduction for research reactors gave frequent cause to look at the existing IAEA-publications for research reactors. They are laid down in the safety series no. 35 edited 1971. I will only discuss here specific parts of these considerations or requirements. Since the authors' personal impressions are that the published considerations are neither that clear nor that less restrictive as necessary the subsequent discussion is carried out. One of the confusing points of the existing IAEA-regulations is the lengthy discussion of reactivity considerations for critical assemblies first, no similar separate discussion for research reactors and a second discussion titled 'control-rod considerations' under the main title 'considerations applying to critical assemblies and research reactor'. This discussion will be restricted to the latter since the critical assemblies with their timely Constance of maximum excess reactivity do not present any problem for all shut-down conditions

Licensing aspects of the NPP Temelin IandC replacement project

International Nuclear Information System (INIS)

Karpeta, C.

1997-01-01

The objections raised against the original design of the instrumentation and control system of the Temelin nuclear power plant are summarized. The nuclear regulatory environment of the Czech Republic is described; the activities of the State Office for Nuclear Safety (SONS) are highlighted. The requirements underlying the licensing of the Temelin IandC replacement project are discussed in some detail. The licensing process adopted by SONS is to a certain degree computer-aided. A database has been developed by SONS; the three-layer structure of the database is described. (A.K.)

Atomic Safety and Licensing Board Panel Biennial Report, Fiscal Years 1993--1994. Volume 6

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-08-01

In Fiscal Year 1993, the Atomic Safety and Licensing Board Panel (``the Panel``) handled 30 proceedings. In Fiscal Year 1994, the Panel handled 36 proceedings. The cases addressed issues in the construction, operation, and maintenance of commercial nuclear power reactors and other activities requiring a license form the Nuclear Regulatory Commission. This report sets out the Panel`s caseload during the year and summarizes, highlight, and analyzes how the wide- ranging issues raised in those proceedings were addressed by the Panel`s judges and licensing boards.

Atomic Safety and Licensing Board Panel Biennial Report, Fiscal Years 1993--1994. Volume 6

International Nuclear Information System (INIS)

1995-08-01

In Fiscal Year 1993, the Atomic Safety and Licensing Board Panel (''the Panel'') handled 30 proceedings. In Fiscal Year 1994, the Panel handled 36 proceedings. The cases addressed issues in the construction, operation, and maintenance of commercial nuclear power reactors and other activities requiring a license form the Nuclear Regulatory Commission. This report sets out the Panel's caseload during the year and summarizes, highlight, and analyzes how the wide- ranging issues raised in those proceedings were addressed by the Panel's judges and licensing boards

A carrier-based approach for overmodulation of three-level neutral-point-lamped inverter with zero neutral-point current

DEFF Research Database (Denmark)

Maheshwari, Ram Krishan; Munk-Nielsen, Stig; Busquets-Monge, S.

2012-01-01

In a voltage source inverter, overmodulation is required to extend the range of operation and enhance the dc-link voltage utilization. A carrier-based implementation of a modulation strategy for the three-level neutral-point-clamped inverter is proposed for the overmodulation region. The modulation...... strategy ensures zero average neutral-point current in a switching period. A newly proposed boundary compression is used to regulate the dc-link voltage at all operating points. A description of the algorithm to implement the modulation strategy is also presented. The main advantage of the proposed...

Investment issues in nuclear plant license renewal

International Nuclear Information System (INIS)

Eynon, R.T.

1999-01-01

A method that determines the operating lives for existing nuclear power plants is discussed. These assumptions are the basis for projections of electricity supply through 2020 reported in the Energy Information Administration's (EIA's) Annual Energy Outlook 1999. To determine if plants will seek license renewal, one must first determine if they will be operating to the end of their current licenses. This determination is based on an economic test that assumes an investment of $150/kW will be required after 30 yr of operation for plants with older designs. This expenditure is intended to be equivalent to the cost that would be associated with any of several needs such as a one0time investment to replace aging equipment (steam generators), a series of investments to fix age-related degradation, increases in operating costs, or costs associated with decreased performance. This investment is compared with the cost of building and operating the lowest-cost new plant over the same 10-yr period. If a plant fails this test, it is assumed to be retired after 30 yr of service. All other plants are then considered candidates for license renewal. The method used to determine if it is economic to apply for license renewal and operate plants for an additional 20 yr is to assume that plants face an investment of $250 million after 40 yr of operation to refurbish aging components. This investment is compared with the lowest-cost new plant alternative evaluated over the same 20 yr that the nuclear plant would operate. If the nuclear plant is the lowest cost option, it is projected to continue to operate. EIA projects that it would be economic to extend the operating licenses for 3.7 GW of capacity (6 units)

ITER neutral beam system

International Nuclear Information System (INIS)

Mondino, P.L.; Di Pietro, E.; Bayetti, P.

1999-01-01

The Neutral Beam (NB) system for the International Thermonuclear Experimental Reactor (ITER) has reached a high degree of integration with the tokamak and with the rest of the plant. Operational requirements and maintainability have been considered in the design. The paper considers the integration with the tokamak, discusses design improvements which appear necessary and finally notes R and D progress in key areas. (author)

NRC licensing of uranium enrichment plants

International Nuclear Information System (INIS)

Moran, B.W.

1991-01-01

The US Nuclear Regulatory Commission (NRC) is preparing a rule making that establishes the licensing requirements for low-enriched uranium enrichment plants. Although implementation of this rule making is timed to correspond with receipt of a license application for the Louisiana Energy Services centrifuge enrichment plant, the rule making is applicable to all uranium enrichment technologies. If ownership of the US gaseous diffusion plants and/or atomic vapor laser isotope separation is transferred to a private or government corporation, these plants also would be licensable under the new rule making. The Safeguards Studies Department was tasked by the NRC to provide technical assistance in support of the rule making and guidance preparation process. The initial and primary effort of this task involved the characterization of the potential safeguards concerns associated with a commercial enrichment plant, and the licensing issues associated with these concerns. The primary safeguards considerations were identified as detection of the loss of special nuclear material, detection of unauthorized production of material of low strategic significance, and detection of production of uranium enriched to >10% 235 U. The primary safeguards concerns identified were (1) large absolute limit of error associated with the material balance closing, (2) the inability to shutdown some technologies to perform a cleanout inventory of the process system, and (3) the flexibility of some technologies to produce higher enrichments. Unauthorized production scenarios were identified for some technologies that could prevent conventional material control and accounting programs from detecting the production and removal of 5 kg 235 U as highly enriched uranium. Safeguards techniques were identified to mitigate these concerns

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.

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).

N-linked glycosylation of SV2 is required for binding and uptake of botulinum neurotoxin A

Science.gov (United States)

Yao, Guorui; Zhang, Sicai; Mahrhold, Stefan; Lam, Kwok-ho; Stern, Daniel; Bagramyan, Karine; Perry, Kay; Kalkum, Markus; Rummel, Andreas; Dong, Min; Jin, Rongsheng

2016-01-01

Botulinum neurotoxin serotype A1 (BoNT/A1) is one of the most dangerous potential bioterrorism agents, and exerts its action by invading motoneurons. It is also a licensed drug widely used for medical and cosmetic applications. Here we report a 2.0 Å resolution crystal structure of BoNT/A1 receptor-binding domain in complex with its neuronal receptor, the glycosylated human SV2C. We find that the neuronal tropism of BoNT/A1 requires recognition of both the peptide moiety and an N-linked glycan on SV2. This N-glycan—conserved in all SV2 isoforms across vertebrates—is essential for BoNT/A1 binding to neurons and its potent neurotoxicity. The glycan-binding interface on SV2 is targeted by a human BoNT/A1-neutralizing antibody currently licensed as an anti-botulism drug. Our studies reveal a new paradigm of host-pathogen interactions, in which pathogens exploit conserved host post-translational modifications to achieve highly specific receptor binding while also tolerating genetic changes across multiple isoforms of receptors. PMID:27294781

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

Westinghouse AP1000 licensing maturity

International Nuclear Information System (INIS)

Schulz, T.; Vijuk, R.P.

2005-01-01

The Westinghouse AP1000 Program is aimed at making available a nuclear power plant that is economical in the U.S deregulated electrical power industry in the near-term. The AP1000 is two-loop 1000 MWe pressurizer water reactor (PWR). It is an up rated version of the AP600. The AP1000 uses passive safety systems to provide significant and measurable improvements in plant simplification, safety, reliability, investment protection and plant costs. The AP1000 uses proven technology, which builds on over 35 years of operating PWR experience. The AP1000 received Final Design Approval by the United States Nuclear Regulatory Commission (U.S. NRC) in September 2004. The AP1000 meets the US utility requirements. The AP1000 and its sister plant the AP600 have gone through a very through and complete licensing review. This paper describes the U.S. NRC review efforts of both the AP600 and the AP1000. The detail of the review and the independent calculations, evaluations and testing is discussed. The AP600 licensing documentation was submitted in 1992. The U.S. NRC granted Final Design Approval in 1999. During the intervening 7 years, the U.S. NRC asked thousands of questions, performed independent safety analysis, audited Westinghouse calculations and analysis, and performed independent testing. The more significant areas of discussion will be described. For the AP1000 Westinghouse first engaged the U.S. NRC in pre-certification discussions to define the extent of the review required, since the design is so similar to the AP600. The AP1000 licensing documentation was submitted in March 2002. The U.S. NRC granted Final Design Approval in September 2004. During the intervening 2 1/2 years, the U.S. NRC asked hundreds of questions, performed independent safety analysis, audited Westinghouse calculations and analysis, and performed independent testing. The more significant areas of discussion will be described. The implications of this review and approval on AP1000 applications in

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

Neutral pumping rates for a next step tokamak ignition device

International Nuclear Information System (INIS)

Galambos, J.D.; Peng, Y.K.M.; Heifetz, D.

1985-01-01

Neutral pumping rates are calculated for pump-limiter and divertor options of a next step tokamak ignition device using a method that accounts for the coupled effects of neutral transport and plasma transport. For both pump limiters and divertors the plasma flow into the channel surrounding the neutralizer plate is greatly reduced by the neutral recycling. The fraction of this flow that is pumped can be large (>50%) but in general is dependent on the particular geometry and plasma conditions. It is estimated that pumping speeds greater than or approximately 10 5 L/s are adequate for the exhaust requirements in the pump-limiter and the divertor cases

Advanced neutral-beam technology

International Nuclear Information System (INIS)

Berkner, K.H.

1980-09-01

Extensive development will be required to achieve the 50- to 75-MW, 175- to 200-keV, 5- to 10-sec pulses of deuterium atoms envisioned for ETF and INTOR. Multi-megawatt injector systems are large (and expansive); they consist of large vacuum tanks with many square meters of cryogenic pumping panels, beam dumps capable of dissipating several megawatts of un-neutralized beam, bending magnets, electrical power systems capable of fast turnoff with low (capacity) stored energy, and, of course, the injector modules (ion sources and accelerators). The technology requirements associated with these components are described

Potent neutralization of hepatitis A virus reveals a receptor mimic mechanism and the receptor recognition site.

Science.gov (United States)

Wang, Xiangxi; Zhu, Ling; Dang, Minghao; Hu, Zhongyu; Gao, Qiang; Yuan, Shuai; Sun, Yao; Zhang, Bo; Ren, Jingshan; Kotecha, Abhay; Walter, Thomas S; Wang, Junzhi; Fry, Elizabeth E; Stuart, David I; Rao, Zihe

2017-01-24

Hepatitis A virus (HAV) infects ∼1.4 million people annually and, although there is a vaccine, there are no licensed therapeutic drugs. HAV is unusually stable (making disinfection problematic) and little is known of how it enters cells and releases its RNA. Here we report a potent HAV-specific monoclonal antibody, R10, which neutralizes HAV infection by blocking attachment to the host cell. High-resolution cryo-EM structures of HAV full and empty particles and of the complex of HAV with R10 Fab reveal the atomic details of antibody binding and point to a receptor recognition site at the pentamer interface. These results, together with our observation that the R10 Fab destabilizes the capsid, suggest the use of a receptor mimic mechanism to neutralize virus infection, providing new opportunities for therapeutic intervention.

