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Sample records for preliminary acceptance criteria

  1. Preliminary Mark-18A (Mk-18A) Target Material Recovery Program Product Acceptance Criteria

    Energy Technology Data Exchange (ETDEWEB)

    Robinson, Sharon M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Patton, Bradley D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2016-09-01

    The Mk-18A Target Material Recovery Program (MTMRP) was established in 2015 to preserve the unique materials, e.g. 244Pu, in 65 previously irradiated Mk-18A targets for future use. This program utilizes existing capabilities at SRS and Savannah River National Laboratory (SRNL) to process targets, recover materials from them, and to package the recovered materials for shipping to ORNL. It also utilizes existing capabilities at ORNL to receive and store the recovered materials, and to provide any additional processing of the recovered materials or residuals required to prepare them for future beneficial use. The MTMRP is presently preparing for the processing of these valuable targets which is expected to begin in ~2019. As part of the preparations for operations, this report documents the preliminary acceptance criteria for the plutonium and heavy curium materials to be recovered from the Mk-18A targets at SRNL for transport and storage at ORNL. These acceptance criteria were developed based on preliminary concepts developed for processing, transporting, and storing the recovered Mk-18A materials. They will need to be refined as these concepts are developed in more detail.

  2. Preliminary Mark-18A (Mk-18A) Target Material Recovery Program Product Acceptance Criteria

    International Nuclear Information System (INIS)

    Robinson, Sharon M.; Patton, Bradley D.

    2016-01-01

    The Mk-18A Target Material Recovery Program (MTMRP) was established in 2015 to preserve the unique materials, e.g. 244 Pu, in 65 previously irradiated Mk-18A targets for future use. This program utilizes existing capabilities at SRS and Savannah River National Laboratory (SRNL) to process targets, recover materials from them, and to package the recovered materials for shipping to ORNL. It also utilizes existing capabilities at ORNL to receive and store the recovered materials, and to provide any additional processing of the recovered materials or residuals required to prepare them for future beneficial use. The MTMRP is presently preparing for the processing of these valuable targets which is expected to begin in ~2019. As part of the preparations for operations, this report documents the preliminary acceptance criteria for the plutonium and heavy curium materials to be recovered from the Mk-18A targets at SRNL for transport and storage at ORNL. These acceptance criteria were developed based on preliminary concepts developed for processing, transporting, and storing the recovered Mk-18A materials. They will need to be refined as these concepts are developed in more detail.

  3. Waste acceptance criteria study: Volume 2, Appendixes: Final report

    International Nuclear Information System (INIS)

    Johnson, E.R.; McLeod, N.B.; McBride, J.A.

    1988-09-01

    These appendices to the report on Waste Acceptance Criteria have been published as a separate volume for the convenience of the reader. They consist of the text of the 10CFR961 Contract for disposal of spent fuel, estimates of the cost (savings) to the DOE system of accepting different forms of spent fuel, estimates of costs of acceptance testing/inspection of spent fuel, illustrative specifications and procedures, and the resolution of comments received on a preliminary draft of the report. These estimates of costs contained herein preliminary and are intended only to demonstrate the trends in costs, the order of magnitude involved, and the methodology used to develop the costs. The illustrative specifications and procedures included herein have been developed for the purpose of providing a starting point for the development of a consensus on such matters between utilities and DOE

  4. Anticipating Potential Waste Acceptance Criteria for Defense Spent Nuclear Fuel

    International Nuclear Information System (INIS)

    Rechard, R.P.; Lord, M.E.; Stockman, C.T.; McCurley, R.D.

    1997-01-01

    The Office of Environmental Management of the U.S. Department of Energy is responsible for the safe management and disposal of DOE owned defense spent nuclear fuel and high level waste (DSNF/DHLW). A desirable option, direct disposal of the waste in the potential repository at Yucca Mountain, depends on the final waste acceptance criteria, which will be set by DOE's Office of Civilian Radioactive Waste Management (OCRWM). However, evolving regulations make it difficult to determine what the final acceptance criteria will be. A method of anticipating waste acceptance criteria is to gain an understanding of the DOE owned waste types and their behavior in a disposal system through a performance assessment and contrast such behavior with characteristics of commercial spent fuel. Preliminary results from such an analysis indicate that releases of 99Tc and 237Np from commercial spent fuel exceed those of the DSNF/DHLW; thus, if commercial spent fuel can meet the waste acceptance criteria, then DSNF can also meet the criteria. In large part, these results are caused by the small percentage of total activity of the DSNF in the repository (1.5%) and regulatory mass (4%), and also because commercial fuel cladding was assumed to provide no protection

  5. Preliminary waste acceptance requirements for the planned Konrad repository

    International Nuclear Information System (INIS)

    Warnecke, E.; Brennecke, P.

    1987-01-01

    The Physikalisch-Technische Bundesanstalt (PTB) has established Preliminary Waste Acceptance Requirements for the planned Konrad repository. These requirements were developed, in accordance with the Safety Criteria of the Reactor Safety Commission, with the help of a site specific safety assessment; they are under the reservation of the plan approval procedure, which is still in progress. In developing waste acceptance requirements, the PTB fulfills one of its duties as the institute responsible for waste disposal and gives guidelines for waste conditioning to waste producers and conditioners. (orig.) [de

  6. A comparison and cross-reference of commercial low-level radioactive waste acceptance criteria

    International Nuclear Information System (INIS)

    Kerr, T.A.

    1997-04-01

    This document, prepared by the National Low-Level Waste Management Program at the Idaho National Engineering and Environmental Laboratory, is a comparison and cross-reference of commercial low-level radioactive waste acceptance criteria. Many of these are draft or preliminary criteria as well as implemented criteria at operating low-level radioactive waste management facilities. Waste acceptance criteria from the following entities are included: US Nuclear Regulatory Commission, South Carolina, Washington, Utah, Nevada, California, illinois, Texas, North Carolina, Nebraska, Pennsylvania, New York, and the Midwest Compact Region. Criteria in the matrix include the following: physical form, chemical form, liquid limits, void space in packages, concentration averaging, types of packaging, chelating agents, solidification media, stability requirements, sorptive media, gas, oil, biological waste, pyrophorics, source material, special nuclear material, package dimensions, incinerator ash, dewatered resin, transuranics, and mixed waste. Each criterion in the matrix is cross-referenced to its source document so that exact requirements can be determined

  7. Hanford Site solid waste acceptance criteria

    International Nuclear Information System (INIS)

    Ellefson, M.D.

    1998-01-01

    Order 5820.2A requires that each treatment, storage, and/or disposal facility (referred to in this document as TSD unit) that manages low-level or transuranic waste (including mixed waste and TSCA PCB waste) maintain waste acceptance criteria. These criteria must address the various requirements to operate the TSD unit in compliance with applicable safety and environmental requirements. This document sets forth the baseline criteria for acceptance of radioactive waste at TSD units operated by WMH. The criteria for each TSD unit have been established to ensure that waste accepted can be managed in a manner that is within the operating requirements of the unit, including environmental regulations, DOE Orders, permits, technical safety requirements, waste analysis plans, performance assessments, and other applicable requirements. Acceptance criteria apply to the following TSD units: the Low-Level Burial Grounds (LLBG) including both the nonregulated portions of the LLBG and trenches 31 and 34 of the 218-W-5 Burial Ground for mixed waste disposal; Central Waste Complex (CWC); Waste Receiving and Processing Facility (WRAP); and T Plant Complex. Waste from all generators, both from the Hanford Site and from offsite facilities, must comply with these criteria. Exceptions can be granted as provided in Section 1.6. Specific waste streams could have additional requirements based on the 1901 identified TSD pathway. These requirements are communicated in the Waste Specification Records (WSRds). The Hanford Site manages nonradioactive waste through direct shipments to offsite contractors. The waste acceptance requirements of the offsite TSD facility must be met for these nonradioactive wastes. This document does not address the acceptance requirements of these offsite facilities

  8. Development of performance assessment methodology for establishment of quantitative acceptance criteria of near-surface radioactive waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Kim, C. R.; Lee, E. Y.; Park, J. W.; Chang, G. M.; Park, H. Y.; Yeom, Y. S. [Korea Hydro and Nuclear Power Co., Ltd., Seoul (Korea, Republic of)

    2002-03-15

    The contents and the scope of this study are as follows : review of state-of-the-art on the establishment of waste acceptance criteria in foreign near-surface radioactive waste disposal facilities, investigation of radiological assessment methodologies and scenarios, investigation of existing models and computer codes used in performance/safety assessment, development of a performance assessment methodology(draft) to derive quantitatively radionuclide acceptance criteria of domestic near-surface disposal facility, preliminary performance/safety assessment in accordance with the developed methodology.

  9. Hanford Site Solid Waste Acceptance Criteria

    Energy Technology Data Exchange (ETDEWEB)

    1993-11-17

    This manual defines the Hanford Site radioactive, hazardous, and sanitary solid waste acceptance criteria. Criteria in the manual represent a guide for meeting state and federal regulations; DOE Orders; Hanford Site requirements; and other rules, regulations, guidelines, and standards as they apply to acceptance of radioactive and hazardous solid waste at the Hanford Site. It is not the intent of this manual to be all inclusive of the regulations; rather, it is intended that the manual provide the waste generator with only the requirements that waste must meet in order to be accepted at Hanford Site TSD facilities.

  10. Hanford Site Solid Waste Acceptance Criteria

    International Nuclear Information System (INIS)

    1993-01-01

    This manual defines the Hanford Site radioactive, hazardous, and sanitary solid waste acceptance criteria. Criteria in the manual represent a guide for meeting state and federal regulations; DOE Orders; Hanford Site requirements; and other rules, regulations, guidelines, and standards as they apply to acceptance of radioactive and hazardous solid waste at the Hanford Site. It is not the intent of this manual to be all inclusive of the regulations; rather, it is intended that the manual provide the waste generator with only the requirements that waste must meet in order to be accepted at Hanford Site TSD facilities

  11. NEVADA TEST SITE WASTE ACCEPTANCE CRITERIA

    International Nuclear Information System (INIS)

    U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION, NEVADA SITE OFFICE

    2005-01-01

    This document establishes the U. S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive and mixed waste for disposal. Mixed waste generated within the State of Nevada by NNSA/NSO activities is accepted for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the Nevada Test Site Area 3 and Area 5 Radioactive Waste Management Site for storage or disposal

  12. Nevada Test Site Waste Acceptance Criteria, December 2000

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-12-01

    This document establishes the US Department of Energy, Nevada Operations Office waste acceptance criteria. The waste acceptance criteria provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive waste and mixed waste for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the Nevada Test Site Area 3 and Area 5 Radioactive Waste Management Sites for storage or disposal.

  13. Nevada Test Site Waste Acceptance Criteria, December 2000

    International Nuclear Information System (INIS)

    2000-01-01

    This document establishes the US Department of Energy, Nevada Operations Office waste acceptance criteria. The waste acceptance criteria provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive waste and mixed waste for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the Nevada Test Site Area 3 and Area 5 Radioactive Waste Management Sites for storage or disposal

  14. Idaho CERCLA Disposal Facility Complex Waste Acceptance Criteria

    Energy Technology Data Exchange (ETDEWEB)

    W. Mahlon Heileson

    2006-10-01

    The Idaho Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Disposal Facility (ICDF) has been designed to accept CERCLA waste generated within the Idaho National Laboratory. Hazardous, mixed, low-level, and Toxic Substance Control Act waste will be accepted for disposal at the ICDF. The purpose of this document is to provide criteria for the quantities of radioactive and/or hazardous constituents allowable in waste streams designated for disposal at ICDF. This ICDF Complex Waste Acceptance Criteria is divided into four section: (1) ICDF Complex; (2) Landfill; (3) Evaporation Pond: and (4) Staging, Storage, Sizing, and Treatment Facility (SSSTF). The ICDF Complex section contains the compliance details, which are the same for all areas of the ICDF. Corresponding sections contain details specific to the landfill, evaporation pond, and the SSSTF. This document specifies chemical and radiological constituent acceptance criteria for waste that will be disposed of at ICDF. Compliance with the requirements of this document ensures protection of human health and the environment, including the Snake River Plain Aquifer. Waste placed in the ICDF landfill and evaporation pond must not cause groundwater in the Snake River Plain Aquifer to exceed maximum contaminant levels, a hazard index of 1, or 10-4 cumulative risk levels. The defined waste acceptance criteria concentrations are compared to the design inventory concentrations. The purpose of this comparison is to show that there is an acceptable uncertainty margin based on the actual constituent concentrations anticipated for disposal at the ICDF. Implementation of this Waste Acceptance Criteria document will ensure compliance with the Final Report of Decision for the Idaho Nuclear Technology and Engineering Center, Operable Unit 3-13. For waste to be received, it must meet the waste acceptance criteria for the specific disposal/treatment unit (on-Site or off-Site) for which it is destined.

  15. Risk acceptance criteria of the Nuclear Regulatory Authority

    International Nuclear Information System (INIS)

    Felizia, Eduardo R.

    2005-01-01

    This report describes some of the regulatory and control functions legally conferred upon the Argentine Nuclear Regulatory Authority concerning radiological risks, as well as a critical analysis of the radiological risk acceptance criteria contained in the Argentine regulatory system. A summary of the application of regulatory standards AR 3.1.3. - 'Radiological criteria related to accidents in nuclear power reactors' and AR 4.1.3. - 'Radiological criteria related to accidents in research reactors' to concrete cases is made, while the favourable and unfavourable aspects of the risk acceptance criteria are discussed. The conclusion is that the Argentine regulatory system contains adequate radiological risk acceptance criteria, that the latter are consistent with the radiological protection principles applicable to man and that, for the moment, there is no need to perform any modifications that would broaden the conceptual framework on which such criteria are based. (author) [es

  16. Nevada Test Site Waste Acceptance Criteria

    International Nuclear Information System (INIS)

    U. S. Department of Energy, National Nuclear Security Administration Nevada Site Office

    2005-01-01

    This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive (LLW) and mixed waste (MW) for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex (RWMC) for storage or disposal

  17. Inelastic analysis acceptance criteria for radioactive material transportation containers

    International Nuclear Information System (INIS)

    Ammerman, D.J.; Ludwigsen, J.S.

    1993-01-01

    The design criteria currently used in the design of radioactive material (RAM) transportation containers are taken from the ASME Boiler and Pressure Vessel Code (ASME, 1992). These load-based criteria are ideally suited for pressure vessels where the loading is quasistatic and all stresses are in equilibrium with externally applied loads. For impact events, the use of load-based criteria is less supportable. Impact events tend to be energy controlled, and thus, energy-based acceptance criteria would appear to be more appropriate. Determination of an ideal design criteria depends on what behavior is desired. Currently there is not a design criteria for inelastic analysis for RAM nation packages that is accepted by the regulatory agencies. This lack of acceptance criteria is one of the major factors in limiting the use of inelastic analysis. In this paper inelastic analysis acceptance criteria based on stress and strain-energy density will be compared for two stainless steel test units subjected to impacts onto an unyielding target. Two different material models are considered for the inelastic analysis, a bilinear fit of the stress-strain curve and a power law hardening model that very closely follows the stress-strain curve. It is the purpose of this paper to stimulate discussion and research into the area of strain-energy density based inelastic analysis acceptance criteria

  18. Reality check on girth weld defect acceptance criteria

    Energy Technology Data Exchange (ETDEWEB)

    Brust, Bud; Kalyanam, Suresh; Shim, Do-Jun; Wilkowski, Gery [Engineering Mechanics Corporation of Columbus, Columbus, OH, (United States)

    2010-07-01

    Girth weld defect tolerance criteria for pipeline construction has evolved with time. Recently, ERPG recommended a new Tier 2 girth weld defect acceptance criterion. This paper described the new development on girth weld defect acceptance criteria. The inherent conservatisms of alternative girth weld defect acceptance criteria from the 2007 API 1104 Appendix A, CSA Z662 Appendix K, are compared to those from the proposed EPRG Tier 2 criteria. It is found that the API and CSA codes have the same empirical limit-load criteria. As well, there are conservatisms in the proposed EPRG Tier 2. The results showed that there are various reasons why large amounts of conservatism in the allowable flaw lengths in the CSA Appendix K,2007 API 1104 Appendix A, and proposed EPRG Tier 2 girth weld defect criterion exist. Small conservatisms on failure stress can result in large conservatisms in flaw size.

  19. Risk Acceptance Criteria and/or Decision optimization

    DEFF Research Database (Denmark)

    Ditlevsen, Ove Dalager

    1996-01-01

    Acceptance criteria applied in practical risk analysis are recapitulated including the concept of rist profile. Modelling of risk profiles is illustrated on the basis of compound Poisson process models. The current practice of authoritative acceptance criteria formulation is discussed from...... a decision theoretical point of view. It is argued that the phenomenon of risk aversion rather than being of concern to the authority should be of concern to the owner. Finally it is discussed whether there is an ethical problem when formally capitalising human lives with a positive interest rate. Keywords......: Risk acceptance, Risk profile, Compound Poisson model for risk profile, Capitalization of human life, Risk aversion....

  20. Design Criteria for Achieving Acceptable Indoor Radon Concentration

    DEFF Research Database (Denmark)

    Rasmussen, Torben Valdbjørn

    2016-01-01

    Design criteria for achieving an acceptable indoor radon concentration are presented in this paper. The paper suggests three design criteria. These criteria have to be considered at the early stage of the building design phase to meet the latest recommendations from the World Health Organization...... in most countries. The three design criteria are; first, establishing a radon barrier facing the ground; second, lowering the air pressure in the lower zone of the slab on ground facing downwards; third, diluting the indoor air with outdoor air. The first two criteria can prevent radon from infiltrating...... from the ground, and the third criteria can dilute the indoor air. By combining these three criteria, the indoor radon concentration can be lowered achieving an acceptable level. In addition, a cheap and reliable method for measuring the radon concentration in the indoor air is described. The provision...

  1. Radwaste characteristics and Disposal Facility Waste Acceptance Criteria

    International Nuclear Information System (INIS)

    Sung, Suk Hyun; Jeong, Yi Yeong; Kim, Ki Hong

    2008-01-01

    The purpose of Radioactive Waste Acceptance Criteria (WAC) is to verify a radioactive waste compliance with radioactive disposal facility requirements in order to maintain a disposal facility's performance objectives and to ensure its safety. To develop WAC which is conformable with domestic disposal site conditions, we furthermore analysed the WAC of foreign disposal sites similar to the Kyung-Ju disposal site and the characteristics of various wastes which are being generated from Korea nuclear facilities. Radioactive WAC was developed in the technical cooperation with the Korea Atomic Energy Research Institute in consideration of characteristics of the wastes which are being generated from various facilities, waste generators' opinions and other conditions. The established criteria was also discussed and verified at an advisory committee which was comprised of some experts from universities, institutes and the industry. So radioactive WAC was developed to accept all wastes which are being generated from various nuclear facilities as much as possible, ensuring the safety of a disposal facility. But this developed waste acceptance criteria is not a criteria to accept all the present wastes generated from various nuclear facilities, so waste generators must seek an alternative treatment method for wastes which were not worth disposing of, and then they must treat the wastes more to be acceptable at a disposal site. The radioactive disposal facility WAC will continuously complement certain criteria related to a disposal concentration limit for individual radionuclide in order to ensure a long-term safety.

  2. Structural acceptance criteria Remote Handling Building Tritium Extraction Facility

    Energy Technology Data Exchange (ETDEWEB)

    Mertz, G.

    1999-12-16

    This structural acceptance criteria contains the requirements for the structural analysis and design of the Remote Handling Building (RHB) in the Tritium Extraction Facility (TEF). The purpose of this acceptance criteria is to identify the specific criteria and methods that will ensure a structurally robust building that will safely perform its intended function and comply with the applicable Department of Energy (DOE) structural requirements.

  3. Structural acceptance criteria Remote Handling Building Tritium Extraction Facility

    International Nuclear Information System (INIS)

    Mertz, G.

    1999-01-01

    This structural acceptance criteria contains the requirements for the structural analysis and design of the Remote Handling Building (RHB) in the Tritium Extraction Facility (TEF). The purpose of this acceptance criteria is to identify the specific criteria and methods that will ensure a structurally robust building that will safely perform its intended function and comply with the applicable Department of Energy (DOE) structural requirements

  4. Nevada National Security Site Waste Acceptance Criteria

    International Nuclear Information System (INIS)

    2012-01-01

    This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept DOE non-radioactive classified waste, DOE non-radioactive hazardous classified waste, DOE low-level radioactive waste (LLW), DOE mixed low-level waste (MLLW), and U.S. Department of Defense (DOD) classified waste for permanent disposal. Classified waste is the only waste accepted for disposal that may be non-radioactive and will be required to meet the waste acceptance criteria for radioactive waste as specified in this document. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project (WMP) at (702) 295-7063, and your call will be directed to the appropriate contact.

  5. Nevada National Security Site Waste Acceptance Criteria

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Management

    2012-02-28

    This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept DOE non-radioactive classified waste, DOE non-radioactive hazardous classified waste, DOE low-level radioactive waste (LLW), DOE mixed low-level waste (MLLW), and U.S. Department of Defense (DOD) classified waste for permanent disposal. Classified waste is the only waste accepted for disposal that may be non-radioactive and will be required to meet the waste acceptance criteria for radioactive waste as specified in this document. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project (WMP) at (702) 295-7063, and your call will be directed to the appropriate contact.

  6. Waste-acceptance criteria for greater confinement disposal

    International Nuclear Information System (INIS)

    Gilbert, T.L.; Meshkov, N.K.

    1987-01-01

    A methodology for establishing waste-acceptance criteria based on quantitative performance factors that characterize the confinement capabilities of a waste disposal site and facility has been developed. The methodology starts from the basic objective of protecting public health and safety by providing assurance that disposal of the waste will not result in a radiation dose to any member of the general public, in either the short or long term, in excess of an established basic dose limit. The method is based on an explicit, straight-forward, and quantitative relationship among individual risk, confinement capabilities, and waste characteristics. A key aspect of the methodology is introduction of a confinement factor that characterizes the overall confinement capability of a particular facility and can be used for quantitative assessments of the performance of different disposal sites and facilities, as well as for establishing site-specific waste acceptance criteria. Confinement factors are derived by means of site-specific pathway analyses. They make possible a direct and simple conversion of a basic dose limit into waste-acceptance criteria, specified as concentration limits on radionuclides in the waste streams and expressed in quantitative form as a function of parameters that characterize the site, facility design, waste containers, and waste form. Waste acceptance criteria can be represented visually as activity/time plots for various waste streams. These plots show the concentrations of radionuclides in a waste stream as a function of time and permit a visual, quantitative assessment of long-term performance, relative risks from different radionuclides in the waste stream, and contributions from ingrowth. 13 references, 7 figures

  7. Waste-acceptance criteria for greater-confinement disposal

    International Nuclear Information System (INIS)

    Gilbert, T.L.; Meshkov, N.K.

    1986-01-01

    A methodology for establishing waste-acceptance criteria based on quantitative performance factors that characterize the confinement capabilities of a waste-disposal site and facility has been developed. The methodology starts from the basic objective of protecting public health and safety by providing assurance that dispsoal of the waste will not result in a radiation dose to any member of the general public, in either the short or long term, in excess of an established basic dose limit. The method is based on an explicit, straightforward, and quantitative relationship among individual risk, confinement capabilities, and waste characteristics. A key aspect of the methodology is the introduction of a confinement factor that characterizes the overall confinement capability of a particular facility and can be used for quantitative assessments of the performance of different disposal sites and facilities, as well as for establishing site-specific waste-acceptance criteria. Confinement factors are derived by means of site-specific pathway analyses. They make possible a direct and simple conversion of a basic dose limit into waste-acceptance criteria, specified as concentration limits on radionuclides in the waste streams and expressed in quantitative form as a function of parameters that characterize the site, facility design, waste containers, and waste form. Waste-acceptance criteria can be represented visually as activity/time plots for various waste streams. These plots show the concentrations of radionuclides in a waste stream as a function of time and permit a visual, quantitative assessment of long-term performance, relative risks from different radionuclides in the waste stream, and contributions from ingrowth. 13 refs

  8. Nevada Test Site Waste Acceptance Criteria (NTSWAC)

    Energy Technology Data Exchange (ETDEWEB)

    NNSA/NSO Waste Management Project

    2008-06-01

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive (LLW) and LLW Mixed Waste (MW) for disposal.