The regulatory review of construction license application and the supporting safety case

International Nuclear Information System (INIS)

Heinonen, Jussi

2014-01-01

Finland is one of the foremost countries in the world in developing the disposal of spent fuel. The construction license application for the Olkiluoto spent fuel disposal facility was submitted to the authorities at the end of 2012 and the facility is expected to start operation around 2020. This has been a long-term project with over 30 years of parallel development of the repository project and the regulatory approach to spent fuel management. In 1983 the government made a strategic decision on the objectives and target time schedule for the research, development and technical planning of nuclear waste management. While an export and international disposal solution was still the preferred option, this decision required the licensees without this possibility to prepare for disposal in Finland and it also gave the time line for the milestones on the way to an operating disposal facility by 2020. The licensing procedure for a disposal facility has several steps that are similar to all nuclear facilities in Finland and are defined in Nuclear Energy Act and Decree (1987, 1988). These licensing steps are: - Decision-in-principle is required for a nuclear facility having considerable general significance. This is essentially a political decision: the government decides if the construction project is in line with the overall good of society. The decision can be applied for one or more sites, the host municipality has a veto right and the parliament has the choice of ratifying or not ratifying the decision. - Construction license is granted by the government and authorises the construction of the disposal facility. The actual construction is regulated by STUK and includes several review and approval steps, hold points and viewpoints. - Operational license is granted by the government and authorises the operation of the facility for a certain period. The operational license is needed before nuclear waste can be disposed. The first step in the licensing process was reached

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

International Nuclear Information System (INIS)

1999-03-01

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

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-03-01

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

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...

The licensing practice on nuclear power plants in Korea

International Nuclear Information System (INIS)

Moon, S. P.

1994-01-01

The evolution of Korean regulatory system has tightly coupled with development ot Korean nuclear power program. The nuclear power plant licensing has become a major regulatory function of the government when the construction of the Kori NPP Unit 1 started in early 1970s. During this period, domestic laws and regulations applicable to the licensing of NPP were not yet fully developed. Therefore the vendor countries' laws and regulations were applied as mandatory requirement. Beginning in the early 19808, component approach was used and contracts were awarded separately for major components of the plants, thus enabling more domestic industries to participate in the projects. The two-step licensing system was incorporated into the law. In the third phase from 1987, major efforts have been concentrated on the maximum participation of local industries. The overriding priority for selecting suppliers was the condition of higher nuclear technology transfer to Korea. The Korea Institute of Nuclear Safety (KINS) was established in 1990 as an independent regulatory expert organization

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...

Strategic Basis for License Application Planning for a Potential Yucca Mountain Repository

International Nuclear Information System (INIS)

Newberry, C. M.; Brocoum, S. J.; Gamble, R. P.; Murray, R. C.; Cline, M.

2002-01-01

If Yucca Mountain, Nevada is designated as the site for development of a geologic repository for disposal of spent nuclear fuel and high-level radioactive waste, the Department of Energy (DOE) must obtain Nuclear Regulatory Commission (NRC) approval first for repository construction, then for an operating license, and, eventually, for repository closure and decommissioning. The licensing criteria defined in Code of Federal Regulations, Title 10, Part 63 (10 CFR Part 63) establish the basis for these NRC decisions. Submittal of a license application (LA) to the NRC for authorization to construct a repository at the Yucca Mountain site is, at this point, only a potential future action by the DOE. The policy process defined in the Nuclear Waste Policy Act (NWPA), as amended, for recommendation and designation of Yucca Mountain as a repository site makes it difficult to predict whether or when the site might be designated. The DOE may only submit a LA to the NRC if the site designation takes effect. In spite of this uncertainty, the DOE must take prudent and appropriate action now, and over the next several years, to prepare for development and timely submittal of a LA. This is particularly true given the need for the DOE to develop, load, and certify the operation of its electronic information system to provide access to its relevant records as part of the licensing support network (LSN) in compliance with NRC requirements six months prior to LA submittal. The DOE must also develop a LA, which is a substantially different document from those developed to support a Site Recommendation (SR) decision. The LA must satisfy NRC licensing criteria and content requirements, and address the acceptance criteria defined by the NRC in its forthcoming Yucca Mountain Review Plan (YMRP). The content of the LA must be adequate to facilitate NRC acceptance and docketing for review, and the LA and its supporting documents must provide the documented basis for the NR C findings required

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.

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....

76 FR 59410 - Government-Owned Inventions; Availability for Licensing

Science.gov (United States)

2011-09-26

...: Licensing information and copies of the U.S. patent applications listed below may be obtained by writing to...-402-0220. A signed Confidential Disclosure Agreement will be required to receive copies of the patent... to menopause, birth control, menstrual cycle/amenorrhea, fertility or endometriosis. Competitive...

Brand management of licensed innovation X

OpenAIRE

Hämäläinen, Tommy

2016-01-01

European start-up company has patented a packaging innovation concept for a certain the food product. The manufacturing and productization of the innovation will be licensed internationally for several participants. The Case Company is therefore interested to know what kind of opportunities and requirements potentially simultaneous strategic partnerships with licensees would mean for the brand of the innovation in theory and practice. The purpose of this thesis was to evaluate the current...

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...

Department of Energy interest and involvement in nuclear plant license renewal activities

International Nuclear Information System (INIS)

Bustard, Larry D.; Harrison, Dennis L.

1991-01-01

Recognizing the importance of nuclear license renewal to the nation's energy strategy, the Department of Energy (DOE) initiated a plant lifetime improvement program during 1985 to determine the feasibility of the license renewal option for US nuclear plants. Initial activities of the DOE program focused on determining whether there were technical and economic obstacles that might preclude or limit the successful implementation of the license renewal option. To make this determination, DOE co-sponsored with the Electric Power Research Institute (EPRI) 'pilot-plant' efforts by Virginia Electric Power and Northern States Power. Both pilot-plant efforts concluded that life extension is technically and economically feasible. In parallel with the pilot plant activities, DOE performed national economic studies that demonstrated the economic desirability of life extension. Having demonstrated the feasibility of life extension, DOE, in conjunction with EPRI, selected two lead plants to demonstrate the license renewal process. These lead plants are Yankees Atomic's Yankee Rowe facility and Northern States Power's Monticello facility. DOE also initiated activities to develop the technical and regulatory bases to support the license renewal process in the United States. These include (1) development of a methodology for identifying systems, structures, and components important to license renewal, (2) development of industry reports that describe industry-accepted approaches for license renewal of ten important classes of equipment, (3) development of technical basis to support license renewal, and (4) interaction/negotiation with the NRC through the Nuclear Management Resources Council (NUMARC) regarding appropriate regulatory requirements for license renewal. DOE has recently identified nuclear plant license renewal to be an important element of its National Energy Strategy. This paper summarizes the significant results, conclusions and ongoing activities of the DOE effort

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 ...

Licensing management system prototype system design

International Nuclear Information System (INIS)

Immerman, W.H.; Arcuni, A.A.; Elliott, J.M.; Chapman, L.D.

1983-11-01

This report is a design document for a prototype implementation of a licensing management system (LMS) as defined in SAND83-7080. It describes the concept of operations for full implementation of an LMS in accordance with the previously defined functional requirements. It defines a subset of a full LMS suitable for meeting prototype implementation goals, and proposes a system design for this subset. The report describes overall system design considerations consistent with, but more explicit than the general characteristics required by the LMS functional definition. A high level design is presented for just those functions selected for prototype implementation. The report also provides a data element dictionary describing the structured logical data elements required to implement the selected functions

Enforced Electrical Neutrality of the Color-Flavor Locked Phase

International Nuclear Information System (INIS)

Rajagopal, Krishna; Wilczek, Frank

2001-01-01

We demonstrate that quark matter in the color-flavor locked phase of QCD is rigorously electrically neutral, despite the unequal quark masses, and even in the presence of an electron chemical potential. As long as the strange quark mass and the electron chemical potential do not preclude the color-flavor locked phase, quark matter is automatically neutral. No electrons are required and none are admitted

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

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...

Tokamak Fusion Test Reactor neutral beam injection system vacuum chamber

International Nuclear Information System (INIS)

Pedrotti, L.R.

1977-01-01

Most of the components of the Neutral Beam Lines of the Tokamak Fusion Test Reactor (TFTR) will be enclosed in a 50 cubic meter box-shaped vacuum chamber. The chamber will have a number of unorthodox features to accomodate both neutral beam and TFTR requirements. The design constraints, and the resulting chamber design, are presented

Tast Force report on bonding and perpetual care of nuclear licensed activities

International Nuclear Information System (INIS)

Anon.

1975-01-01

Potential issues which should be considered prior to the adoption and implementation of a bonding or perpetual care program are examined. The following topics are discussed: problem definition; major processors; factors in setting the amount of a bond; waste handling licensees; ore refineries and mills; former AEC licensed facilities; other specific licenses; authority; states where it is deemed that amendment of existing statutes is necessary to authorize imposition of a bonding requirement for licenses; administration; and recommendations. The following appendices are included: summary of cost estimate to decontaminate the American Nuclear Company; report on 1974 national conference on radiation control workshop no. 3; suggested changes to state regulations; and suggested legislation for licensee bonding and perpetual care trust funds

Economics of license renewal in the U.S. - entergy's perspective

International Nuclear Information System (INIS)

Young, Garry G.

2003-01-01

License renewal of operating nuclear plants in the United States has become one of the most successful U.S. nuclear regulatory activities in the past few years. In 1995, the U.S. Nuclear Regulatory Commission (NRC) published a revised rule in 10 CFR Part 54 that provided the requirements for an operating nuclear plant to seek license renewal. At that time, many people believed that only a select few operating nuclear plants would pursue license renewal and that most plants would operate for no more than 40 years. By mid-2003, the owners of approximately 52% of the U.S. nuclear fleet of 103 operating nuclear plants have decided to pursue license renewal and more are expected to follow. This change in direction since 1995 can be attributed to the improving economics of U.S. nuclear power plant operation and to the improved regulatory process resulting from the 1995 revision to 10 CFR Part 54. In 2000, Entergy submitted a license renewal application for Arkansas Nuclear One, Unit 1 (ANO-1). This application was the third to be submitted to the NRC at a time when it was still unclear how successful the regulatory process might be. However, less than 17 months later, in June 2001, the NRC granted a renewed operating license for ANO-1 at a total cost of approximately $11 million. Due in part to the ANO-1 license renewal success, Entergy now has tentative plans to pursue license renewal for the entire fleet of operating nuclear power plants. Without license renewal, Entergy's current nuclear fleet capacity of approximately 9,000 MW(e) would begin to decline in 2012. With license renewal, Entergy's nuclear fleet capacity can remain in place until 2032. This projection does not include the expected improvements in capacity due to power uprate that is currently planned. The combination of power uprate and license renewal will add significant economic value to Entergy's nuclear fleet. One of the major factors in strong performance is capacity factor. In 1990, the average

Applying ecological models to communities of genetic elements: the case of neutral theory.