  9. Nevada Test Site Waste Acceptance Criteria (NTSWAC)

    International Nuclear Information System (INIS)

    NNSA/NSO Waste Management Project

    2008-01-01

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive (LLW) and LLW Mixed Waste (MW) for disposal

  10. Toxic chemical risk acceptance criteria

    International Nuclear Information System (INIS)

    Craig, D.K.; Davis, J.; Lee, L.; Lein, P.; Omberg, S.

    1992-01-01

    This paper presents recommendations of a subcommittee of the Westinghouse M ampersand 0 Nuclear Facility Safety Committee concerning toxic chemical risk acceptance criteria. Two sets of criteria have been developed, one for use in the hazard classification of facilities, and the second for use in comparing risks in DOE non-reactor nuclear facility Safety Analysis Reports. The Emergency Response Planning Guideline (ERPG) values are intended to provide estimates of concentration ranges for specific chemicals above which exposure would be expected to lead to adverse heath effects of increasing severity for ERPG-1, -2, and -3s. The subcommittee recommends that criteria for hazard class or risk range be based on ERPGs for all chemicals. Probability-based Incremental Cancer Risk (ICR) criteria are recommended for additional analyses of risks from all known or suspected human carcinogens. Criteria are given for both on-site and off-site exposure. The subcommittee also recommends that the 5-minute peak concentration be compared with the relevant criterion with no adjustment for exposure time. Since ERPGs are available for only a limited number of chemicals, the subcommittee has developed a proposed hierarchy of concentration limit parameters for the different criteria

  11. Application of trial risk acceptance criteria

    International Nuclear Information System (INIS)

    Johnson, D.H.; Kastenberg, W.E.; Okrent, D.

    1982-01-01

    The objective of this paper is to investigate some of the implications inherent in the application of various proposed sets of risk acceptance criteria. A power-law model of risk aversion is utilized to estimate the equivalent number of individual deaths and is treated parametrically. The implications of ALARA requirements for cost-effective improvements are also illustrated. The risks assessed for various technological endeavors, as well as some estimated natural background risks, are compared to the trial criteria

  12. Environmental Restoration Disposal Facility Waste Acceptance Criteria

    International Nuclear Information System (INIS)

    Dronen, V.R.

    1998-06-01

    The Hanford Site is operated by the U. S. Department of Energy (DOE) with a primary mission of environmental cleanup and restoration. The Environmental Restoration Disposal Facility (ERDF) is an integral part of the DOE environmental restoration effort at the Hanford Site. The purpose of this document is to establish the ERDF waste acceptance criteria for disposal of materials resulting from Hanford Site cleanup activities. Definition of and compliance with the requirements of this document will enable implementation of appropriate measures to protect human health and the environment, ensure the integrity of the ERDF liner system, facilitate efficient use of the available space in the ERDF, and comply with applicable environmental regulations and DOE orders. To serve this purpose, the document defines responsibilities, identifies the waste acceptance process, and provides the primary acceptance criteria and regulatory citations to guide ERDF users. The information contained in this document is not intended to repeat or summarize the contents of all applicable regulations

  13. Nevada National Security Site Waste Acceptance Criteria

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2013-06-01

    This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept the following: • DOE hazardous and non-hazardous non-radioactive classified waste • DOE low-level radioactive waste (LLW) • DOE mixed low-level waste (MLLW) • U.S. Department of Defense (DOD) classified waste The LLW and MLLW listed above may also be classified waste. Classified waste is the only waste accepted for disposal that may be non-radioactive and shall be required to meet the waste acceptance criteria for radioactive waste as specified in this document. Classified waste may be sent to the NNSS as classified matter. Section 3.1.18 provides the requirements that must be met for permanent burial of classified matter. The NNSA/NFO and support contractors are available to assist the generator in understanding or interpreting this document. For assistance, please call the NNSA/NFO Environmental Management Operations (EMO) at (702) 295-7063, and the call will be directed to the appropriate contact.

  14. Nevada National Security Site Waste Acceptance Criteria

    International Nuclear Information System (INIS)

    2013-01-01

    This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept the following: DOE hazardous and non-hazardous non-radioactive classified waste; DOE low-level radioactive waste (LLW); DOE mixed low-level waste (MLLW); and, U.S. Department of Defense (DOD) classified waste. The LLW and MLLW listed above may also be classified waste. Classified waste is the only waste accepted for disposal that may be non-radioactive and shall be required to meet the waste acceptance criteria for radioactive waste as specified in this document. Classified waste may be sent to the NNSS as classified matter. Section 3.1.18 provides the requirements that must be met for permanent burial of classified matter. The NNSA/NFO and support contractors are available to assist the generator in understanding or interpreting this document. For assistance, please call the NNSA/NFO Environmental Management Operations (EMO) at (702) 295-7063, and the call will be directed to the appropriate contact.

  15. Preliminary waste acceptance requirements - Konrad repository project

    International Nuclear Information System (INIS)

    Brennecke, P.W.; Warnecke, E.H.

    1991-01-01

    In Germany, the planned Konrad repository is proposed for the disposal of all types of radioactive wastes whose thermal influence upon the host rock is negligible. The Bundesamt fuer Strahlenschutz has established Preliminary Waste Acceptance Requirements (as of April 1990) for this facility. The respective requirements were developed on the basis of the results of site-specific safety assessments. They include general requirements on the waste packages to be disposed of as well as more specific requirements on the waste forms, the packaging and the radionuclide inventory per waste package. In addition, the delivery of waste packages was regulated. An outline of the structure and the elements of the Preliminary Waste Acceptance Requirements of April 1990 is given including comments on their legal status. (Author)

  16. Automated Transportation Management System (ATMS) V2.0 logistics module PBI acceptance criteria

    International Nuclear Information System (INIS)

    Weidert, R.S.

    1995-01-01

    This document defines the acceptance criteria for the Automated Transportation Management System V2.0 Logistics Module Performance Based Incentive (PBI). This acceptance criteria will be the primary basis for the generation of acceptance test procedures. The purpose of this document is to define the minimum criteria that must be fulfilled to guarantee acceptance of the Logistics Module

  17. Acceptance criteria for the evaluation of nuclear power reactor security plans

    International Nuclear Information System (INIS)

    1982-08-01

    This guidance document contains acceptance criteria to be used in the NRC license review process. It contains specific criteria for use in evaluating the acceptability of nuclear power reactor security programs as detailed in security plans

  18. Human factors engineering design review acceptance criteria for the safety parameter display

    International Nuclear Information System (INIS)

    McGevna, V.; Peterson, L.R.

    1981-01-01

    This report contains human factors engineering design review acceptance criteria developed by the Human Factors Engineering Branch (HFEB) of the Nuclear Regulatory Commission (NRC) to use in evaluating designs of the Safety Parameter Display System (SPDS). These criteria were developed in response to the functional design criteria for the SPDS defined in NUREG-0696, Functional Criteria for Emergency Response Facilities. The purpose of this report is to identify design review acceptance criteria for the SPDS installed in the control room of a nuclear power plant. Use of computer driven cathode ray tube (CRT) displays is anticipated. General acceptance criteria for displays of plant safety status information by the SPDS are developed. In addition, specific SPDS review criteria corresponding to the SPDS functional criteria specified in NUREG-0696 are established

  19. Nevada National Security Site Waste Acceptance Criteria

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Management

    2010-09-03

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NNSSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NNSS Area 3 and Area 5 Radioactive Waste Management Complex for disposal. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project at (702) 295-7063 or fax to (702) 295-1153.

  20. Nevada National Security Site Waste Acceptance Criteria

    International Nuclear Information System (INIS)

    2010-01-01

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NNSSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NNSS Area 3 and Area 5 Radioactive Waste Management Complex for disposal. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project at (702) 295-7063 or fax to (702) 295-1153.

  1. Nevada National Security Site Waste Acceptance Criteria

    International Nuclear Information System (INIS)

    2011-01-01

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NNSSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NNSS Area 3 and Area 5 Radioactive Waste Management Complex for disposal. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project at (702) 295-7063 or fax to (702) 295-1153.

  2. A Study on the Acceptance Criteria for DTrip Frequency

    International Nuclear Information System (INIS)

    Kim, Kil Yoo; Lee, Hyun Woo; Jae, Moo Sung

    2011-01-01

    Many risk informed regulation and applications (RIR and A) are approved, and more RIR and A will be actively applied in Korea. The acceptance criteria for the RIR and A have been DCDF, and DLERF. However, in the economical point of view, the change of the reactor trip frequency (hereafter, it is called Dtrip) are important element to monitor in the RIR and A. A reactor trip causes a huge economical loss, and causes a bad reputation in the social acceptance which causes eventually a social cost, and could induce a safety problem by giving a severe stress on the operators. Usually, the chief managers of nuclear power plants are reluctant to increase the trip frequency by a RIR and A, even though the RIR and A could bring an economical benefit, and could not threaten the safety. Because, if a reactor trip occurs, it would be reflected in his performance assessment. Therefore, it is necessary to set up an acceptance criteria for Dtrip in the RIR and A without depending on the personal preference of the chief manager. This paper introduces the acceptance criteria for Dtrip in the RIR and A

  3. Acceptance criteria for radioactive waste deposition

    International Nuclear Information System (INIS)

    Rzyski, B.M.

    1989-01-01

    The disposal of low-and intermediate level radioactive waste in either shallow ground or rock cavities must be subjected to special guidelines which are used by national authorities and implementing bodies when establishing and regulating respositories. These informations are given by the acceptance criteria and will depend on specific site conditions and optmized procedures. (author) [pt

  4. DISPOSABLE CANISTER WASTE ACCEPTANCE CRITERIA

    Energy Technology Data Exchange (ETDEWEB)

    R.J. Garrett

    2001-07-30

    The purpose of this calculation is to provide the bases for defining the preclosure limits on radioactive material releases from radioactive waste forms to be received in disposable canisters at the Monitored Geologic Repository (MGR) at Yucca Mountain. Specifically, this calculation will provide the basis for criteria to be included in a forthcoming revision of the Waste Acceptance System Requirements Document (WASRD) that limits releases in terms of non-isotope-specific canister release dose-equivalent source terms. These criteria will be developed for the Department of Energy spent nuclear fuel (DSNF) standard canister, the Multicanister Overpack (MCO), the naval spent fuel canister, the High-Level Waste (HLW) canister, the plutonium can-in-canister, and the large Multipurpose Canister (MPC). The shippers of such canisters will be required to demonstrate that they meet these criteria before the canisters are accepted at the MGR. The Quality Assurance program is applicable to this calculation. The work reported in this document is part of the analysis of DSNF and is performed using procedure AP-3.124, Calculations. The work done for this analysis was evaluated according to procedure QAP-2-0, Control of Activities, which has been superseded by AP-2.21Q, Quality Determinations and Planning for Scientific, Engineering, and Regulatory Compliance Activities. This evaluation determined that such activities are subject to the requirements of DOE/RW/0333P, Quality Assurance Requirements and Description (DOE 2000). This work is also prepared in accordance with the development plan titled Design Basis Event Analyses on DOE SNF and Plutonium Can-In-Canister Waste Forms (CRWMS M&O 1999a) and Technical Work Plan For: Department of Energy Spent Nuclear Fuel Work Packages (CRWMS M&O 2000d). This calculation contains no electronic data applicable to any electronic data management system.

  5. On the consistency of risk acceptance criteria with normative theories for decision-making

    Energy Technology Data Exchange (ETDEWEB)

    Abrahamsen, E.B. [University of Stavanger, 4036 Stavanger (Norway)], E-mail: eirik.abrahamsen@uis.no; Aven, T. [University of Stavanger, 4036 Stavanger (Norway)

    2008-12-15

    In evaluation of safety in projects it is common to use risk acceptance criteria to support decision-making. In this paper, we discuss to what extent the risk acceptance criteria is in accordance with the normative theoretical framework of the expected utility theory and the rank-dependent utility theory. We show that the use of risk acceptance criteria may violate the independence axiom of the expected utility theory and the comonotonic independence axiom of the rank-dependent utility theory. Hence the use of risk acceptance criteria is not in general consistent with these theories. The level of inconsistency is highest for the expected utility theory.

  6. On the consistency of risk acceptance criteria with normative theories for decision-making

    International Nuclear Information System (INIS)

    Abrahamsen, E.B.; Aven, T.

    2008-01-01

    In evaluation of safety in projects it is common to use risk acceptance criteria to support decision-making. In this paper, we discuss to what extent the risk acceptance criteria is in accordance with the normative theoretical framework of the expected utility theory and the rank-dependent utility theory. We show that the use of risk acceptance criteria may violate the independence axiom of the expected utility theory and the comonotonic independence axiom of the rank-dependent utility theory. Hence the use of risk acceptance criteria is not in general consistent with these theories. The level of inconsistency is highest for the expected utility theory

  7. Nevada test site defense waste acceptance criteria, certification, and transfer requirements

    International Nuclear Information System (INIS)

    1988-10-01

    The Nevada Test Site (NTS) Defense Waste Acceptance Criteria, Certification and Transfer Requirements establishes procedures and criteria for safe transfer, disposal, and storage of defense transuranic, low-level, and mixed waste at the NTS. Included are an overview of the NTS defense waste management program; the NTS waste acceptance criteria for transuranic, low-level, and mixed wastes; waste certification requirements and guidance; application to submit waste; and requirements for waste transfer and receipt. 5 figs., 16 tabs

  8. Criteria for accepting piping vibrations measured during FFTF plant startup

    International Nuclear Information System (INIS)

    Huang, S.N.

    1981-03-01

    Piping in the Fast Flux Test Facility is subjected to low-amplitude, high cycle vibration over the plant lifetime. Excitation sources include the mechanical vibration induced by main centrifugal pumps, auxiliary reciprocating pumps, EM pumps and possible flow oscillations. Vibration acceptance criteria must be established which will prevent excessive pipe and support fatigue damage when satified. This paper describes the preparation of such criteria against pipe failure used for acceptance testing of the Fast Flux Test Facility main heat transport piping

  9. Hanford Site solid waste acceptance criteria

    International Nuclear Information System (INIS)

    Willis, N.P.; Triner, G.C.

    1991-09-01

    Westinghouse Hanford Company manages the Hanford Site solid waste treatment, storage, and disposal facilities for the US Department of Energy Field Office, Richland under contract DE-AC06-87RL10930. These facilities include radioactive solid waste disposal sites, radioactive solid waste storage areas and hazardous waste treatment, storage, and/or disposal facilities. This manual defines the criteria that must be met by waste generators for solid waste to be accepted by Westinghouse Hanford Company for treatment, storage and/or disposal facilities. It is to be used by all waste generators preparing radioactive solid waste for storage or disposal at the Hanford Site facilities and for all Hanford Site generators of hazardous waste. This manual is also intended for use by Westinghouse Hanford Company solid waste technical staff involved with approval and acceptance of solid waste. The criteria in this manual represent a compilation of state and federal regulations; US Department of Energy orders; Hanford Site requirements; and other rules, regulations, guidelines, and standards as they apply to management of solid waste. Where appropriate, these requirements are included in the manual by reference. It is the intent of this manual to provide guidance to the waste generator in meeting the applicable requirements

  10. Nevada Test Site Waste Acceptance Criteria (NTSWAC), Rev. 7-01

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Management

    2009-05-01

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NTSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex for disposal.

  11. Nevada Test Site Waste Acceptance Criteria (NTSWAC), Rev. 7-01

    International Nuclear Information System (INIS)

    2009-01-01

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NTSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex for disposal.

  12. Acceptance criteria for disposal of radioactive wastes in shallow ground and rock cavities

    International Nuclear Information System (INIS)

    1985-01-01

    This document provides an overview of basic information related to waste acceptance criteria for disposal in shallow ground and rock cavity repositories, consisting of a discussion of acceptable waste types. The last item includes identification of those waste characteristics which may influence the performance of the disposal system and as such are areas of consideration for criteria development. The material is presented in a manner similar to a safety assessment. Waste acceptance criteria aimed at limiting the radiation exposure to acceptable levels are presented for each pathway. Radioactive wastes considered here are low-level radioactive wastes and intermediate-level radioactive wastes from nuclear fuel cycle operations and applications of radionuclides in research, medicine and industry

  13. Acceptability criteria for final underground disposal of radioactive waste

    International Nuclear Information System (INIS)

    Sousselier, Y.

    1984-01-01

    Specialists now generally agree that the underground disposal of suitably immobilized radioactive waste offers a means of attaining the basic objective of ensuring the immediate and long-term protection of man and the environment throughout the requisite period of time and in all foreseeable circumstances. Criteria of a more general as well as a more specific nature are practical means through which this basic protection objective can be reached. These criteria, which need not necessarily be quantified, enable the authorities to gauge the acceptability of a given project and provide those responsible for waste management with a basis for making decisions. In short, these principles constitute the framework of a suitably safety-oriented waste management policy. The more general criteria correspond to the protection objectives established by the national authorities on the basis of principles and recommendations formulated by international organizations, in particular the ICRP and the IAEA. They apply to any underground disposal system considered as a whole. The more specific criteria provide a means of evaluating the degree to which the various components of the disposal system meet the general criteria. They must also take account of the interaction between these components. As the ultimate aim is the overall safety of the disposal system, individual components can be adjusted to compensate for the performance of others with respect to the criteria. This is the approach adopted by the international bodies and national authorities in developing acceptability criteria for the final underground radioactive disposal systems to be used during the operational and post-operational phases respectively. The main criteria are reviewed and an attempt is made to assess the importance of the specific criteria according to the different types of disposal systems. (author)

  14. Development on inelastic analysis acceptance criteria for radioactive material transportation packages

    International Nuclear Information System (INIS)

    Ammerman, D.J.; Ludwigsen, J.S.

    1995-01-01

    The response of radioactive material transportation packages to mechanical accident loadings can be more accurately characterized by non-linear dynamic analysis than by the ''Equivalent dynamic'' static elastic analysis typically used in the design of these packages. This more accurate characterization of the response can lead to improved package safety and design efficiency. For non-linear dynamic analysis to become the preferred method of package design analysis, an acceptance criterion must be established that achieves an equivalent level of safety as the currently used criterion defined in NRC Regulatory Guide 7.6 (NRC 1978). Sandia National Laboratories has been conducting a study of possible acceptance criteria to meet this requirement. In this paper non-linear dynamic analysis acceptance criteria based on stress, strain, and strain-energy-density will be discussed. An example package design will be compared for each of the design criteria, including the approach of NRC Regulatory Guide 7.6

  15. A Method to Improve the Software Acceptance Criteria for Nuclear Power Plants

    International Nuclear Information System (INIS)

    Suh, Yong Suk; Park, Heui Youn; Son, Ki Sung; Lee, Ki Hyun; Kim, Hyeon Soo

    2005-01-01

    The license is a mandatory process required by a governmental authority and the certification is a voluntary process administrated by a professional community. A software certification is a result of an assessment that the certified software conforms to required criteria or standards. The certification is used as a committed promise to produce a high quality software, so software acquirers are requiring it from their suppliers. For example, US DoD (Department of Defense) requires an achievement of CMMI-SW (Capability Maturity Model Integration-Software) certification for participating in a major military software project. It is commonly said that the purpose of achieving a certification is to improve the product quality. In the nuclear area, a software certification has been rarely concerned with or required for the software used in a safety function of NPPs (Nuclear Power Plants). The safety critical software for NPPs is accepted by the nuclear regulators when the following three criteria are met: acceptable plans should be prepared to control the software development activities, the plans should be followed in an acceptable software life cycle, and the process should produce acceptable design outputs. The acceptance criteria are so abstractive that the nuclear regulators may assess the software development plans, activities, outputs based on their subjective engineering judgments. This is inevitable because a software has invisible or intangible characteristics. It is hard to assess the totality of a software prior to running it. These have caused the judgments to be biased. The regulators may want some objectiveness in assessing how much capability for software development the supplier possesses. In that case, the software certification can assist them for such an assessment. This paper proposes a method to improve the software acceptance criteria by applying the software certification to the criteria. This will assist the regulators to assess the supplier

  16. On the use of risk acceptance criteria in the offshore oil and gas industry

    International Nuclear Information System (INIS)

    Aven, Terje; Vinnem, Jan Erik

    2005-01-01

    Risk acceptance criteria, as upper limits of acceptable risks, have been used for offshore activities on the Norwegian Continental Shelf for more than 20 years. The common thinking has been that risk analyses and assessments cannot be conducted in a meaningful way without the use of such criteria. The ALARP principle also applies, but the risk acceptance criteria have played a more active role in the assessment processes than seen for example in the UK. Recently there has, however, been a discussion about the suitability of risk acceptance criteria to assess and control risks. The purpose of this paper is to contribute to this discussion by presenting and discussing a risk analysis regime that is not based on the use of risk acceptance criteria at all. We believe that we can do better if cost-effectiveness (in a wide sense) is the ruling thinking rather than adoption of pre-defined risk acceptance limits. This means a closer resemblance with the ALARP principle as adopted in the UK and other countries, but is not a direct application of this practice. Also the building blocks of the common way of applying the ALARP principle are reviewed. The Norwegian offshore oil and gas industry is the starting point, but the discussion is to large extent general

  17. MCO combustible gas management leak test acceptance criteria; TOPICAL

    International Nuclear Information System (INIS)

    SHERRELL, D.L.

    1999-01-01

    Existing leak test acceptance criteria for mechanically sealed and weld sealed multi-canister overpacks (MCO) were evaluated to ensure that MCOs can be handled and stored in stagnant air without compromising the Spent Nuclear Fuel Project's overall strategy to prevent accumulation of combustible gas mixtures within MCO's or within their surroundings. The document concludes that the integrated leak test acceptance criteria for mechanically sealed and weld sealed MCOs (1 x 10(sup -5) std cc/sec and 1 x 10(sup -7) std cc/sec, respectively) are adequate to meet all current and foreseeable needs of the project, including capability to demonstrate compliance with the NFPA 60 Paragraph 3-3 requirement to maintain hydrogen concentrations[within the air atmosphere CSB tubes] t or below 1 vol% (i.e., at or below 25% of the LFL)

  18. Review of issues relevant to acceptable risk criteria for nuclear waste management

    International Nuclear Information System (INIS)

    Cohen, J.J.

    1978-01-01

    Development of acceptable risk criteria for nuclear waste management requires the translation of publicly determined goals and objectives into definitive issues which, in turn, require resolution. Since these issues are largely of a subjective nature, they cannot be resolved by technological methods. Development of acceptable risk criteria might best be accomplished by application of a systematic methodology for the optimal implementation of subjective values. Multi-attribute decision analysis is well suited for this purpose

  19. Waste-acceptance criteria and risk-based thinking for radioactive-waste classification

    International Nuclear Information System (INIS)

    Lowenthal, M.D.

    1998-01-01

    The US system of radioactive-waste classification and its development provide a reference point for the discussion of risk-based thinking in waste classification. The official US system is described and waste-acceptance criteria for disposal sites are introduced because they constitute a form of de facto waste classification. Risk-based classification is explored and it is found that a truly risk-based system is context-dependent: risk depends not only on the waste-management activity but, for some activities such as disposal, it depends on the specific physical context. Some of the elements of the official US system incorporate risk-based thinking, but like many proposed alternative schemes, the physical context of disposal is ignored. The waste-acceptance criteria for disposal sites do account for this context dependence and could be used as a risk-based classification scheme for disposal. While different classes would be necessary for different management activities, the waste-acceptance criteria would obviate the need for the current system and could better match wastes to disposal environments saving money or improving safety or both

  20. Flaw acceptance criteria taking into consideration the NDT: radiographic and ultrasonic testing. Analysis through the fracture mechanics methods

    International Nuclear Information System (INIS)

    Capurro, E.; Alicino, F.; Corvi, A.