Science.gov (United States)

Linquist, Stefan; Cottenie, Karl; Elliott, Tyler A; Saylor, Brent; Kremer, Stefan C; Gregory, T Ryan

2015-07-01

A promising recent development in molecular biology involves viewing the genome as a mini-ecosystem, where genetic elements are compared to organisms and the surrounding cellular and genomic structures are regarded as the local environment. Here, we critically evaluate the prospects of ecological neutral theory (ENT), a popular model in ecology, as it applies at the genomic level. This assessment requires an overview of the controversy surrounding neutral models in community ecology. In particular, we discuss the limitations of using ENT both as an explanation of community dynamics and as a null hypothesis. We then analyse a case study in which ENT has been applied to genomic data. Our central finding is that genetic elements do not conform to the requirements of ENT once its assumptions and limitations are made explicit. We further compare this genome-level application of ENT to two other, more familiar approaches in genomics that rely on neutral mechanisms: Kimura's molecular neutral theory and Lynch's mutational-hazard model. Interestingly, this comparison reveals that there are two distinct concepts of neutrality associated with these models, which we dub 'fitness neutrality' and 'competitive neutrality'. This distinction helps to clarify the various roles for neutral models in genomics, for example in explaining the evolution of genome size. © 2015 John Wiley & Sons Ltd.

Neutral Beam Power System for TPX

International Nuclear Information System (INIS)

Ramakrishnan, S.; Bowen, O.N.; O'Conner, T.; Edwards, J.; Fromm, N.; Hatcher, R.; Newman, R.; Rossi, G.; Stevenson, T.; von Halle, A.

1993-01-01

The Tokamak Physics Experiment (TPX) will utilize to the maximum extent the existing Tokamak Fusion Test Reactor (TFTR) equipment and facilities. This is particularly true for the TFTR Neutral Beam (NB) system. Most of the NB hardware, plant facilities, auxiliary sub-systems, power systems, service infrastructure, and control systems can be used as is. The major changes in the NB hardware are driven by the new operating duty cycle. The TFTR Neutral Beam was designed for operation of the Sources for 2 seconds every 150 seconds. The TPX requires operation for 1000 seconds every 4500 seconds. During the Conceptual Design Phase of TPX every component of the TFTR NB Electrical Power System was analyzed to verify whether the equipment can meet the new operational requirements with our without modifications. The Power System converts 13.8 kV prime power to controlled pulsed power required at the NB sources. The major equipment involved are circuit breakers, auto and rectifier transformers surge suppression components, power tetrodes, HV Decks, and HVDC power transmission to sources. Thermal models were developed for the power transformers to simulate the new operational requirements. Heat runs were conducted for the power tetrodes to verify capability. Other components were analyzed to verify their thermal limitations. This paper describes the details of the evaluation and redesign of the electrical power system components to meet the TPX operational requirements

Licensing of advanced reactors: Status report and perspective

International Nuclear Information System (INIS)

King, T.

1988-01-01

In July, 1986, the U.S. Nuclear Regulatory Commission issued a Policy State on the Regulation of Advanced Nuclear Power Plants. As part of this policy, advanced reactor designers were encouraged to interact with NRC [Nuclear Regulatory Commission] early in the design process to obtain feedback regarding licensing requirements for advanced reactors. Accordingly, the staff has been interacting with the Department of Energy (DOE) and its contractors on the review of three advanced reactor conceptual designs: one modular high temperature gas-cooled reactor (MHTGR) and two liquid metal reactors (LMRs). This paper provides a status of the NRC review effort, describes the key policy and technical issues resulting from our review and provides the current status and approach to the development of licensing guidance on each

Licensing process for safety-critical software-based systems

Energy Technology Data Exchange (ETDEWEB)

Haapanen, P. [VTT Automation, Espoo (Finland); Korhonen, J. [VTT Electronics, Espoo (Finland); Pulkkinen, U. [VTT Automation, Espoo (Finland)

2000-12-01

. Many of the methods and tools needed in the licensing process are still under development and further research is needed to establish a flexible and cost effective process. Also the database for the assessment methods is still inadequate. Other recently published reports in OHA-report series handle the statistical reliability assessment (STUK-YTO-TR 119), usage models (STUK-YTO-TR 128), handling of programmable automation in plant PSA-studies (STUK-YTO-TR 129)and diversity requirements (STUK-YTO-TR 142).(orig.)

Licensing process for safety-critical software-based systems

International Nuclear Information System (INIS)

Haapanen, P.; Korhonen, J.; Pulkkinen, U.

2000-12-01

methods and tools needed in the licensing process are still under development and further research is needed to establish a flexible and cost effective process. Also the database for the assessment methods is still inadequate. Other recently published reports in OHA-report series handle the statistical reliability assessment (STUK-YTO-TR 119), usage models (STUK-YTO-TR 128), handling of programmable automation in plant PSA-studies (STUK-YTO-TR 129)and diversity requirements (STUK-YTO-TR 142).(orig.)

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

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

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

Positive ion portion of the LBL/LLL Neutral Beam Program

International Nuclear Information System (INIS)

Pyle, R.V.; Baker, W.R.; Anderson, O.A.

1978-06-01

The positive ion portion of the Neutral Beam Development Program at the Lawrence Berkeley (LBL) and Livermore (LLL) Laboratories has two purposes: (a) to carry out general research and development in a timely way to assure that users' needs can be met in principle, and (b) to carry out specific development for users. To meet the first requirement, we have programs to develop sources capable of producing beams with high (85%) atomic fractions, long pulse lengths (10 sec to DC), and at beam energies up to 150 keV. We are also pursuing the development of on-line computer diagnostics and controls, the sophisticated high-power electronics required by neutral beam systems, and energy recovery. To meet the second requirement, we are developing prototype source modules to meet the requirements of the TMX and MFTF experiments at Lawrence Livermore Laboratory, the TFTR experiment at the Princeton Plasma Physics Laboratory, and the Doublet III experiment at General Atomic Co. The Lawrence Laboratories are also constructing and will demonstrate at LBL a complete prototype neutral injection system for TFTR, and are designing a similar system for Doublet III

Velocity limitation of a neutral dust cloud colliding with a magnetized plasma

International Nuclear Information System (INIS)

Lehnert, B.

1986-08-01

The problem is considered of a cloud of neutral dust which moves into a cloud of static plasma which is confined in a magnetic field. Earlier experiments and theoretical analysis on critical velocity limitation by plasma-wall interaction suggest that such limitation also arises in the case of plasma-neutral dust interaction. Nevertheless further analysis is required to provide a full and clear picture of the interaction between plasma and neutral gas on one hand and plasma and neutral dust on the other. (author)

Development of Regulatory Technical Requirements for the Advanced Integral Type Research Reactor

International Nuclear Information System (INIS)

Jo, Jong Chull; Yune, Young Gill; Kim, Woong Sik; Kim, Hho Jung

2004-01-01

This paper presents the current status of the study on the development of regulatory technical requirements for the licensing review of an advanced integral type research reactor of which the license application is expected in a few years. According to the Atomic Energy Act of Korea, both research and education reactors are subject to the technical requirements for power reactors in the licensing review. But, some of the requirements may not be applicable or insufficient for the licensing reviews of reactors with unique design features. Thus it is necessary to identify which review topics or areas can not be addressed by the existing requirements and to develop the required ones newly or supplement appropriately. Through the study performed so far, it has been identified that the following requirements need to be developed newly for the licensing review of SMART-P: the use of proven technology, the interfacial facility, the non-safety systems, and the metallic fuels. The approach and basis for the development of each of the requirements are discussed. (authors)

78 FR 46255 - Revisions to Environmental Review for Renewal of Nuclear Power Plant Operating Licenses; Correction

Science.gov (United States)

2013-07-31

... Environmental Review for Renewal of Nuclear Power Plant Operating Licenses; Correction AGENCY: Nuclear... nuclear power plant. Compliance with the provisions of the rule is required by June 20, 2014. This... environmental effect of renewing the operating license of a nuclear power plant. This document is necessary to...

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...

IRIS project update: status of the design and licensing activities

International Nuclear Information System (INIS)

Petrovic, B.; Carelli, M.

2004-01-01

This paper presents an overview of the current status of the IRIS (International Reactor Innovative and Secure) project, focusing on the design and licensing activities. An update relative to the previous presentation at the 4th HND Conference is provided, highlighting some of the main accomplishments over the past two years. After successfully completing the conceptual design phase, IRIS is now finalizing the preliminary design as well. The pre-application licensing review with the U.S. NRC has been initiated in October of 2002. The safety-by-design approach and PRA-guided design open the possibility to aim for licensing not requiring off-site emergency response planning. Multiple single-unit and twin-unit site layouts have been developed within the ESP (Early Site Permit) program currently pursued by three U.S. power utilities. Desalination and district heating options have recently been added to the base design. Staggered construction schedules of multiple units may be applied to optimize cash-flow and minimize the required investment, making IRIS a financially attractive option, even for economies with limited investment capabilities. Because of its modularity, compatibility with smaller/medium grids, and enabling gradual build of new generating capacity matching the needs, IRIS has a large potential in the worldwide market.(author)

Climate Neutral Campus Key Terms and Definitions | Climate Neutral Research

Science.gov (United States)

Campuses | NREL Neutral Campus Key Terms and Definitions Climate Neutral Campus Key Terms and Definitions The term climate neutral evolved along with net zero and a number of other "green" and accuracy in these areas lets research campuses know exactly how close they are to climate

Initiatives in transport cask licensing

International Nuclear Information System (INIS)

Patterson, John

1998-01-01

The variations in research reactor fuel form, configuration, irradiation characteristics, and transport cask have required a substantial number of transport cask licensing actions associated with foreign research reactor spent fuel transportation. When compounded by limited time for shipment preparations, due to contract timing or delayed receipt of technical data, the number and timing of certifications has adversely impacted the ability of regulatory agencies to support intended shipping schedules. This issue was brought into focus at a april, 1998 meeting among DOE, the US Nuclear Regulatory Commission, and DOE's spent fuel transportation contractors. (author)

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

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

Status report on the HFR conversion and re-licensing project

International Nuclear Information System (INIS)

Wijtsma, F.G.

2003-01-01

In 1999 the HFR license holder (JRC, Petten, the Netherlands) initiated a project to study the conversion of the HFR from HEU to LEU. The first phase of this project consisted of a parametric study to determine the optimum fuel element and control rod design within given boundary conditions such as geometry, density, performance and cycle length. Results of this study are a 22 plates fuel element (550 g 235 U) at a density of 4.8 g.cm -3 and a 17 plates control rod (440 g 235 U). The second phase contains all aspects related to the conversion including a full-scale test irradiation of a prototype LEU element. The actual conversion of the HFR requires a new license. For this reason the re-licensing project has started in 2001. In this context many studies have been performed e.g. Risk Scoping Study, Safety Analyses, TOPA (Technical, Operational, Personnel and Administrative) evaluation. The license application will be based on a new Safety Report and an Environmental Impact Statement and will be submitted to the competent Authorities at the end of October 2003. (author)

8MVA modulator/regulator for neutral beams

International Nuclear Information System (INIS)

Remsen, D.B. Jr.; Overett, T.H.

1980-05-01

This paper describes very generally the modulator/regulator (Mod/Reg) being built for Transrex by Systems, Science and Software for use on the neutral beam power supplies that Transrex is building for General Atomic Company to power the neutral beam heating systems that will be used on the Doublet III fusion device. The Mod/Reg is required to provide an 80 kV, 100 A pulse for a second every 90 sec. The voltage is to be regulated to 3%, and in case of fault the pulse must be interrupted within 10 μsec. An additional requirement was that the total system have very low capacity such that the total energy stored would be less than 15 joules. This is a restriction imposed by the source designer to prevent destroying the source in case of an arc within the source

75 FR 6301 - Revisions to License Exception GOV To Provide Authorization for Exports and Reexports of...

Science.gov (United States)

2010-02-09

... of the United States, Russia, Japan, Canada, Europe and Italy. (The Italian Space Agency has separate... subject to a license requirement when exported or reexported to Russia. However, even when BIS license... unexpected delays in a launch schedule, such as for mechanical failures in a launch vehicle or weather...

Importance of the licensing process on the safety culture in the Brazilian nuclear fuel cycle facilities

International Nuclear Information System (INIS)

Motta, E.S.; Sousa, A.L.B. de; Paiva, R.L.C. de; Mezrahi, A.