    1993-01-01

    The present study compares and evaluates the flaw acceptance criteria of the non-destructive inspections meeting European Community standards, through the application of the fracture mechanics methods that were determined and verified by the previous activity. Some choices were made; these, however, do not change the general validity of the conclusions. Shaved full-penetration butt welds of Class 1 components making up the primary circuit were considered and the following parameters varied: standards: French, German, Italian (ASME III) and UK; material: AISI 316 and low alloy steel A 533; base material and weld metal; temperature: RT, 370 deg C for the austenitic and 260 deg C for the ferritic steel; ultrasonic and radiographic methods; defect position: surface and internal; stress condition: situations with different primary and secondary stresses. From a preliminary examination of this study it is evident that the large quantity of results available and the abundance of information contained therein make a simple and exhaustive synthesis difficult. In fact, different analyses are possible and we have, therefore, limited the research to activities to perform a comparison and a general evaluation of the acceptance criteria of the non-destructive testing. (authors). 57 refs., 25 figs., 11 tabs

  1. Acceptance of spent fuel of varying characteristics

    International Nuclear Information System (INIS)

    Short, S.M.

    1990-03-01

    This paper is a preliminary overview of a study with the primary objective of establishing a set of acceptance selection criteria and corresponding spent fuel characteristics to be incorporated as a component of requirements for the Federal Waste Management System (FWMS). A number of alternative acceptance allocations and selection rules were analyzed to determine the operational sensitivity of each element of the FWMS to the resultant spent fuel characteristics. Preliminary recommendations of the study include three different sets of selection rules to be included in the FWMS design basis. 2 refs., 4 figs., 4 tabs

  2. Why risk acceptance criteria need to be defined by the authorities and not the industry?

    International Nuclear Information System (INIS)

    Abrahamsen, Eirik Bjorheim; Aven, Terje

    2012-01-01

    In various industries it is common to use risk acceptance criteria to support decision-making. The criteria are seen as absolute in the sense that measures need to be implemented if the criteria are not met. In Norway the petroleum regulations state that the operator has a duty to formulate risk acceptance criteria relating to major accidents and to the environment. This practice is in line with the internal control principle, which states that the operator has the full responsibility for identifying the hazards and seeing that they are controlled. In this paper we discuss the rationale for this practice. The expected utility theory, which is the backbone for all economic thinking, is used as a basis for the discussion. We show that if risk acceptance criteria are to be introduced as a risk management tool, they should be formulated by the authorities, as is the common scheme seen in many countries and industries, for example in the UK. Risk acceptance criteria formulated by the industry would not in general serve the interest of the society as a whole.

  3. 78 FR 65007 - Inspections, Tests, Analyses, and Acceptance Criteria; Vogtle Electric Generating Plant, Unit 3

    Science.gov (United States)

    2013-10-30

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 052-00026; NRC-2008-0252] Inspections, Tests, Analyses, and Acceptance Criteria; Vogtle Electric Generating Plant, Unit 3 AGENCY: Nuclear Regulatory Commission. ACTION: Determination of inspections, tests, analyses, and acceptance criteria completion...

  4. 78 FR 53483 - Inspections, Tests, Analyses, and Acceptance Criteria; Vogtle Electric Generating Plant, Unit 3

    Science.gov (United States)

    2013-08-29

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 052-00025; NRC-2008-0252] Inspections, Tests, Analyses, and Acceptance Criteria; Vogtle Electric Generating Plant, Unit 3 AGENCY: Nuclear Regulatory Commission. ACTION: Determination of inspections, tests, analyses, and acceptance criteria (ITAAC) completion...

  5. 78 FR 53484 - Inspections, Tests, Analyses, and Acceptance Criteria; Vogtle Electric Generating Plant, Unit 4

    Science.gov (United States)

    2013-08-29

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 052-00026; NRC-2008-0252] Inspections, Tests, Analyses, and Acceptance Criteria; Vogtle Electric Generating Plant, Unit 4 AGENCY: Nuclear Regulatory Commission. ACTION: Determination of inspections, tests, analyses, and acceptance criteria (ITAAC) completion...

  6. 78 FR 38411 - Vogtle Electric Generating Plant, Unit 4; Inspections, Tests, Analyses, and Acceptance Criteria

    Science.gov (United States)

    2013-06-26

    ... Plant, Unit 4; Inspections, Tests, Analyses, and Acceptance Criteria AGENCY: Nuclear Regulatory Commission. ACTION: Determination of inspections, tests, analyses, and acceptance criteria completion. SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) staff has determined that the inspections, tests...

  7. Synthetic seismic acceleration time-histories and their acceptance criteria

    International Nuclear Information System (INIS)

    Xu Hong

    1996-01-01

    In seismic dynamic response analysis of structures and equipment, time-history analysis is now widely used. The 3-D seismic acceleration time-histories or 3-D seismic displacement time-histories are required in the 3-D seismic dynamic response analysis as the seismic excitation input data. Because of the lack of actual acceleration time-histories for the field where the structures or equipment are installed, the general practice is to use the synthetic seismic acceleration time-histories, which are derived from the design seismic response spectra of the field, as the seismic excitation input data. However, from one specified design response spectrum indefinite solutions of acceleration time-histories can be derived depending on the values of the input parameters. Not all the derived synthetic time-histories can be used as seismic excitation input data. Only those which meet the acceptance criteria can be used. The factors (input parameters), which will affect the time-history solution from a specified seismic response spectrum, and the acceptance criteria are discussed

  8. Establishing seismic design criteria to achieve an acceptable seismic margin

    International Nuclear Information System (INIS)

    Kennedy, R.P.

    1997-01-01

    In order to develop a risk based seismic design criteria the following four issues must be addressed: (1) What target annual probability of seismic induced unacceptable performance is acceptable? (2). What minimum seismic margin is acceptable? (3) Given the decisions made under Issues 1 and 2, at what annual frequency of exceedance should the Safe Shutdown Earthquake ground motion be defined? (4) What seismic design criteria should be established to reasonably achieve the seismic margin defined under Issue 2? The first issue is purely a policy decision and is not addressed in this paper. Each of the other three issues are addressed. Issues 2 and 3 are integrally tied together so that a very large number of possible combinations of responses to these two issues can be used to achieve the target goal defined under Issue 1. Section 2 lays out a combined approach to these two issues and presents three potentially attractive combined resolutions of these two issues which reasonably achieves the target goal. The remainder of the paper discusses an approach which can be used to develop seismic design criteria aimed at achieving the desired seismic margin defined in resolution of Issue 2. Suggestions for revising existing seismic design criteria to more consistently achieve the desired seismic margin are presented

  9. HWVP compliance with the Hanford site solid waste acceptance criteria

    International Nuclear Information System (INIS)

    Bromm, R.; Ornelas, J.; Fundingsland, S.; Shah, K.

    1993-01-01

    In order to ensure that the Hanford Waste Vitrification Project (HWVP) will meet solid waste acceptance criteria, a review of the criteria was performed. The primary purpose of the study was to evaluate the modifications that will be required to bring the HWVP into compliance for secondary waste which will be generated during normal operations of the facility. To accomplish this objective, the current HWVP design was evaluated based on the criteria established. Once the non-compliance areas and potentially non-compliance areas were identified, alternative plant design modifications were proposed. This paper summarizes the results and recommendations of that study

  10. Criteria for risk acceptance: a health physicist's view

    International Nuclear Information System (INIS)

    Hull, A. P.

    1977-01-01

    While energy need (or demand) and the risks of energy production and use may be objectively quantified, risk acceptance embodies a subjective element of preferences and values. Yet, as demonstrated by the nuclear controversy in the United States, public acceptance is essential to the beneficial uses of radiation. The statement of the objectives and purposes of the Health Physics Society and our application of it are proposed as offering useful criteria for risk acceptance. The principle of comparing risk with a number of those regularly accepted in everyday life is emphasized. On this basis, it is concluded that the expenditures to attain currently applicable or proposed 'as low as practicable' (or 'as low as readily achievable') levels for the nuclear fuel cycle are disproportionate to those addressed to other sources of general public exposure to radiation. They are also disproportionate compared to those addressed to a variety of public health risks. It is suggested that sensible priorities for radiation and public health protection might be achieved by the application of a de minimus negligible (but nonzero) level of probable risk. (Research supported by the U.S. Energy Research and Development Administration.)

  11. Typical design/qualification acceptance criteria for newly installed pipelines and equipment components of VVER-type NPPs

    International Nuclear Information System (INIS)

    Masopust, R.

    2003-01-01

    This paper describes in general the typical design/qualification acceptance criteria and seismic acceptance criteria in particular that are applicable for important to safety newly installed pipelines and equipment components of VVER-type already existing NPPs, specifically during the design verification phase of this newly installed equipment. These criteria are currently used for VVER 440-213 and VVER 1000 NPPs in Czech Republic and in Slovakia. The similar criteria are also used in Hungary. (author)

  12. Acceptance criteria for the ITER divertor vertical target

    International Nuclear Information System (INIS)

    Fouquet, S.; Schlosser, J.; Merola, M.; Durocher, A.; Escourbiac, F.; Grosman, A.; Missirlian, M.; Portafaix, C.

    2006-01-01

    In the frame of the toroidal pump limiter fabrication for Tore Supra, CEA developed a large experience of infrared test for acceptance of high heat flux components armoured with carbon fibre composite flat tiles. The test is based on a thermal transient induced by an alternative hot/cold water flow in the heat sink structure. The tile surface temperature transients are compared with those of a reference element, the maximum difference for each tile leading to a value called ΔT ref m ax . This method is proposed for the commissioning of plasma facing components for the ITER divertor vertical target. This paper describes the determination of the best acceptance criteria for the 'monoblock' geometry of the carbon part. First, it has been shown that the location and the extension of the defects could reliably be determined by monitoring both top and lateral surfaces during the test. Second, it was possible to fix an acceptance method based on ΔT ref m ax . Samples with calibrated defects are now under fabrication to validate the results

  13. Procedures and acceptance criteria for PAS-1 cask inspections

    International Nuclear Information System (INIS)

    Mercado, J.E.

    1998-01-01

    The procedures and acceptance criteria that comprise this document were prepared to support a one-time test to certify two PAS-1 casks in accordance with US Department of Energy Certificate of Compliance US A/9184/B(U), which was issued in 1998. The specific inspections addressed in this document are the visual weld inspection and a dimensional inspection of the primary containment vessel

  14. Preliminary criticality study supporting transuranic waste acceptance into the plasma hearth process

    International Nuclear Information System (INIS)

    Slate, L.J.; Santee, G.E. Jr.

    1996-01-01

    This study documents preliminary scoping calculations to address criticality issues associated with the processing of transuranic (TRU) waste and TRU mixed waste in the Plasma Hearth Process (PHP) Test Project. To assess the criticality potential associated with processing TRU waste, the process flow in the PHP is evaluated to identify the stages where criticality could occur. A criticality analysis methodology is then formulated to analyze the criticality potential. Based on these analyses, TRU acceptance criteria can be defined for the PHP. For the current level of analysis, the methodology only assesses the physical system as designed and does not address issues associated with the criticality double contingency principle. The analyses suggest that criticality within the PHP system and within the planned treatment residue (stag) containers does not pose a criticality hazard even when processing waste feed drums containing a quantity of TRU greater than would be reasonably expected. The analyses also indicate that the quantity of TRU that can be processed during each batch is controlled by moving and storage conditions for the resulting slag collection drums

  15. 21 CFR 212.70 - What controls and acceptance criteria must I have for my finished PET drug products?

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 4 2010-04-01 2010-04-01 false What controls and acceptance criteria must I have... POSITRON EMISSION TOMOGRAPHY DRUGS (Eff. 12-12-2011) Finished Drug Product Controls and Acceptance § 212.70 What controls and acceptance criteria must I have for my finished PET drug products? (a) Specifications...

  16. Testing the validity and acceptability of the diagnostic criteria for Hoarding Disorder: a DSM-5 survey.

    Science.gov (United States)

    Mataix-Cols, D; Fernández de la Cruz, L; Nakao, T; Pertusa, A

    2011-12-01

    The DSM-5 Obsessive-Compulsive Spectrum Sub-Workgroup is recommending the creation of a new diagnostic category named Hoarding Disorder (HD). The validity and acceptability of the proposed diagnostic criteria have yet to be formally tested. Obsessive-compulsive disorder/hoarding experts and random members of the American Psychiatric Association (APA) were shown eight brief clinical vignettes (four cases meeting criteria for HD, three with hoarding behaviour secondary to other mental disorders, and one with subclinical hoarding behaviour) and asked to decide the most appropriate diagnosis in each case. Participants were also asked about the perceived acceptability of the criteria and whether they supported the inclusion of HD in the main manual. Altogether, 211 experts and 48 APA members completed the survey (30% and 10% response rates, respectively). The sensitivity and specificity of the HD diagnosis and the individual criteria were high (80-90%) across various types of professionals, irrespective of their experience with hoarding cases. About 90% of participants in both samples thought the criteria would be very/somewhat acceptable for professionals and sufferers. Most experts (70%) supported the inclusion of HD in the main manual, whereas only 50% of the APA members did. The proposed criteria for HD have high sensitivity and specificity. The criteria are also deemed acceptable for professionals and sufferers alike. Training of professionals and the development and validation of semi-structured diagnostic instruments should improve diagnostic accuracy even further. A field trial is now needed to confirm these encouraging findings with real patients in real clinical settings.

  17. Strain-based plastic instability acceptance criteria for ferritic steel safety class 1 nuclear components under level D

    International Nuclear Information System (INIS)

    Kim, Ji Su; Lee, Han Sang; Kim, Yun Jae; Kim, Jong Sung; Kim, Jin Won

    2015-01-01

    This paper proposes strain-based acceptance criteria for assessing plastic instability of the safety class 1 nuclear components made of ferritic steel during level D service loads. The strain-based criteria were proposed with two approaches: (1) a section average approach and (2) a critical location approach. Both approaches were based on the damage initiation point corresponding to the maximum load-carrying capability point instead of the fracture point via tensile tests and finite element analysis (FEA) for the notched specimen under uni-axial tensile loading. The two proposed criteria were reviewed from the viewpoint of design practice and philosophy to select a more appropriate criterion. As a result of the review, it was found that the section average approach is more appropriate than the critical location approach from the viewpoint of design practice and philosophy. Finally, the criterion based on the section average approach was applied to a simplified reactor pressure vessel (RPV) outlet nozzle subject to SSE loads. The application shows that the strain-based acceptance criteria can consider cumulative damages caused by the sequential loads unlike the stress-based acceptance criteria and can reduce the over conservatism of the stress-based acceptance criteria, which often occurs for level D service loads.

  18. Strain-based plastic instability acceptance criteria for ferritic steel safety class 1 nuclear components under level D

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Ji Su; Lee, Han Sang; Kim, Yun Jae [Dept. of Mechanical Engineering, Korea University, Seoul (Korea, Republic of); Kim, Jong Sung [Dept. of Mechanical Engineering, Sunchon National University, Suncheon (Korea, Republic of); Kim, Jin Won [Dept. of Nuclear Engineering, Chosun University, Gwangju (Korea, Republic of)

    2015-04-15

    This paper proposes strain-based acceptance criteria for assessing plastic instability of the safety class 1 nuclear components made of ferritic steel during level D service loads. The strain-based criteria were proposed with two approaches: (1) a section average approach and (2) a critical location approach. Both approaches were based on the damage initiation point corresponding to the maximum load-carrying capability point instead of the fracture point via tensile tests and finite element analysis (FEA) for the notched specimen under uni-axial tensile loading. The two proposed criteria were reviewed from the viewpoint of design practice and philosophy to select a more appropriate criterion. As a result of the review, it was found that the section average approach is more appropriate than the critical location approach from the viewpoint of design practice and philosophy. Finally, the criterion based on the section average approach was applied to a simplified reactor pressure vessel (RPV) outlet nozzle subject to SSE loads. The application shows that the strain-based acceptance criteria can consider cumulative damages caused by the sequential loads unlike the stress-based acceptance criteria and can reduce the over conservatism of the stress-based acceptance criteria, which often occurs for level D service loads.

  19. 76 FR 6459 - Mahoning Hydropower, LLC; Notice of Preliminary Permit Application Accepted for Filing and...

    Science.gov (United States)

    2011-02-04

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 13954-000] Mahoning Hydropower, LLC; Notice of Preliminary Permit Application Accepted for Filing and Soliciting Comments... Hydropower, LLC filed an application for a preliminary permit, pursuant to section 4(f) of the Federal Power...

  20. 76 FR 7838 - Mahoning Hydropower, LLC; Notice of Preliminary Permit Application Accepted for Filing and...

    Science.gov (United States)

    2011-02-11

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 13953-000] Mahoning Hydropower, LLC; Notice of Preliminary Permit Application Accepted for Filing and Soliciting Comments... Hydropower, LLC filed an application for a preliminary permit, pursuant to section 4(f) of the Federal Power...

  1. Multi-Canister Overpack (MCO) Combustible Gas Management Leak Test Acceptance Criteria (OCRWM)

    International Nuclear Information System (INIS)

    SHERRELL, D.L.

    2000-01-01

    The purpose of this document is to support the Spent Nuclear Fuel Project's combustible gas management strategy while avoiding the need to impose any requirements for oxygen free atmospheres within storage tubes that contain multi-canister overpacks (MCO). In order to avoid inerting requirements it is necessary to establish and confirm leak test acceptance criteria for mechanically sealed and weld sealed MCOs that are adequte to ensure that, in the unlikely event the leak test results for any MCO were to approach either of those criteria, it could still be handled and stored in stagnant air without compromising the SNF Project's overall strategy to prevent accumulation of combustible gas mixtures within MCOs or within their surroundings. To support that strategy, this document: (1) establishes combustible gas management functions and minimum functional requirements for the MCO's mechanical seals and closure weld(s); (2) establishes a maximum practical value for the minimum required initial MCO inert backfill gas pressure; and (3) based on items 1 and 2, establishes and confirms leak test acceptance criteria for the MCO's mechanical seal and final closure weld(s)

  2. The use of acceptability criteria for radiological risk at AWE Aldermaston

    International Nuclear Information System (INIS)

    Thurston, B.B.; Tutt, K.J.; Zabierek, G.A.

    1989-01-01

    The limit-line approach to setting acceptable risk criteria for nuclear power plants is in general use in the United Kingdom. The Atomic Weapons Establishment (AWE) is a Ministry of Defence Establishment which contains a number of nuclear material processing facilities. Limit-line risk criteria have been used for some years to provide a framework within which identified hazards may be judged in a systematic manner, rather than on an ad hoc basis. This paper describes how this is applied to both new facilities and to changes made to existing ones including decommissioning. (author)

  3. 75 FR 59706 - Coastal Hydropower, LLC; Notice of Preliminary Permit Application Accepted for Filing and...

    Science.gov (United States)

    2010-09-28

    ... Hydropower, LLC; Notice of Preliminary Permit Application Accepted for Filing and Soliciting Comments... on July 16, 2010, Coastal Hydropower, LLC filed an application for a preliminary permit, pursuant to... generation of the project would be 7.9 gigawatt-hours. Applicant Contact: Neil Anderson, Coastal Hydropower...

  4. Acceptance criteria for deposition of low-level and intermediate-level radiation levels radioactive wastes

    International Nuclear Information System (INIS)

    2002-09-01

    This norm establishes the criteria for acceptance low and intermediate radiation level for safe deposition in repositories, for assuring the protection of workers, population and environment against the hazardous effects of the ionizing radiations. The criteria of this norm applies to the low and intermediate radiation levels

  5. Technical Basis For Radiological Acceptance Criteria For Uranium At The Y-12 National Security Complex

    Energy Technology Data Exchange (ETDEWEB)

    Veinot, K. G.

    2009-07-22

    The purpose of this report is to establish radiological acceptance criteria for uranium. Other factors for acceptance not considered include criticality safety concerns, contaminants to the process stream, and impacts to the Safety Basis for the affected facilities. Three types of criteria were developed in this report. They include limits on external penetrating and non-penetrating radiation and on the internal hazard associated with inhalation of the material. These criteria are intended to alleviate the need for any special controls beyond what are normally utilized for worker protection from uranium hazards. Any proposed exceptions would require case-by-case evaluations to determine cost impacts and feasibility. Since Y-12 has set rigorous ALARA goals for worker doses, the external limits are based on assumptions of work time involved in the movement of accepted material plus the desire that external doses normally received are not exceeded, and set so that no special personnel monitoring would be required. Internal hazard controls were established so that dose contributions from non-uranium nuclides would not exceed 10% of that expected from the uranium component. This was performed using a Hazard Index (HI) previously established for work in areas contaminated with non-uranium nuclides. The radiological acceptance criteria for uranium are summarized in Table 1. Note that these limits are based on the assumption that radioactive daughter products have reached equilibrium.

  6. Preliminary estimates of the impacts of alternative spent fuel acceptance rates

    International Nuclear Information System (INIS)

    Clark, L.L.; McKee, R.W.; Short, S.M.

    1986-02-01

    The rate at which spent fuel is accepted by the federal waste management system is an important interface between the private nuclear power sector and the federal government, which will assume responsibility for spent fuel disposal. An analysis of alternative rates based on minimum age criteria indicates substantial incentives to limit acceptance rates so as to result in minimum 10 to 15 year fuel ages for repository acceptance [1500 to 2500 metric tons of uranium (MTU) per year]. These incentives include lower heat generation rates and systems costs

  7. 75 FR 59707 - Coastal Hydropower, LLC; Notice of Preliminary Permit Application Accepted for Filing and...

    Science.gov (United States)

    2010-09-28

    ... Hydropower, LLC; Notice of Preliminary Permit Application Accepted for Filing and Soliciting Comments... on July 16, 2010, Coastal Hydropower, LLC filed an application for a preliminary permit, pursuant to... Hydropower, LLC, Key Centre, 601 108th Avenue, NE., Suite 1900, Bellevue, WA 98004; phone: (425) 943-7690...

  8. Managing Hanford Site solid waste through strict acceptance criteria

    International Nuclear Information System (INIS)

    Jasen, W.G.; Pierce, R.D.; Willis, N.P.

    1993-02-01

    Various types of waste have been generated during the 50-year history of the Hanford Site. Regulatory changes in the last 20 years have provided the emphasis for better management of these wastes. Interpretations of the Atomic Energy Act of 1954 (AEA) and the Resource Conservation and Recovery Act of 1976 (RCRA) have led to the definition of a group of wastes called radioactive mixed wastes (RMW). As a result of the radioactive and hazardous properties of these wastes, strict management programs have been implemented for the management of these wastes. Solid waste management is accomplished through a systems performance approach to waste management that used best-demonstrated available technology (BDAT) and best management practices. The solid waste program at the Hanford Site strives to integrate all aspects of management relative to the treatment, storage and disposal (TSD) of solid waste. Often there are many competing and important needs. It is a difficult task to balance these needs in a manner that is both equitable and productive. Management science is used to help the process of making decisions. Tools used to support the decision making process include five-year planning, cost estimating, resource allocation, performance assessment, waste volume forecasts, input/output models, and waste acceptance criteria. The purpose of this document is to describe how one of these tools, waste acceptance criteria, has helped the Hanford Site manage solid wastes

  9. Qualitative acceptance criteria for radioactive wastes to be disposed of in deep geological formations

    International Nuclear Information System (INIS)

    1990-05-01

    The present Safety Guide has to be seen as a companion document to the IAEA Safety Series No. 99. It is concerned with the waste form which is an important component of the overall disposal system. Because of the broad range of waste types and conditioned forms and variations in the sites, designs and constructional approaches being considered for deep geological repositories, this report necessarily approaches the waste acceptance criteria in a general way, recognizing that the assignment of quantitative limits to these criteria has to be the responsibility of national authorities. The main objective of this Safety Guide is to set out qualitative waste acceptance criteria as a basis for specifying quantitative limits for the waste forms and packages which are intended to be disposed of in deep geological repositories. It should serve as guidance for assigning such parameter values which would fully comply with the safety assessment and performance of a waste disposal system as a whole. This document is intended to serve both national authorities and regulatory bodies involved in the development of deep underground disposal systems. The qualitative waste acceptance criteria dealt with in the present Safety Guide are primarily concerned with the disposal of high level, intermediate level and long-lived alpha bearing wastes in deep geological repositories. Although some criteria are also applicable in other waste disposal concepts, it has to be borne in mind that the set of criteria presented here shall ensure the isolation capability of a waste disposal system for periods of time much longer than for other waste streams with shorter lifetimes. 51 refs, 1 tab

  10. Design loads, loading combinations and structural acceptance criteria for BWR containments in the United States

    International Nuclear Information System (INIS)

    Edwards, N.W.