2013-01-01

The main objective of the Nuclear Fuel Cycle Facilities licensing processes is to ensure the safety of these installations in their entire life cycle (in the installation site selection, designing, construction, pre-operational tests, operational and decommissioning phases). The Brazilian licensing process requires from the operator, among others, before the operating license: (I) a Site Report and a Final Safety Analysis Report, ensuring that all safety related issues are adequately analyzed and understood; (II) a formal structured Management System focused on the installation safety; and (III) dissemination of safety related information to all involved operator employees and subcontractors. Therefore, these requirements reflect in an adequate operator actions and practices, ensuring a working environment with a high level of safety culture. (author)

Importance of the licensing process on the safety culture in the Brazilian nuclear fuel cycle facilities

Energy Technology Data Exchange (ETDEWEB)

Motta, E.S.; Sousa, A.L.B. de; Paiva, R.L.C. de; Mezrahi, A., E-mail: emotta@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN-RJ), Rio de Janeiro, RJ (Brazil)

2013-07-01

The main objective of the Nuclear Fuel Cycle Facilities licensing processes is to ensure the safety of these installations in their entire life cycle (in the installation site selection, designing, construction, pre-operational tests, operational and decommissioning phases). The Brazilian licensing process requires from the operator, among others, before the operating license: (I) a Site Report and a Final Safety Analysis Report, ensuring that all safety related issues are adequately analyzed and understood; (II) a formal structured Management System focused on the installation safety; and (III) dissemination of safety related information to all involved operator employees and subcontractors. Therefore, these requirements reflect in an adequate operator actions and practices, ensuring a working environment with a high level of safety culture. (author)

Method of active charge and current neutralization of intense ion beams for ICF

International Nuclear Information System (INIS)

Guiragossian, Z.G.T.; Orthel, J.L.; Lemons, D.S.; Thode, L.E.

1981-01-01

Methods of generating the beam neutralization electrons with required properties are given in the context of a Light Ion Fusion Experiment (LIFE) designed accelerator. Recently derived envelope equations for neutralized and ballistically focused intense ion beams are applied to the LIFE geometry in which 10 MeV He + multiple beamlets coalesce and undergo 45:1 radial compression while beam pulses experience a 20:1 axial compression in the propagation range of 10 m. Both active and auto-neutralization methods are examined and found to produce initial electron temperatures consistent with the requirement of the envelope equation for both radial and axial adiabatic beam pulse compressions. The stability of neutralized beam propagation is also examined concerning the Pierce type electrostatic instability and for the case of LIFE beams it is found to have insignificant effect. A scaled experimental setup is presented which can serve to perform near term tests on the ballistically focused propagation of neutralized light ion beams

NRC as referee (reactor licensing following the Three Mile Island accident)

International Nuclear Information System (INIS)

Eisenhut, D.G.

1984-01-01

In this article, the NRC's licensing director reports on the progress made by US utilities in complying with the key regulations stemming from the Three Mile Island accident. Over 130 items must be improved at more than 65 reactors. The actions taken by France in response to its own analysis of the accident are discussed. New NRC requirements with regard to operational safety, design, and emergency-response capability are outlined. Nearly all the training, or software, items in Nureg-0737 (''Clarification of TMI Action Plan Requirements'') and more than half of the mechanical, or hardware, items have been completed at plants with operating reactors. The Committee to Review Generic Requirements was created to develop means for controlling the number and nature of NRC requirements placed on licensees. Probabilistic risk-assessment techniques were not widely used by the NRC until after the Three Mile Island accident. The NRC has directed licensees and applicants for operating licenses to conduct control-room design reviews to identify and correct human-engineering discrepancies. Includes 2 tables

Hydropower : A Regulatory Guide to Permitting and Licensing in Idaho, Montana, Oregon, and Washington.

Energy Technology Data Exchange (ETDEWEB)

McCoy, Gilbert A.

1992-12-01

The design, construction and operation of a hydropower project can result in many potential impacts. These potential impacts are of concern to a host of federal, state, and local authorities. Early consultation with land and water management, fish and wildlife resource protection, and health and human safety-oriented agencies should occur to determine specific concerns and study requirements for each proposed project. This Guide to Permitting and Licensing outlines the characteristic features of attractive hydropower sites; summarizes an array of developmental constraints; illustrates potential environmental impacts and concerns; and summarizes all federal, state, and local permitting and licensing requirements.

Hydropower: A Regulatory Guide to Permitting and Licensing in Idaho, Montana, Oregon, and Washington.

Energy Technology Data Exchange (ETDEWEB)

McCoy, Gilbert A.

1992-12-01

The design, construction and operation of a hydropower project can result in many potential impacts. These potential impacts are of concern to a host of federal, state, and local authorities. Early consultation with land and water management, fish and wildlife resource protection, and health and human safety-oriented agencies should occur to determine specific concerns and study requirements for each proposed project. This Guide to Permitting and Licensing outlines the characteristic features of attractive hydropower sites; summarizes an array of developmental constraints; illustrates potential environmental impacts and concerns; and summarizes all federal, state, and local permitting and licensing requirements.

Lawrence Berkeley laboratory neutral-beam engineering test facility power-supply system

International Nuclear Information System (INIS)

Lutz, I.C.; Arthur, C.A.; deVries, G.J.; Owren, H.M.

1981-10-01

The Lawrence Berkeley Laboratory is upgrading the neutral beam source test facility (NBSTF) into a neutral beam engineering test facility (NBETF) with increased capabilities for the development of neutral beam systems. The NBETF will have an accel power supply capable of 170 kV, 70 A, 30 sec pulse length, 10% duty cycle; and the auxiliary power supplies required for the sources. This paper describes the major components, their ratings and capabilities, and the flexibility designed to accomodate the needs of source development

Neutrality Versus Materiality: A Thermodynamic Theory of Neutral Surfaces

Directory of Open Access Journals (Sweden)

Rémi Tailleux

2016-09-01

Full Text Available In this paper, a theory for constructing quasi-neutral density variables γ directly in thermodynamic space is formulated, which is based on minimising the absolute value of a purely thermodynamic quantity J n . Physically, J n has a dual dynamic/thermodynamic interpretation as the quantity controlling the energy cost of adiabatic and isohaline parcel exchanges on material surfaces, as well as the dependence of in-situ density on spiciness, in a description of water masses based on γ, spiciness and pressure. Mathematically, minimising | J n | in thermodynamic space is showed to be equivalent to maximising neutrality in physical space. The physics of epineutral dispersion is also reviewed and discussed. It is argued, in particular, that epineutral dispersion is best understood as the aggregate effect of many individual non-neutral stirring events (being understood here as adiabatic and isohaline events with non-zero buoyancy, so that it is only the net displacement aggregated over many events that is approximately neutral. This new view resolves an apparent paradox between the focus in neutral density theory on zero-buoyancy motions and the overwhelming evidence that lateral dispersion in the ocean is primarily caused by non-zero buoyancy processes such as tides, residual currents and sheared internal waves. The efficiency by which a physical process contributes to lateral dispersion can be characterised by its energy signature, with those processes releasing available potential energy (negative energy cost being more efficient than purely neutral processes with zero energy cost. The latter mechanism occurs in the wedge of instability, and its source of energy is the coupling between baroclinicity, thermobaricity, and density compensated temperature/salinity anomalies. Such a mechanism, which can only exist in a salty ocean, is speculated to be important for dissipating spiciness anomalies and neutral helicity. The paper also discusses potential

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...

Licensing Air and Transboundary Shipments of Spent Nuclear Fuel

International Nuclear Information System (INIS)

Komarov, S.V.; Budu, M.E.; Derganov, D.V.; Savina, O.A.; Bolshinsky, I.M.; Moses, S.D.; Biro, L.

2016-01-01

Since 1996 the IAEA TS-R-1 regulation included new requirements applicable to transport of fissile materials by air. The later 2005 and 2009 editions confirmed the validity of those provisions. Despite the fact that the IAEA TS-R-1 allows for air shipments of SNF in Type B and Type C packages, the examples of such shipments are not abundant. Nuclear regulatory bodies and transport safety experts are cautious about air shipments of SNF. Why so? What are the risks? What are the alternatives? In this new regulatory framework, in 2009, two air shipments in Type B packages of Research Reactor (RR) Spent Nuclear Fuel (SNF) from Romania and Libya were performed under the U.S. DOE/NNSA RRRFR Program. The first licensing process of such shipment brought up many questions about package and shipment safety from the licensing experts' side and so the scope of analyses exceeded the requirements of IAEA. Under the thorough supervision of Rosatom and witnessed by DOE and CNCAN, all questions were answered by various strength analyses and risk evaluations. But the progress achieved didn't stop here. In 2010-2011, an energy absorption container (EAC) with titanium spheres as absorbers based on the SKODA VPVR/M cask was designed as the first Type C package in the world destined for RR SNF, currently under approval process. At the same time, intense preparations for the safe removal of the Russian-origin damaged RR SNF from Serbia, Vinca were in progress. The big amount of SNF and its rapidly worsening condition imposed as requirements to organize only one shipment as fast as possible, i.e. using at the maximum extent the entire experience available from other SNF shipments. The long route, several transit countries and means of transport, two different casks, new European regulations and many other issues resulted for the Serbian shipment in one of the most complex SNF shipments’ licensing exercise. This paper shows how the international regulatory framework ensures the

Design of cryo-vacuum system for MW neutral beam injector

International Nuclear Information System (INIS)

Hu Chundong; Xie Yuanlai

2010-01-01

Neutral beam injector is an equipment that is used to produce and then to neutralize high energetic particle beam. A neutral beam injector (EAST-NBI) with MW magnitude neutral beam power is considered to be developed to support the EAST physical research. The requirements for vacuum system were analyzed after introducing the principle of EAST-NBI. A differential vacuum system structure was chosen after analyzing the performance of different vacuum pumping system structure. The gas sources and their characteristics were analyzed, and two inserted type cryocondensation pumps were chosen as main vacuum pump. The schematic structure of the two cryocondensation pump with pumping area 8 m 2 and 6 m 2 were given and their cooling method and temperature control mode were determined. (authors)

75 FR 51823 - Government-Owned Inventions; Availability for Licensing

Science.gov (United States)

2010-08-23

...: Licensing information and copies of the U.S. patent applications listed below may be obtained by writing to.../402-0220. A signed Confidential Disclosure Agreement will be required to receive copies of the patent... infertility and irregular menstrual periods than in healthy women. The discovery of MATER as an important...

Selection/licensing of nuclear power plant operators

International Nuclear Information System (INIS)

Saari, L.M.

1983-07-01

An important aspect of nuclear power plant (NPP) safety is the reactor operator in the control room. The operators are the first individuals to deal with an emergency situation, and thus, effective performance on their part is essential for safe plant operations. Important issues pertaining to NPP reactor operators would fall within the personnel subsystem of our safety system analysis. While there are many potential aspects of the personnel subsystem, a key first step in this focus is the selection of individuals - attempting to choose individuals for the job of reactor operator who will safely perform the job. This requires a valid (job-related) selection process. Some background information on the Nuclear Regulatory Commission (NRC) licensing process used for selecting NPP reactor operators is briefly presented and a description of a research endeavor now underway at Battelle for developing a valid reactor operator licensing examination is included

Software licenses: Good fences make good neighbors

International Nuclear Information System (INIS)

McCreary, J.G.; Woodyard, A.

1995-01-01

The basis for a good contract is that it is beneficial to both parties. A good foundation will cement the responsibilities and obligations of the parties after areas of agreement have been negotiated. Unfortunately, software licenses do not always reflect what is best for all. Some clauses are definitely for the benefit of the vendor, while others are required by a prudent client. The resulting contract is then a matter of reasonable compromise to achieve a good business relationship. Major issues of warranty, liability, training, support, and payment may be in conflict. Such topics as maintenance, testing, patents, extent of use, and return of software are often overlooked or addressed unevenly. This paper addresses these subjects and provides guidelines for software licenses. An understanding of legal phrases is of value. A better understanding of the viewpoints of both the vendor and the client results in a better working relationship

Decay power evaluation for licensing analysis

International Nuclear Information System (INIS)

Tran, H.; Schrock, V.E.