    1979-01-01

    The definition of loads, loading combinations, and structural acceptance criteria used for the design and evaluation of BWR containments in the Unites States has become much more comprehensive over the past decade. The Mark I pressure suppression containment vessels were designed for a static design pressure, a design temperature, dead load and static equivalent earthquake. The current Mark III containments are being designed to accommodate many more loads such as safety relief valve discharge loads, and suppression pool hydrodynamic loadings associated with the steam condensation phenomena as well as pressure and temperature transients for a range of pipe break sizes. Consistent with the more comprehensive definition of loads and loading combinations, the ASME Code presently establishes structural acceptance criteria with different margins of safety by the definition of Service Level Assignments A, B, C and D. Acting in a responsible manner, United States utilities are currently evaluating and modifying existing containment vessels to account for the more detailed load definition and structural acceptance criteria. (orig.)

  11. Criteria required for an acceptable point-of-care test for UTI detection: Obtaining consensus using the Delphi technique.

    Science.gov (United States)

    Weir, Nichola-Jane M; Pattison, Sally H; Kearney, Paddy; Stafford, Bob; Gormley, Gerard J; Crockard, Martin A; Gilpin, Deirdre F; Tunney, Michael M; Hughes, Carmel M

    2018-01-01

    Urinary Tract Infections (UTIs) are common bacterial infections, second only to respiratory tract infections and particularly prevalent within primary care. Conventional detection of UTIs is culture, however, return of results can take between 24 and 72 hours. The introduction of a point of care (POC) test would allow for more timely identification of UTIs, facilitating improved, targeted treatment. This study aimed to obtain consensus on the criteria required for a POC UTI test, to meet patient need within primary care. Criteria for consideration were compiled by the research team. These criteria were validated through a two-round Delphi process, utilising an expert panel of healthcare professionals from across Europe and United States of America. Using web-based questionnaires, panellists recorded their level of agreement with each criterion based on a 5-point Likert Scale, with space for comments. Using median response, interquartile range and comments provided, criteria were accepted/rejected/revised depending on pre-agreed cut-off scores. The first round questionnaire presented thirty-three criteria to the panel, of which 22 were accepted. Consensus was not achieved for the remaining 11 criteria. Following response review, one criterion was removed, while after revision, the remaining 10 criteria entered the second round. Of these, four were subsequently accepted, resulting in 26 criteria considered appropriate for a POC test to detect urinary infections. This study generated an approved set of criteria for a POC test to detect urinary infections. Criteria acceptance and comments provided by the healthcare professionals also supports the development of a multiplex point of care UTI test.

  12. Characteristics of radioactive waste forms conditioned for storage and disposal: Guidance for the development of waste acceptance criteria

    International Nuclear Information System (INIS)

    1983-04-01

    This report attempts to review the characteristics of the individual components of the waste package, i.e. the waste form and the container, in order to formulate, where appropriate, quidelines for the development of practical waste acceptance criteria. Primarily the criteria for disposal are considered, but if more stringent criteria are expected to be necessary for storage or transportation prior to the disposal, these will be discussed. The report will also suggest test areas which will aid the development of the final waste acceptance criteria

  13. Summary of research and development activities in support of waste acceptance criteria for WIPP

    International Nuclear Information System (INIS)

    Hunter, T.O.

    1979-11-01

    The development of waste acceptance criteria for the Waste Isolation Pilot Plant (WIPP) is summarized. Specifications for acceptable waste forms are included. Nine program areas are discussed. They are: TRU characterization, HLW interactions, thermal/structural interactions, nuclide migration, permeability, brine migration, borehole plugging, operation/design support, and instrumentation development. Recommendations are included

  14. Sample acceptance time criteria, electronic issue and alloimmunisation in thalassaemia.

    Science.gov (United States)

    Trompeter, S; Baxter, L; McBrearty, M; Zatkya, E; Porter, J

    2015-12-01

    To determine the safety of a 1-week acceptance criteria of sample receipt in laboratory to transfusion commencement in transfusion dependent thalassaemia with respect to alloimmunisation. To determine the safety of electronic issue of blood components in such a setting. Retrospective audit of alloimmunisation (1999-2012) and blood exposure in registered thalassaemia patients at a central London thalassaemia centre where the acceptance criteria for the group and save sample from arrival in the laboratory to the time of issue of blood for transfusion for someone who has been transfused in the last 28 days was 1 week, and there was electronic issue protocol for patients who have always had a negative antibody screen (other than temporary positivity in pregnant women receiving prophylactic anti-D or anti Le-a, Anti Le-b and Anti P1 that are no longer detectable). There were 133 patients with thalassemia variants regularly attending UCLH for review. A total of 105 patients had transfusion dependent thalassaemia (TDT) (7 E-beta thalassaemia, 98 beta thalassaemia major). Ten of the 84 patients who received their transfusions at UCLH were alloimmunised. Seven of them had been alloimmunised prior to arrival at UCLH. Only two patients developed antibodies at UCLH during this period. The prevalence of alloantibody formation of 2% in UCLH transfused patients, with presumptive incidence of 0.01 alloantibodies per 100 units or 0·001 immunisations per person per year compares favourably with other reported series and suggests that 1 week interval with appropriate electronic issue is acceptable practice. © 2015 British Blood Transfusion Society.

  15. Waste acceptance criteria for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    1996-04-01

    The Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC), DOE/WIPP-069, was initially developed by a U.S. Department of Energy (DOE) Steering Committee to provide performance requirements to ensure public health and safety as well as the safe handling of transuranic (TRU) waste at the WIPP. This revision updates the criteria and requirements of previous revisions and deletes those which were applicable only to the test phase. The criteria and requirements in this document must be met by participating DOE TRU Waste Generator/Storage Sites (Sites) prior to shipping contact-handled (CH) and remote-handled (RH) TRU waste forms to the WIPP. The WIPP Project will comply with applicable federal and state regulations and requirements, including those in Titles 10, 40, and 49 of the Code of Federal Regulations (CFR). The WAC, DOE/WIPP-069, serves as the primary directive for assuring the safe handling, transportation, and disposal of TRU wastes in the WIPP and for the certification of these wastes. The WAC identifies strict requirements that must be met by participating Sites before these TRU wastes may be shipped for disposal in the WIPP facility. These criteria and requirements will be reviewed and revised as appropriate, based on new technical or regulatory requirements. The WAC is a controlled document. Revised/changed pages will be supplied to all holders of controlled copies

  16. Identification of permit and waste acceptance criteria provisions requiring modification for acceptance of commercial mixed waste

    International Nuclear Information System (INIS)

    1994-03-01

    In October 1990, representatives of States and compact regions requested that the US Department of Energy (DOE) explore an agreement with host States and compact regions under which DOE would accept commercial mixed low-level radioactive waste (LLW) at DOE's own treatment and disposal facilities. A program for DOE management of commercial mixed waste is made potentially more attractive in light of the low commercial mixed waste volumes, high regulatory burdens, public opposition to new disposal sites, and relatively high cost of constructing commercial disposal facilities. Several studies were identified as essential in determining the feasibility of DOE accepting commercial mixed waste for disposal. The purpose of this report is to identify any current or proposed waste acceptance criteria (WAC) or Resource Conservation and Recovery Act (RCRA) provisions that would have to be modified for commercial mixed waste acceptance at specified DOE facilities. Following the introduction, Section 2 of this report (a) provides a background summary of existing and proposed mixed waste disposal facilities at each DOE site, and (b) summarizes the status of any RCRA Part B permit and WAC provisions relating to the disposal of mixed waste, including provisions relating to acceptance of offsite waste. Section 3 provides overall conclusions regarding the current status and permit modifications that must be implemented in order to grant DOE sites authority under their permits to accept commercial mixed waste for disposal. Section 4 contains a list of references

  17. 78 FR 12050 - S. Martinez Livestock, Inc.; Notice of Preliminary Permit Application Accepted for Filing and...

    Science.gov (United States)

    2013-02-21

    ... Livestock, Inc.; Notice of Preliminary Permit Application Accepted for Filing and Soliciting Comments.... Martinez Livestock, Inc. filed an application for a preliminary permit, pursuant to section 4(f) of the... megawatt hours. Applicant Contact: Mr. Daniel T. Martinez, S. Martinez Livestock, Inc., 13395 Hwy. 24...

  18. Definition of acceptance criteria for the ITER divertor plasma-facing components through systematic experimental analysis

    International Nuclear Information System (INIS)

    Escourbiac, F; Richou, M; Guigon, R; Durocher, A; Schlosser, J; Grosman, A; Constans, S; Merola, M; Riccardi, B

    2009-01-01

    Experience has shown that a critical part of the high-heat flux (HHF) plasma-facing component (PFC) is the armour to heat sink bond. An experimental study was performed in order to define acceptance criteria with regards to thermal hydraulics and fatigue performance of the International Thermonuclear Experimental Reactor (ITER) divertor PFCs. This study, which includes the manufacturing of samples with calibrated artificial defects relevant to the divertor design, is reported in this paper. In particular, it was concluded that defects detectable with non-destructive examination (NDE) techniques appeared to be acceptable during HHF experiments relevant to heat fluxes expected in the ITER divertor. On the basis of these results, a set of acceptance criteria was proposed and applied to the European vertical target medium-size qualification prototype: 98% of the inspected carbon fibre composite (CFC) monoblocks and 100% of tungsten (W) monoblock and flat tiles elements (i.e. 80% of the full units) were declared acceptable.

  19. Definition of acceptance criteria for the ITER divertor plasma-facing components through systematic experimental analysis

    Science.gov (United States)

    Escourbiac, F.; Richou, M.; Guigon, R.; Constans, S.; Durocher, A.; Merola, M.; Schlosser, J.; Riccardi, B.; Grosman, A.

    2009-12-01

    Experience has shown that a critical part of the high-heat flux (HHF) plasma-facing component (PFC) is the armour to heat sink bond. An experimental study was performed in order to define acceptance criteria with regards to thermal hydraulics and fatigue performance of the International Thermonuclear Experimental Reactor (ITER) divertor PFCs. This study, which includes the manufacturing of samples with calibrated artificial defects relevant to the divertor design, is reported in this paper. In particular, it was concluded that defects detectable with non-destructive examination (NDE) techniques appeared to be acceptable during HHF experiments relevant to heat fluxes expected in the ITER divertor. On the basis of these results, a set of acceptance criteria was proposed and applied to the European vertical target medium-size qualification prototype: 98% of the inspected carbon fibre composite (CFC) monoblocks and 100% of tungsten (W) monoblock and flat tiles elements (i.e. 80% of the full units) were declared acceptable.