1987-01-01

The ANSI/ANS 5.1-1979 Standard on Decay Power in shutdown reactors has been available as the basis for accident analysis for the past 7 yr. The US Nuclear Regulatory Commission has made a commitment to use this standard in new licensing approaches and has approved a licensing model for boiling water. More sweeping changes in the licensing rules are currently under review that will involve the use of best-estimate models and a statistical evaluation of the uncertainty (95% confidence level) in the key results. The structure of the decay power standard is well suited for such applications because it provides a statistically meaningful uncertainty in the decay power from fission products. The normalized decay power is a function specific to each point in the reactor volume due to the fact that the fuel composition develops a spatial dependence as burnup proceeds and decay power depends on the mix of fissioning nuclides. For reactor safety calculations it is desirable to employ a single temporal decay power function for the whole core inasmuch as many variations of accident parameters are required. This is the usual approach in large system thermal-hydraulics codes. Such a single representative or generic curve for a specified total operating power history can be acceptable but at the expense of some increase in the uncertainty. In this paper, the author present a method of evaluating the additional uncertainty in the decay power associated with use of a generic curve

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...

Public perspectives on proposed license renewal regulations for nuclear power plants

International Nuclear Information System (INIS)

Ligon, D.; Hughes, A.; Seth, S.

1991-01-01

On 17 July 1990, the U.S Nuclear Regulatory Commission (NRC) issued for public comment its proposed rule for renewing the operating licenses of nuclear power plants (55 FR 29043). This solicitation marked the fourth time that NRC has Invited public comments on its efforts to develop regulatory requirements for re licensing nuclear power plants. Previously, NRC solicited public comments on establishing a policy statement on plant life extension, and on the issues and options for license renewal discussed in NUREG-1317. On 13-14 November 1989, NRC held a public workshop where the NRC staff discussed a conceptual approach to the rule and solicited written comments on the regulatory philosophy, conceptual rule, and on certain questions. NRC is taking into account all comments received in its development of the final rule which is scheduled for issuance in the summer of 1991

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.

Licensing assessment of the CANDU pressurized heavy water reactor. Volume I. Preliminary safety information document

International Nuclear Information System (INIS)

1977-06-01

The PHWR design contains certain features that will require significant modifications to comply with USNRC siting and safety requirements. The most significant of these features are the reactor vessel; control systems; quality assurance program requirements; seismic design of structures, systems and components; and providing an inservice inspection program capability. None of these areas appear insolvable with current state-of-the-art engineering or with upgrading of the quality assurance program for components constructed outside of the USA. In order to be licensed in the U. S., the entire reactor assembly would have to be redesigned to comply with ASME Boiler and Pressure Vessel Code, Section III, Division 1 and Division 2. A summary matrix at the end of this volume identifies compliance of the systems and structures of the PHWR plant with the USNRC General Design Criteria. The matrix further identifies the estimated incremental cost to a 600 MWe PHWR that would be required to license the plant in the U. S. Further, the matrix identifies whether or not the incremental licensing cost is size dependent and the relative percentage of the base direct cost of a Canadian sited plant

Neutralized drift compression experiments with a high-intensity ion beam

International Nuclear Information System (INIS)

Roy, P.K.; Yu, S.S.; Waldron, W.L.; Anders, A.; Baca, D.; Barnard, J.J.; Bieniosek, F.M.; Coleman, J.; Davidson, R.C.; Efthimion, P.C.; Eylon, S.; Friedman, A.; Gilson, E.P.; Greenway, W.G.; Henestroza, E.; Kaganovich, I.; Leitner, M.; Logan, B.G.; Sefkow, A.B.; Seidl, P.A.; Sharp, W.M.; Thoma, C.; Welch, D.R.

2007-01-01

To create high-energy density matter and fusion conditions, high-power drivers, such as lasers, ion beams, and X-ray drivers, may be employed to heat targets with short pulses compared to hydro-motion. Both high-energy density physics and ion-driven inertial fusion require the simultaneous transverse and longitudinal compression of an ion beam to achieve high intensities. We have previously studied the effects of plasma neutralization for transverse beam compression. The scaled experiment, the Neutralized Transport Experiment (NTX), demonstrated that an initially un-neutralized beam can be compressed transversely to ∼1 mm radius when charge neutralization by background plasma electrons is provided. Here, we report longitudinal compression of a velocity-tailored, intense, neutralized 25 mA K + beam at 300 keV. The compression takes place in a 1-2 m drift section filled with plasma to provide space-charge neutralization. An induction cell produces a head-to-tail velocity ramp that longitudinally compresses the neutralized beam, enhances the beam peak current by a factor of 50 and produces a pulse duration of about 3 ns. The physics of longitudinal compression, experimental procedure, and the results of the compression experiments are presented

The licensing practice on nuclear power plants in Korea

Energy Technology Data Exchange (ETDEWEB)

Moon, S P

1994-12-31

The evolution of Korean regulatory system has tightly coupled with development ot Korean nuclear power program. The nuclear power plant licensing has become a major regulatory function of the government when the construction of the Kori NPP Unit 1 started in early 1970s. During this period, domestic laws and regulations applicable to the licensing of NPP were not yet fully developed. Therefore the vendor countries` laws and regulations were applied as mandatory requirement. Beginning in the early 19808, component approach was used and contracts were awarded separately for major components of the plants, thus enabling more domestic industries to participate in the projects. The two-step licensing system was incorporated into the law. In the third phase from 1987, major efforts have been concentrated on the maximum participation of local industries. The overriding priority for selecting suppliers was the condition of higher nuclear technology transfer to Korea. The Korea Institute of Nuclear Safety (KINS) was established in 1990 as an independent regulatory expert organization. 1 tab., 4 figs.

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)

76 FR 15826 - Fisheries of the Exclusive Economic Zone Off Alaska; Gulf of Alaska License Limitation Program

Science.gov (United States)

2011-03-22

... Islands (AI); Southeast Outside District (SEO); Central Gulf of Alaska (CG), which includes the West... LLP licenses could resume fishing under the licenses in the future and thereby adversely affect active... BS or AI regulatory areas because a Pacific cod endorsement requirement has already been established...

Considerations about the licensing process of special nuclear industrial facilities

Energy Technology Data Exchange (ETDEWEB)

Talarico, M.A., E-mail: talaricomarco@hotmail.com [Marinha do Brasil, Rio de Janeiro, RJ (Brazil). Coordenacao do Porgrama de Submarino com Propulsao Nuclear; Melo, P.F. Frutuoso e [Coordenacao dos Programas de Pos-Graduacao em Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear

2015-07-01

This paper brings a discussion about the challenges involved in the development of a new kind of nuclear facility in Brazil, a naval base for nuclear submarines, with attention to the licensing process and considerations about the risk-informed decision making application to the licensing process. Initially, a model of such a naval base, called in this work, special industrial facility, is proposed, with its systems and respective sets of basic requirements, in order to make it possible the accomplishment of the special industrial facility support function to the nuclear submarine. A discussion about current challenges to overcome in this project is presented: the challenges due to the new characteristics of this type of nuclear facility; existence of several interfaces between the special industrial facilities systems and nuclear submarine systems in design activities; lack of specific regulation in Brazil to allow the licensing process of special industrial facilities by the nuclear safety authority; and comments about the lack of information from reference nuclear facilities, as is the case with nuclear power reactors (for example, the German Grafenrheinfeld nuclear plant is the reference plant for the Brazilian Angra 2 nuclear plant). Finally, in view of these challenges, an analysis method of special industrial facility operational scenarios to assist the licensing process is proposed. Also, considerations about the application of risk-informed decision making to the special industrial facility activity and licensing process in Brazil are presented. (author)

Considerations about the licensing process of special nuclear industrial facilities

International Nuclear Information System (INIS)

Talarico, M.A.; Melo, P.F. Frutuoso e

2015-01-01

This paper brings a discussion about the challenges involved in the development of a new kind of nuclear facility in Brazil, a naval base for nuclear submarines, with attention to the licensing process and considerations about the risk-informed decision making application to the licensing process. Initially, a model of such a naval base, called in this work, special industrial facility, is proposed, with its systems and respective sets of basic requirements, in order to make it possible the accomplishment of the special industrial facility support function to the nuclear submarine. A discussion about current challenges to overcome in this project is presented: the challenges due to the new characteristics of this type of nuclear facility; existence of several interfaces between the special industrial facilities systems and nuclear submarine systems in design activities; lack of specific regulation in Brazil to allow the licensing process of special industrial facilities by the nuclear safety authority; and comments about the lack of information from reference nuclear facilities, as is the case with nuclear power reactors (for example, the German Grafenrheinfeld nuclear plant is the reference plant for the Brazilian Angra 2 nuclear plant). Finally, in view of these challenges, an analysis method of special industrial facility operational scenarios to assist the licensing process is proposed. Also, considerations about the application of risk-informed decision making to the special industrial facility activity and licensing process in Brazil are presented. (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)

Safety features and licensing of CNNC-ACP100

Energy Technology Data Exchange (ETDEWEB)

Zhong, F., E-mail: Zhongfj2000@163.com [Nuclear Power Inst. of China, National Key Lab. of Science and Technology on Reactor System Design Technology (China)

2014-07-01

ACP100 is an innovatory modular pressurized water reactor, the engineering safety systems fully adopt passive safety design technology. Its inherent safety and passive features/systems are verified via testing facilities and are highlighted at certain levels of defence in depth. The licensing of ACP 100 is within current LWR framework and meets up-to-date codes and requirements in nuclear safety. (author)

Could a scheme for licensing smokers work in Australia?

Science.gov (United States)

Magnusson, Roger S; Currow, David C

2013-08-05

In this article, we evaluate the possible advantages and disadvantages of a licensing scheme that would require adult smokers to verify their right to purchase tobacco products at point of sale using a smart-card licence. A survey of Australian secondary school students conducted in 2011 found that half of 17-2013-old smokers and one-fifth of 12-2013-old smokers believed it was "easy" or "very easy" to purchase cigarettes themselves. Reducing tobacco use by adolescents now is central to the future course of the current epidemic of tobacco-caused disease, since most current adult smokers began to smoke as adolescents--at a time when they were unable to purchase tobacco lawfully. The requirement for cigarette retailers to reconcile all stock purchased from wholesalers against a digital record of retail sales to licensed smokers would create a robust incentive for retailers to comply with laws that prohibit tobacco sales to children. Foreseeable objections to introducing a smokers licence need to be taken into account, but once we move beyond the "shock of the new", it is difficult to identify anything about a smokers licence that is particularly offensive or demeaning. A smoker licensing scheme deserves serious consideration for its potential to dramatically curtail retailers' violation of the law against selling tobacco to minors, to impose stricter accountability for sale of a uniquely harmful drug and to allow intelligent use of information about smokers' purchases to help smokers quit.

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...

Standard format and content for a license application to store spent fuel and high-level radioactive waste

International Nuclear Information System (INIS)

1989-09-01

Subpart B, ''License Application, Form, and Contents,'' of 10 CFR Part 72, ''Licensing Requirements for the Independent Storage of Spent Nuclear Fuel and High-Level Radioactive Waste,'' specifies the information to be covered in an application for a license to store spent fuel in an independent spent fuel storage installation (ISFSI) or to store spent fuel and high-level radioactive waste in a monitored retrievable storage facility (MRS). However, Part 72 does not specify the format to be followed in the license application. This regulatory guide suggests a format acceptable to the NRC staff for submitting the information specified in Part 72 for license application to store spent fuel in an ISFSI or to store spent fuel and high-level radioactive waste in an MRS

Exporting the Canadian licensing program

International Nuclear Information System (INIS)

Whelan, D.J.

1981-06-01

This paper deals with the problems of an overseas regulatory agency in licensing a Canadian-supplied nuclear plant which is referenced to a plant in Canada. Firstly, the general problems associated with the use of a reference plant are discussed. This is followed by a discussion of specific problems which arise from the licensing practices in Canada. The paper concludes with recommendations to simplify the task of demonstrating the licensability of an overseas CANDU plant

7 CFR 6.32 - Globalization of licenses.

Science.gov (United States)

2010-01-01

... 7 Agriculture 1 2010-01-01 2010-01-01 false Globalization of licenses. 6.32 Section 6.32 Agriculture Office of the Secretary of Agriculture IMPORT QUOTAS AND FEES Dairy Tariff-Rate Import Quota Licensing § 6.32 Globalization of licenses. If the Licensing Authority determines that entries of an article...

42 CFR 431.710 - Provisional licenses.

Science.gov (United States)

2010-10-01

... Licensing Nursing Home Administrators § 431.710 Provisional licenses. To fill a position of nursing home... 42 Public Health 4 2010-10-01 2010-10-01 false Provisional licenses. 431.710 Section 431.710 Public Health CENTERS FOR MEDICARE & MEDICAID SERVICES, DEPARTMENT OF HEALTH AND HUMAN SERVICES...

Product Licenses Database Application

CERN Document Server

Tonkovikj, Petar

2016-01-01

The goal of this project is to organize and centralize the data about software tools available to CERN employees, as well as provide a system that would simplify the license management process by providing information about the available licenses and their expiry dates. The project development process is consisted of two steps: modeling the products (software tools), product licenses, legal agreements and other data related to these entities in a relational database and developing the front-end user interface so that the user can interact with the database. The result is an ASP.NET MVC web application with interactive views for displaying and managing the data in the underlying database.

75 FR 61116 - Refunds Under the Cable Statutory License

Science.gov (United States)

2010-10-04

... Copyright Act, before it was amended to allow a cable system to calculate its royalty fees on a community-by... statutory license set forth in Section 111 are required to pay royalty fees to the Copyright Office... the methodology for a cable operator to calculate royalty fees. Cable operators now pay royalty fees...

Radiation protection in medical research. Licensing requirement for the use of radiation and advice for the application procedure; Strahlenschutz in der medizinischen Forschung. Genehmigungsbeduerftigkeit von Strahlenanwendungen und Hinweise zum Antragsverfahren

Energy Technology Data Exchange (ETDEWEB)

Minkov, V.; Klammer, H.; Brix, G. [Bundesamt fuer Strahlenschutz, Abteilung fuer medizinischen und beruflichen Strahlenschutz, Neuherberg (Germany)

2017-07-15

In Germany, persons who are to be exposed to radiation for medical research purposes are protected by a licensing requirement. However, there are considerable uncertainties on the part of the applicants as to whether licensing by the competent Federal Office for Radiation Protection is necessary, and regarding the choice of application procedure. The article provides explanatory notes and practical assistance for applicants and an outlook on the forthcoming new regulations concerning the law on radiation protection of persons in the field of medical research. Questions and typical mistakes in the application process were identified and evaluated. The qualified physicians involved in a study are responsible for deciding whether a license is required for the intended application of radiation. The decision can be guided by answering the key question whether the study participants would undergo the same exposures regarding type and extent if they had not taken part in the study. When physicians are still unsure about their decision, they can seek the advisory service provided by the professional medical societies. Certain groups of people are particularly protected through the prohibition or restriction of radiation exposure. A simplified licensing procedure is used for a proportion of diagnostic procedures involving radiation when all related requirements are met; otherwise, the regular licensing procedure should be used. The new radiation protection law, which will enter into force on the 31st of december 2018, provides a notification procedure in addition to deadlines for both the notification and the licensing procedures. In the article, the authors consider how eligible studies involving applications of radiation that are legally not admissible at present may be feasible in the future, while still ensuring a high protection level for study participants. (orig.) [German] Personen, bei denen Strahlenanwendungen zum Zweck der medizinischen Forschung durchgefuehrt

PLT neutral injection ignitron accelerating supply

International Nuclear Information System (INIS)

Ashcroft, D.L.; Murray, J.G.; Newman, R.A.; Peterson, F.L.

1975-11-01

A phase-controlled rectifier was designed for the accelerating supply on the PLT Neutral Beam Injection system at PPPL. The rectifier must furnish 70 amperes at up to 50 KV for 300 milliseconds, with a duty cycle of up to 10 percent. Protection of the injectors requires the supply to withstand repeated crowbarring. The rectifying element selected to satisfy these requirements was a commercially-available ignitron, installed in a supporting frame and using firing circuits and controls designed by PPPL

PLT neutral injection ignitron accelerating supply

International Nuclear Information System (INIS)

Ashcroft, D.L.; Murray, J.G.; Newman, R.A.; Peterson, F.L.

1976-03-01

A phase-controlled rectifier has been designed for the accelerating supply on the PLT Neutral Beam Injection system at PPPL. The rectifier must furnish 70 amperes at up to 50 KV for 300 milliseconds, with a duty cycle of up to 10 percent. Protection of the injectors requires the supply to withstand repeated crowbarring. The rectifying element selected to satisfy these requirements was a commercially-available ignitron, installed in a supporting frame and using firing circuits and controls designed by PPPL

Titration of individual strains in trivalent live-attenuated influenza vaccine without neutralization.

Science.gov (United States)

Sirinonthanawech, Naraporn; Surichan, Somchaiya; Namsai, Aphinya; Puthavathana, Pilaipan; Auewarakul, Prasert; Kongchanagul, Alita

2016-11-01

Formulation and quality control of trivalent live-attenuated influenza vaccine requires titration of infectivity of individual strains in the trivalent mix. This is usually performed by selective neutralization of two of the three strains and titration of the un-neutralized strain in cell culture or embryonated eggs. This procedure requires standard sera with high neutralizing titer against each of the three strains. Obtaining standard sera, which can specifically neutralize only the corresponding strain of influenza viruses and is able to completely neutralize high concentration of virus in the vaccine samples, can be a problem for many vaccine manufacturers as vaccine stocks usually have very high viral titers and complete neutralization may not be obtained. Here an alternative approach for titration of individual strain in trivalent vaccine without the selective neutralization is presented. This was done by detecting individual strains with specific antibodies in an end-point titration of a trivalent vaccine in cell culture. Similar titers were observed in monovalent and trivalent vaccines for influenza A H3N2 and influenza B strains, whereas the influenza A H1N1 strain did not grow well in cell culture. Viral interference among the vaccine strains was not observed. Therefore, providing that vaccine strains grow well in cell culture, this assay can reliably determine the potency of individual strains in trivalent live-attenuated influenza vaccines. Copyright © 2016 Elsevier B.V. All rights reserved.

Nuclear facilities licensing

International Nuclear Information System (INIS)

Carvalho, A.J.M. de.

1978-01-01

The need for the adoption of a legal and normative system, defining objectives, pescriptions and the process of nuclear licensing and building of nuclear power plants in Brazil is enphasized. General rules for the development of this system are presented. The Brazilian rules on the matter are discussed. A general view of the German legal system for nuclear power plant licensing and the IAEA recommendations on the subject are finally presented. (A.L.S.L.) [pt

18 CFR 16.10 - Information to be provided by an applicant for new license: Filing requirements.

Science.gov (United States)

2010-04-01

... FEDERAL POWER ACT PROCEDURES RELATING TO TAKEOVER AND RELICENSING OF LICENSED PROJECTS Applications for... redistribution of power flows on line loading (with respect to applicable thermal, voltage, or stability limits... governmental agencies and subdivisions likely to be interested in or affected by the proposed expansion. (11...

Licensing procedure for nuclear power in Sweden. An international look with lessons for Sweden

International Nuclear Information System (INIS)

Gaahlin, Emil; Nilsson, Isabelle; Pettersson, Maria; Soederholm, Patrik

2011-02-01

In this study we present an in-depth analysis of the existing licensing procedure for nuclear power in Sweden, and the related processes towards different public authorities. In order to put the existing legislation into context we also analyze the legal and political prerequisites for the establishment of nuclear reactors during the 1970s. The purpose of this report is thus to: (a) analyze the legal and political conditions under which the existing nuclear power plants in Sweden were built; and (b) review and analyze the existing licensing procedure for nuclear power in the country. Four main statutes (and several subordinated regulations) apply in connection with the establishment of a new nuclear plant in Sweden, including the adoption of physical plans, a principal governmental decision on the permissibility of the plant and at least five major licenses. Physical planning according to the Planning and Building Act is primarily a municipal responsibility. A plan has to meet certain environmental requirements; not least the 'provisions on efficient management of natural resources' in the Environmental Code, indicating how different kinds of land and water areas should be used and thereby direct the location of different installations. The Swedish rules are complex and vague in many respects, and may therefore imply major uncertainties for a prospective investor. The legal protection is less unclear if an area is of national interest for a specific purpose, such as nature conservation, where it normally would not be possible to locate, say, a nuclear power plant. An area may also be of national interest for nuclear plants, which of course significantly alters the preconditions in favour of the plant project. The physical planning procedure comprises an 'environmental consideration' of the plan, including an 'environmental impact assessment' (EIA), provided the plan is likely to have significant effects on the environment. This 'programmatic EIA' does however not

Fuel licensing process for an industrial use. ATF licensing process for an industrial use - Utility's perspective

International Nuclear Information System (INIS)

Waeckel, Nicolas

2013-01-01

To develop and license a breakthrough nuclear fuel technology for commercial use is becoming challenging. All the former safety analysis design limits (SAFDLs) defined in the 1970's for the standard UO 2 -Zr fuels, might no longer be applicable. Identification of the appropriate safety analysis design limits For each type of innovative fuel, the developers will have to identify and investigate all the possible failure/ruins scenarios (not only those related to severe accidents but also those related to normal operation). In order to save time and to focus on the best options, those failure scenarios (which could be 'killers' for the ATF concept) have to be determined early enough in the development process. Based on the above failure scenarios, the developers will have to propose the licensing limits (and the experimental protocol to determine and to justify them). As mentioned earlier, the licensing limits should not be defined against the accidental conditions only. For the operators, the (good) in-reactor fuel behaviour is crucial. As an example, in the case of the new fuel concepts coming with an outer coating, it is important to include the analysis of the consequences of the loss of this protective outer layer in the licensing process due to a manufacturing defect or an inevitable in-reactor fretting wear. Obviously, the new/specific SAFDLs will have to be endorsed by the regulators (which could be a long process by itself). Identification of a commercial reactor to irradiate the first ATF A commercial NPP is not a material test reactor (MTR); irradiating lead test fuel rods (LTFRs) or lead test assemblies (LTAs) implies strict requirements regarding the manufacturing processes [which should not include chemicals (additives or solvents) potentially incompatible with the nuclear technical specifications], the compatibility with the hosting fuel core (in terms of geometry, enrichment, thermal hydraulic performances, etc.) and the robustness and

Conceptual design of the neutral beamline for TPX long pulse operation

International Nuclear Information System (INIS)

Wright, K.E.; Dahlgren, F.; Fan, H.M.; Grisham, L.R.; Hammersand, F.G.; Kamperschroer, J.H.; Lontai, L.M.; Oldaker, M.E.; Rogoff, P.

1993-01-01

The Tokamak Physics Experiment (TPX) will require a minimum of 8.0 megawatts of Neutral Beam beating power to be injected into the plasma for pulse lengths up to one thousand (1000) seconds to meet the experimental objectives. The Neutral Beam Injection System (NBIS) for initial operation on TPX will consist of one neutral beamline (NBL) with three Ion sources. Provisions will be made for a total of three NBLs. The NBIS will provide S.S MW of 120 keV D 0 and 2.S MW of partial-energy D 0 at 60 keV and 40 keV. The system also provides for measuring the neutral beam power, limits excess cold gas from entering the torus, and provides independent power, control, and protection for each individual ion source and accelerating structure. The Neutral Beam/Torus Connecting Duct (NB/TCD) includes a vacuum valve, an electrical insulating break, alignment bellows, vacuum seals, internal energy absorbing protective elements, beam diagnostics and bakeout capability. The NBL support structure will support the NBL, which will weigh approximately 80 tons at the proper elevation and withstand a seismic event. The NBIS currently operational on the Tokamak Fusion Test Reactor (TFTR) at the Princeton Plasma Physics Laboratory (PPPL) is restricted to injection pulse lengths of two (2) seconds by the limited capability of various energy absorbers. This paper describes the modifications and improvements which will be implemented for the TFTR Neutral Beamlines and the NB/TCD to satisfy the TPX requirements

Charging induced emission of neutral atoms from NaCl nanocube corners

International Nuclear Information System (INIS)

Ceresoli, Davide; Zykova-Timan, Tatyana; Tosatti, Erio

2008-01-01

Detachment of neutral cations/anions from solid alkali halides can in principle be provoked by donating/subtracting electrons to the surface of alkali halide crystals, but generally constitutes a very endothermic process. However, the amount of energy required for emission is smaller for atoms located in less favorable positions, such as surface steps and kinks. For a corner ion in an alkali halide cube the binding is the weakest, so it should be easier to remove that atom, once it is neutralized. We carried out first principles density functional calculations and simulations of neutral and charged NaCl nanocubes, to establish the energetics of extraction of neutralized corner ions. Following hole donation (electron removal) we find that detachment of neutral Cl corner atoms will require a limited energy of about 0.8 eV. Conversely, following the donation of an excess electron to the cube, a neutral Na atom is extractable from the corner at the lower cost of about 0.6 eV. Since the cube electron affinity level (close to that a NaCl(100) surface state, which we also determine) is estimated to lie about 1.8 eV below vacuum, the overall energy balance upon donation to the nanocube of a zero-energy electron from vacuum will be exothermic. The atomic and electronic structure of the NaCl(100) surface, and of the nanocube Na and Cl corner vacancies are obtained and analyzed as a byproduct

Operating reactors licensing actions summary

International Nuclear Information System (INIS)

1981-08-01

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

77 FR 71404 - Notice of Intent to License Government-Owned Inventions; Intent to License on a Partially...

Science.gov (United States)

2012-11-30

... DEPARTMENT OF DEFENSE Department of the Army Notice of Intent to License Government-Owned Inventions; Intent to License on a Partially-Exclusive Basis AGENCY: Department of the Army, DoD. ACTION... by the Secretary of the Army. The US Army Edgewood Chemical Biological Center intends to license...

Neutral beam injector for 475 keV MARS sloshing ions

International Nuclear Information System (INIS)

Goebel, D.M.; Hamilton, G.W.

1983-01-01

A neutral beam injector system which produces 5 MW of 475 keV D 0 neutrals continuously on target has been designed. The beamline is intended to produce the sloshing ion distribution required in the end plug region of the conceptual MARS tandem mirror commercial reactor. The injector design utilizes the LBL self-extraction negative ion source and Transverse Field Focusing (TFF) accelerator to generate a long, ribbon ion beam. A laser photodetachment neutralizer strips over 90% of the negative ions. Magnetic and neutron shield designs are included to exclude the fringe fields of the end plug and provide low activation by the neutron flux from the target plasma. The use of a TFF accelerator and photodetachment neutralizer produces a total system electrical efficiency of about 63% for this design

Status of safety issues at licensed power plants

International Nuclear Information System (INIS)

1991-05-01

As part of ongoing US Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, a program has been established whereby an annual NUREG report will be published on the status of licensee implementation and NRC verification of safety issues in major NRC requirement areas. This report, the second volume of a three-volume series, addresses the status of unresolved safety issues (USIs) at licensed plants. The data contained in these NUREG reports are a product of the NRC's Safety Issues Management System (SIMS) database, which is maintained by the Project Management Staff in the Office of Nuclear Reactor Regulation and by NRC regional personnel. The purpose of this report is to provide a comprehensive description of the status of implementation and verification of the 27 safety issues designated as USIs and to make this information available to other interested parties, including the public. A corollary purpose of this NUREG report is to serve as a follow-on to NUREG-0933, ''A Prioritization of Generic Safety Issues,'' which tracks safety issues up until requirements are approved for imposition at licensed plants. 3 figs., 4 tabs

Status of safety issues at licensed power plants: TMI action plan requirements, unresolved safety issues, generic safety issues

International Nuclear Information System (INIS)

1991-12-01

As part of ongoing US Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, a program was established whereby an annual NUREG report would be published on the status of licensee implementation and NRC verification of safety issues in major NRC requirements areas. This information was compiled and reported in three NUREG volumes. Volume 1, published in March 1991, addressed the status of of Three Mile Island (TMI) Action Plan Requirements. Volume 2, published in May 1991, addressed the status of unresolved safety issues (USIs). Volume 3, published in June 1991, addressed the implementation and verification status of generic safety issues (GSIs). This annual NUREG report combines these volumes into a single report and provides updated information as of September 30, 1991. The data contained in these NUREG reports are a product of the NRC's Safety Issues Management System (SIMS) database, which is maintained by the Project Management Staff in the Office of Nuclear Reactor Regulation and by NRC regional personnel. This report is to provide a comprehensive description of the implementation and verification status of TMI Action Plan Requirements, safety issues designated as USIs, and GSIs that have been resolved and involve implementation of an action or actions by licensees. This report makes the information available to other interested parties, including the public. An additional purpose of this NUREG report is to serve as a follow-on to NUREG-0933, ''A Prioritization of Generic Safety Issues,'' which tracks safety issues up until requirements are approved for imposition at licensed plants or until the NRC issues a request for action by licensees

Licensing system for primary category radioactive installations

International Nuclear Information System (INIS)

Ramirez Riquelme, Angelica Beatriz

1997-01-01

The development of a licensing system for primary category radioactive installations is described, which aims to satisfy the needs of the Chilean Nuclear Energy Commission's Department of Nuclear and Radiological Safety, particularly the sections for Licensing Outside Radioactive Installations and Safety Control. This system involves the identification, control and inspection of the installations, their personnel and connected activities, for the purpose of protecting the population's health and the environment. Following the basic cycle methodology, a systems analysis and engineering stage was prepared, establishing the functions of the system's elements and defining the requirements, based on interviews with the users. This stage was followed by the design stage, focusing on the data structure, the software architecture and the procedural detail. The codification stage followed, which translated the design into legible machine-readable format. In the testing stage, the entries that were defined were proven to produce the expected data. Finally and operational and maintenance stage was developed, when the system was installed and put to use. All the above generated a useful system for the Licensing section of the Department of Nuclear and Radiological Safety, since it provides faster and easier access to information. A project is described that introduces new development tools in the Computer department following standards established by the C.CH.E.N. (author)

Review process for license renewal applications

International Nuclear Information System (INIS)

Craig, John W.; Kuo, P.T.

1991-01-01

In preparation for license renewal reviews, the Nuclear Regulatory Commission has recently published for public review and comment a proposed rule for license renewal and a draft Standard Review Plan as well as a draft Regulatory Guide relating to the implementation of the proposed rule. In support of future license renewal applications, the nuclear industry has also submitted 11 industry reports for NRC review and approval. This paper briefly describe how these parallel regulatory and industry activities will be factored into the NRC review process for license renewal. (author)

Conversion to low-enriched fuel in research reactor aspects of licensing the Federal Republic of Germany

International Nuclear Information System (INIS)

Jacquemin, J.

1985-01-01

Conversion to low-enriched fuel and usage of new developed highly densified fuel in research-reactors will be an essential alteration in operating the reactor. According to the German Energy Act this has to be licensed. here might be some risk to the licensee of an older research-reactor by suspending his operating license because he cannot meet current requirements to be fulfilled or because of a court decision.Disposal of irradiated fuel elements of the new fuel type is a further significant problem which has to be solved before issuing a new license. (author)

10 CFR 781.51 - Nonexclusive licenses.

Science.gov (United States)

2010-01-01

... corporate structure of which licensee is a part, if any. However, the license shall not be assignable or... license upon the policies of the United States Government; (3) The effect of the license upon domestic and... extent of U.S. Government contribution to the development of the invention; (iv) The degree of...

7 CFR 6.33 - License fee.

Science.gov (United States)

2010-01-01

... certified mail, return receipt requested, advising the licensee that if payment is not mailed in accordance.... Where the license at issue is a historical license, this will result, pursuant to § 6.23(b), in the person's loss of historical eligibility for such license. (d) Licensees may elect not to accept certain...

Research and development tasks of the basalt waste isolation program, and their relationship to the licensing process

International Nuclear Information System (INIS)

Kunkel, W.P.

1978-06-01

This document presents a preliminary licensing program and outlines the research and development strategy by which a license will be obtained for the repository. It addresses the base data covering the major areas of investigation and technology which will provide input to the licensing process. Basically, each facet of the program, as described in the plan, will be used as part of the documentation required for the Preliminary and Final Safety Analysis Report (PSAR and FSAR), as well as the Environmental Report

Intense diagnostic neutral beam development for ITER

International Nuclear Information System (INIS)

Rej, D.J.; Henins, I.; Fonck, R.J.; Kim, Y.J.

1992-01-01

For the next-generation, burning tokamak plasmas such as ITER, diagnostic neutral beams and beam spectroscopy will continue to be used to determine a variety of plasma parameters such as ion temperature, rotation, fluctuations, impurity content, current density profile, and confined alpha particle density and energy distribution. Present-day low-current, long-pulse beam technology will be unable to provide the required signal intensities because of higher beam attenuation and background bremsstrahlung radiation in these larger, higher-density plasmas. To address this problem, we are developing a short-pulse, intense diagnostic neutral beam. Protons or deuterons are accelerated using magnetic-insulated ion-diode technology, and neutralized in a transient gas cell. A prototype 25-kA, 100-kV, 1-μs accelerator is under construction at Los Alamos. Initial experiments will focus on ITER-related issues of beam energy distribution, current density, pulse length, divergence, propagation, impurity content, reproducibility, and maintenance

Neutral beam current drive with balanced injection

International Nuclear Information System (INIS)

Eckhartt, D.

1990-01-01

Current drive with fast ions has proved its capability to sustain a tokamak plasma free of externally induced electric fields in a stationary state. The suprathermal ion population within the toroidal plasma was created by quasi-tangential and uni-directional injection of high-energy neutral atoms, their ionisation and subsequent deceleration by collisions with the background plasma particles. In future large tokamaks of the NET/INTER-type, with reactor-relevant values of plasma density and temperature, this current drive scheme is expected to maintain the toroidal current at the plasma centre, as current drive by lower hybrid waves will be restricted to the outer plasma regions owing to strong wave damping. Adequate penetration of the neutral atoms through the dense plasma requires particle energies of several hundred kilovolts per nucleon since beam absorption scales roughly with the ratio beam energy over density. The realisation of such high-energy high-power neutral beams, based on negative ion technology, is now under study. (author) 7 refs., 2 figs

National negative-ion-based neutral-beam development plan

International Nuclear Information System (INIS)

Cooper, W.S.; Pyle, R.V.

1983-08-01

The plan covers facilities required, program milestones, and decision points. It includes identification of applications, experiments, theoretical research areas, development of specific technologies and reactor development and demonstration facilities required to bring about the successful application of negative-ion-based neutral beams. Particular emphasis is placed on those activities leading to use on existing plasma confinement experiments or their upgrades

MEX04/058 supporting the license renewal of the LVNPP

International Nuclear Information System (INIS)

Diaz, A.; Arganis, C.; Viais, J.; Mendoza, G.; Lucatero, M. A.; Contreras, A.

2010-10-01

Nuclear power plants in the United States are authorized to operate for 40 years. However, this 40-year period was chosen based on economic considerations and not on technological restrictions or safety aspects. In general, the operation of equipment, systems and components in a nuclear power plant is subject to rigorous maintenance and inspection monitoring under strict surveillance programs throughout their life. In fact, according to the Nuclear Energy Institute, in December 2009, 59 nuclear power plants in the United States had already reached the 40 years of the original operating license and carried out their renewal process, extending their operation for up to 20 more years. These 59 nuclear power plants carried out their renewal process, basing their operation mainly on safety reviews that validated the good working order of systems, structures and components, meeting the technical specifications required, as well as complying with the specific safety provisions for prolonging the use of a operating license. The owner is responsible for showing the Regulatory Agency that it is capable of effectively managing the aging of the systems, structures and components,guaranteeing their good working order during the renewal period. In the specific case of Mexico, Unit 1 of the Laguna Verde Nuclear Power Plant (LVNPP) has an original 30-year license, with almost 20 years of proper operation, for which, in order to request a license extension, it is necessary to begin management activities, which allow for constituting and submitting the license renewal application to the Regulatory Agency in order to continue its commercial operation. This paper presents some of most important activities carried out by Instituto Nacional de Investigaciones Nucleares and LVNPP in the international project MEX04/058, related to Plant Life Management as a support of the beginning of plant license renewal process. (Author)

25 CFR 11.601 - Marriage licenses.

Science.gov (United States)

2010-04-01

... 25 Indians 1 2010-04-01 2010-04-01 false Marriage licenses. 11.601 Section 11.601 Indians BUREAU... ORDER CODE Domestic Relations § 11.601 Marriage licenses. A marriage license shall be issued by the clerk of the court in the absence of any showing that the proposed marriage would be invalid under any...

The optimal licensing contract in a differentiated Stackelberg model.

Science.gov (United States)

Hong, Xianpei; Yang, Lijun; Zhang, Huaige; Zhao, Dan

2014-01-01

This paper extends the work of Wang (2002) by considering a differentiated Stackelberg model, when the leader firm is an inside innovator and licenses its new technology by three options, that is, fixed-fee licensing, royalty licensing, and two-part tariff licensing. The main contributions and conclusions of this paper are threefold. First of all, this paper derives a very different result from Wang (2002). We show that, with a nondrastic innovation, royalty licensing is always better than fixed-fee licensing for the innovator; with a drastic innovation, royalty licensing is superior to fixed-fee licensing for small values of substitution coefficient d; however when d becomes closer to 1, neither fee nor royalty licensing will occur. Secondly, this paper shows that the innovator is always better off in case of two-part tariff licensing than fixed-fee licensing no matter what the innovation size is. Thirdly, the innovator always prefers to license its nondrastic innovation by means of a two-part tariff instead of licensing by means of a royalty; however, with a drastic innovation, the optimal licensing strategy can be either a two-part tariff or a royalty, depending upon the differentiation of the goods.

9 CFR 108.2 - Plot plans, blueprints, and legends required.

Science.gov (United States)

2010-01-01

... 9 Animals and Animal Products 1 2010-01-01 2010-01-01 false Plot plans, blueprints, and legends... REQUIREMENTS FOR LICENSED ESTABLISHMENTS § 108.2 Plot plans, blueprints, and legends required. Each applicant for an establishment license shall prepare a plot plan showing all buildings for each particular land...

Macroscopic cross sections for analyzing the transport of neutral particles in plasmas

International Nuclear Information System (INIS)

Suzuki, Tadakazu; Taji, Yuukichi; Nakahara, Yasuaki

1975-05-01

Algorithms have been developed for calculating the ionization and charge exchange cross sections required for analyzing the neutral transport in plasmas. In our algorithms, the integration of the expression for reaction rate of neutrals with plasmas is performed by expanding the integrand with the use of polynomials. At present, multi-energy-group sets of the cross sections depending on plasma temperature and energy of neutrals can be prepared by means of Maxwellian averages over energy. Calculational results are printed out in the FIDO format. Some numerical examples are given for several forms of spatial distributions assumed for the plasma ion temperature and source neutral energy. (auth.)

Calculation of neutral beam deposition accounting for excited states

International Nuclear Information System (INIS)

Gianakon, T.A.

1992-09-01

Large-scale neutral-beam auxillary heating of plasmas has led to new plasma operational regimes which are often dominated by fast ions injected via the absorption of an energetic beam of hydrogen neutrals. An accurate simulation of the slowing down and transport of these fast ions requires an intimate knowledge of the hydrogenic neutral deposition on each flux surface of the plasma. As a refinement to the present generation of transport codes, which base their beam deposition on ground-state reaction rates, a new set of routines, based on the excited states of hydrogen, is presented as mechanism for computing the attenuation and deposition of a beam of energetic neutrals. Additionally, the numerical formulations for the underlying atomic physics for hydrogen impacting on the constiuent plasma species is developed and compiled as a numerical database. Sample results based on this excited state model are compared with the ground-state model for simple plasma configurations

Recruitment training and licensing of operating personnel for nuclear power plants

International Nuclear Information System (INIS)

Palabrica, R.J.

1979-01-01

This article covers the step-by-step and most rigid recruitment, training, and licensing procedures undertaken in the selection for personnel involved in nuclear power plant operations. These procedures are true to all countries. However, for developing countries such as the Philippines, a bachelor's degree may be required as compared with the U.S. wherein a high school diploma is the minimum requirement. Because of the complexity of a nuclear facility, the work will require highly capable individuals with mature judgement who can render correct decisions even under highly stressed conditions. Thus during the selection and recruitment of applicants for the operator position, they are not only given aptitude tests but are also subjected to a series of psychological examintions. Once they are accepted, they are made to undergo a comprehensive and in-depth training to ensure that they will be capable of operating the nuclear power plant safely and effectively. Finally, those prospective operators have to pass licensing examinations in order to prove their competence and skills. Retraining programs follow after their training to maintain their skills. (RTD)

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

Groundwater leaching of neutralized and untreated acid-leached uranium-mill tailings

International Nuclear Information System (INIS)

Gee, G.W.; Begej, C.W.; Campbell, A.C.; Sauter, N.N.; Opitz, B.E.; Sherwood, D.R.

1981-01-01

Tailings neutralization was examined to determine the effect of neutralization on contaminant release. Column leaching of acid extracted uranium mill tailings from Exxon Highland Mill, Wyoming, Pathfinder Gas Hills Mill, Wyoming, and the Dawn Midnite Mill, Washington, resulted in the flushing of high concentrations of salts in the first four pore volumes of leachate, followed by a steady decrease to the original groundwater salt concentrations. Neutralization decreased the concentration of salts and radionuclides leaching from the tailings and decreased the volume of solution required to return the solution to the groundwater pH and EC. Radium-226 and uranium-238 leached quickly from the tailings in the initial pore volumes of both neutralized and unneutralized tailings, and then decreased significantly. 6 figures, 5 tables

AVC/H.264 patent portfolio license

Science.gov (United States)

Skandalis, Dean A.

2006-08-01

MPEG LA, LLC offers a joint patent license for the AVC (a/k/a H.264) Standard (ISO/IEC IS 14496-10:2004). Like MPEG LA's other licenses, the AVC Patent Portfolio License is offered for the convenience of the marketplace as an alternative enabling users to access essential intellectual property owned by many patent holders under a single license rather than negotiating licenses with each of them individually. The AVC Patent Portfolio License includes essential patents owned by DAEWOO Electronics Corporation; Electronics and Telecommunications Research Institute (ETRI); France Telecom, societe anonyme; Fujitsu Limited; Hitachi, Ltd.; Koninklijke Philips Electronics N.V.; LG Electronics Inc.; Matsushita Electric Industrial Co., Ltd.; Microsoft Corporation; Mitsubishi Electric Corporation; Robert Bosch GmbH; Samsung Electronics Co., Ltd.; Sedna Patent Services, LLC; Sharp Kabushiki Kaisha; Siemens AG; Sony Corporation; The Trustees of Columbia University in the City of New York; Toshiba Corporation; UB Video Inc.; and Victor Company of Japan, Limited. Another is expected also to join as of August 1, 2006. MPEG LA's objective is to provide worldwide access to as much AVC essential intellectual property as possible for the benefit of AVC users. Therefore, any party that believes it has essential patents is welcome to submit them for evaluation of their essentiality and inclusion in the License if found essential.

ACR: Licensing and design readiness

International Nuclear Information System (INIS)

Alizadeh, A.

2009-01-01

Full text The Canadian nuclear technology has a long history dating back to the 1940s. In this regard, Canada is in a unique situation, shared only by a very few countries, where original nuclear power technology has been invented and further developed. Canadian Nuclear Safety Commission (CNSC), then called AECB, was established in 1946. CNSC focuses on nuclear security, nuclear safety, establishing health and safety regulations, and has also played an instrumental role in the formation of the IAEA. CNSC has provided assistance to the establishment of regulatory authorities in AECL's client countries such as Korea, Argentina, China and Romania. AECL has developed the Gen III+ ACR 1000 as evolutionary advancement of the current CANDU 6 reactor. ACR-1000 has evolved from AECL's in depth experience with CANDU systems, components, and materials, as well as the feedback received from owners and operators of CANDU plants. The ACR-1000 design retains the proven strengths and features of CANDU reactors, while incorporating innovations and state-of-the-art technology. It also features major improvements in economics, inherent safety characteristics, and performance. ACR-1000 has completed its Basic Engineering, has advanced in the licensing process in Canada, and is ready for deployment in Canadian and world markets. EC6 is an evolution of CANDU 6 and is a Gen III natural uranium fuelled reactor. Its medium size and potential for fuel localization and advanced fuel cycles is an optimal strategic solution in many markets.AECL's reactor products are shown to be compliant with a variety of licensing and regulatory requirements. These include the new CNSC DRD-337, IAEA NS-R1, and EUR. This allows the countries interested in CANDU reactor products to be confident of its licensing in their own regulatory regimes.

Study of neutral particles

International Nuclear Information System (INIS)

Bartel, W.; Bulos, F.; Eisner, A.

1975-01-01

The range of physics problems for which a detector emphasizing neutrals is most suitable is discussed. The primary goals are the all neutrals cross section, sigma/sub o/ (e + e - → neutrals), the characterization of the neutral energy in multi-hadronic events, the search for monoenergetic photons, and good sensitivity in the difficult region of low energy photons. Those features of multi-hadronic events which are most relevant to a neutral detector were calculated using a jet model with parameters extrapolated from SPEAR energies. These distributions are presented and discussed

The Optimal Licensing Contract in a Differentiated Stackelberg Model

Directory of Open Access Journals (Sweden)

Xianpei Hong

2014-01-01

Full Text Available This paper extends the work of Wang (2002 by considering a differentiated Stackelberg model, when the leader firm is an inside innovator and licenses its new technology by three options, that is, fixed-fee licensing, royalty licensing, and two-part tariff licensing. The main contributions and conclusions of this paper are threefold. First of all, this paper derives a very different result from Wang (2002. We show that, with a nondrastic innovation, royalty licensing is always better than fixed-fee licensing for the innovator; with a drastic innovation, royalty licensing is superior to fixed-fee licensing for small values of substitution coefficient d; however when d becomes closer to 1, neither fee nor royalty licensing will occur. Secondly, this paper shows that the innovator is always better off in case of two-part tariff licensing than fixed-fee licensing no matter what the innovation size is. Thirdly, the innovator always prefers to license its nondrastic innovation by means of a two-part tariff instead of licensing by means of a royalty; however, with a drastic innovation, the optimal licensing strategy can be either a two-part tariff or a royalty, depending upon the differentiation of the goods.