  20. Definition of acceptance criteria for the ITER divertor plasma-facing components through systematic experimental analysis

    Energy Technology Data Exchange (ETDEWEB)

    Escourbiac, F; Richou, M; Guigon, R; Durocher, A; Schlosser, J; Grosman, A [CEA/IRFM, F-13108, Saint-Paul-lez-Durance (France); Constans, S [AREVA-NP, Le Creusot (France); Merola, M [ITER Organization, Cadarache (France); Riccardi, B [Fusion For Energy, Barcelona (Spain)], E-mail: frederic.escourbiac@cea.fr

    2009-12-15

    Experience has shown that a critical part of the high-heat flux (HHF) plasma-facing component (PFC) is the armour to heat sink bond. An experimental study was performed in order to define acceptance criteria with regards to thermal hydraulics and fatigue performance of the International Thermonuclear Experimental Reactor (ITER) divertor PFCs. This study, which includes the manufacturing of samples with calibrated artificial defects relevant to the divertor design, is reported in this paper. In particular, it was concluded that defects detectable with non-destructive examination (NDE) techniques appeared to be acceptable during HHF experiments relevant to heat fluxes expected in the ITER divertor. On the basis of these results, a set of acceptance criteria was proposed and applied to the European vertical target medium-size qualification prototype: 98% of the inspected carbon fibre composite (CFC) monoblocks and 100% of tungsten (W) monoblock and flat tiles elements (i.e. 80% of the full units) were declared acceptable.

  1. Criteria for accepting piping thermal expansion movements during FFTF plant startup

    International Nuclear Information System (INIS)

    Clark, G.L.; Anderson, M.J.

    1981-03-01

    A deflection measurement program was conducted as a final step in the design qualification of the Fast Flux Test Facility liquid sodium piping. Measurements were obtained from the ambient empty position, through the 400 0 F (204 0 C) sodium fill, to an 800 0 F (427 0 C) maximum iso-thermal test condition. The program was designed to confirm that the pipe responded as predicted under both deadweight and thermal expansion loads. This paper describes the design of the test programs; the criteria used to select appropriate measurement locations from the approximately 4000 supports used on this pipe; and the criteria used to accept test results

  2. Development of Waste Acceptance Criteria at 221-U Building: Initial Flow and Transport Scoping Calculations

    Energy Technology Data Exchange (ETDEWEB)

    Freedman, Vicky L.; Zhang, Z. F.; Keller, Jason M.; Chen, Yousu

    2007-05-30

    This report documents numerical flow and transport simulations performed that establish initial waste acceptance criteria for the potential waste streams that may be safely sequestered in the 221-U Building and similar canyon structures. Specifically, simulations were executed to identify the maximum loading of contaminant mass (without respect to volume) that can be emplaced within the 221-U Building with no more than 1 pCi/m2 of contaminant migrating outside the structure within a 1,000 year time period. The initial scoping simulations were executed in one dimension to assess important processes, and then two dimensions to establish waste acceptance criteria. Two monolithic conditions were assessed: (1) a grouted canyon monolith; and (2) a canyon monolith filled with sand, both assuming no cracks or fissures were present to cause preferential transport. A three-staged approach was taken to account for different processes that may impact the amount of contaminant that can be safely sequestered in canyon structure. In the first stage, flow and transport simulations established waste acceptance criteria based on a linear (Kd) isotherm approach. In the second stage, impacts on thermal loading were examined and the differences in waste acceptance criteria quantified. In the third stage of modeling, precipitation/dissolution reactions were considered on the release and transport of the contaminants, and the subsequent impact on the maximum contaminant loading. The reactive transport modeling is considered a demonstration of the reactive transport capability, and shows the importance of its use for future performance predictions once site-specific data have been obtained.

  3. Preliminary selection criteria for the Yucca Mountain Project waste package container material

    International Nuclear Information System (INIS)

    Halsey, W.G.

    1991-01-01

    The Department of Energy's Yucca Mountain Project (YMP) is evaluating a site at Yucca Mountain in Nevada for construction of a geologic repository for the storage of high-level nuclear waste. Lawrence Livermore National Laboratory's (LLNL) Nuclear Waste Management Project (NWMP) has the responsibility for design, testing, and performance analysis of the waste packages. The design is performed in an iterative manner in three sequential phases (conceptual design, advanced conceptual design, and license application design). An important input to the start of the advanced conceptual design is the selection of the material for the waste containers. The container material is referred to as the 'metal barrier' portion of the waste package, and is the responsibility of the Metal Barrier Selection and Testing task at LLNL. The selection will consist of several steps. First, preliminary, material-independent selection criteria will be established based on the performance goals for the container. Second, a variety of engineering materials will be evaluated against these criteria in a screening process to identify candidate materials. Third, information will be obtained on the performance of the candidate materials, and final selection criteria and quantitative weighting factors will be established based on the waste package design requirements. Finally, the candidate materials will be ranked against these criteria to determine whether they meet the mandated performance requirements, and to provide a comparative score to choose the material for advanced conceptual design activities. This document sets forth the preliminary container material selection criteria to be used in screening candidate materials. 5 refs

  4. Defining waste acceptance criteria for the Hanford Replacement Cross-Site Transfer System

    International Nuclear Information System (INIS)

    Hudson, J.D.

    1996-04-01

    This document provides a methodology for defining waste acceptance criteria for the Hanford Replacement Cross-Site Transfer System (RCSTS). This methodology includes characterization, transport analysis, and control. A framework is described for each of these functions. A tool was developed for performing the calculations associated with the transport analysis. This tool, a worksheet that is available in formats acceptable for a variety of PC spreadsheet programs, enables a comparison of the pressure required to transport a given slurry at a rate that particulate suspension is maintained to the pressure drop available from the RCSTS

  5. Performance-based ECCS cladding acceptance criteria: A new simulation approach

    International Nuclear Information System (INIS)

    Zoino, A.; Alfonsi, A.; Rabiti, C.; Szilard, R.H.; Giannetti, F.; Caruso, G.

    2017-01-01

    Highlights: • A new methodology to demonstrate compliance with the new ECCS acceptance criteria is described. • A wide spectrum of fuel rod initial burnup states can be analysed in the design phase. • The coupled suite PHISICS/RELAP5-3D has been used in the analyses. • A demo simulation of the equilibrium cycle, load-following and a LOCA analysis has been performed. - Abstract: The U.S. Nuclear Regulatory Commission is currently proposing rulemaking to revise the Loss Of Coolant Accident (LOCA) and therefore the Emergency Core Cooling System (ECCS) acceptance criteria, to include the effects of higher burnup on cladding performance as well as to address other technical issues. As motivated by the new rule, the need to use advanced cladding designs may be a result. A loss of operational margin may result due to the more restrictive cladding embrittlement criteria. Initial and future compliance with the rule may significantly increase vendor workload and licensee cost, as a spectrum of fuel rod initial burnup states may need to be analyzed to demonstrate compliance. Consequently, there will be an increased focus on licensee decision making related to LOCA analysis to minimize cost and impact, and to manage margin. The study here presented has been part of a big project used to investigate technical issues and approaches for future industrial applications within the Risk-Informed Safety Margin Characterization (RISMC) Pathway. Specifically, the primary aim of this study is to lay out a roadmap to demonstrate the application of the new methodology. The present analysis shows a simplified version of the methodology of an industrial application on the Core Design and the Multi-Cycle Analysis.

  6. Preparation of acceptance tests and criteria for the Test Blanket Systems to be operated in ITER

    Energy Technology Data Exchange (ETDEWEB)

    Laan, J.G. van der, E-mail: JaapG.vanderLaan@iter.org [ITER Organization, Route de Vinon sur Verdon, CS 90 046, 13067 St Paul Lez Durance Cedex (France); Cuquel, B. [AIRBUS Defence and Space S.A.S., 13115 Saint Paul Lez Durance (France); Demange, D.; Ghidersa, B.-E. [Karlsruhe Institute of Technology, Karlsruhe (Germany); Giancarli, L.M.; Iseli, M.; Jourdan, T. [ITER Organization, Route de Vinon sur Verdon, CS 90 046, 13067 St Paul Lez Durance Cedex (France); Nevière, J.-C. [Comex-Nucleaire, 13115 Saint Paul Lez Durance (France); Pascal, R.; Ring, W. [ITER Organization, Route de Vinon sur Verdon, CS 90 046, 13067 St Paul Lez Durance Cedex (France)

    2015-10-15

    Highlights: • Initial guideline for acceptance testing and acceptance criteria for Test Blanket Systems in ITER. • These tests complement those required by the applicable codes and standards, and regulations. • Completion of TBS manufacture will be followed by Factory Acceptance Testing, prior to shipment. • Next steps are “Reception Inspection Tests”, and on-site pre-installation and components tests. • This guideline allows the detailing of the TBS specific test plans and their scheduling. - Abstract: This paper describes the main acceptance criteria and required acceptance tests for the components of the six Test Blanket Systems to be installed and operated in ITER. It summarizes the guide-line toward the establishment of detailed test plans for the TBS, starting from the end-product at the ITER Members factories, and to generally define the type of tests that have to be performed on the ITER site after shipment, and/or prior to the systems final commissioning phase.

  7. Basic considerations for the preparation of performance testing materials as related to performance evaluation acceptance criteria

    International Nuclear Information System (INIS)

    McCurdy, D.E.; Morton, J.S.

    2001-01-01

    The preparation of performance testing (PT) materials for environmental and radiobioassay applications involves the use of natural matrix materials containing the analyte of interest, the addition (spiking) of the analyte to a desired matrix (followed by blending for certain matrices) or a combination of the two. The distribution of the sample analyte concentration in a batch of PT samples will reflect the degree of heterogeneity of the analyte in the PT material and/or the reproducibility of the sample preparation process. Commercial and government implemented radioanalytical performance evaluation programs have a variety of acceptable performance criteria. The performance criteria should take into consideration many parameters related to the preparation of the PT materials including the within and between sample analyte heterogeneity, the accuracy of the quantification of an analyte in the PT material and to what 'known' value will a laboratory's result be compared. How sample preparation parameters affect the successful participation in performance evaluation (PE) programs having an acceptance criteria established as a percent difference from a 'known' value or in PE programs using other acceptance criteria, such as the guidance provided in ANSI N42.22 and N13.30 is discussed. (author)

  8. Preliminary radiation criteria and nuclear analysis for ETF

    International Nuclear Information System (INIS)

    Engholm, B.A.

    1980-09-01

    Preliminary biological and materials radiation dose criteria for the Engineering Test Facility are described and tabulated. In keeping with the ETF Mission Statement, a key biological dose criterion is a 24-hour shutdown dose rate of 2 mrem/hr on the surface of the outboard bulk shield. Materials dose criteria, which primarily govern the inboard shield design, include 10 9 rads exposure limit to epoxy insulation, 3 x 10 -4 dpa damage to the TF coil copper stabilizer, and a total nuclear heating rate of 5 kW in the inboard TF coils. Nuclear analysis performed during FY 80 was directed primarily at the inboard and outboard bulk shielding, and at radiation streaming in the neutral beam drift ducts. Inboard and outboard shield thicknesses to achieve the biological and materials radiation criteria are 75 cm inboard and 125 cm outboard, the configuration consisting of alternating layers of stainless steel and borated water. The outboard shield also includes a 5 cm layer of lead. NBI duct streaming analyses performed by ORNL and LASL will play a key role in the design of the duct and NBI shielding in FY 81. The NBI aluminum cryopanel nuclear heating rate during the heating cycle is about 1 milliwatt/cm 3 , which is far less than the permissible limit

  9. Acceptance criteria for determining armed response force size at nuclear power plants

    International Nuclear Information System (INIS)

    1983-02-01

    This guidance document contains acceptance criteria to be used in the NRC license review process. It consists of a scored worksheet and guidelines for interpreting the worksheet score that can be used in determining the adequacy of the armed response force size at a nuclear power reactor facility

  10. 48 CFR 15.607 - Criteria for acceptance and negotiation of an unsolicited proposal.

    Science.gov (United States)

    2010-10-01

    ... and negotiation of an unsolicited proposal. 15.607 Section 15.607 Federal Acquisition Regulations System FEDERAL ACQUISITION REGULATION CONTRACTING METHODS AND CONTRACT TYPES CONTRACTING BY NEGOTIATION Unsolicited Proposals 15.607 Criteria for acceptance and negotiation of an unsolicited proposal. (a) A...

  11. Acceptance criteria for the low enriched uranium reform amendments

    International Nuclear Information System (INIS)

    Emeigh, C.W.; Gundersen, G.E.; Withee, C.J.

    1984-05-01

    Revisions have been made to the material control and accounting requirements for NRC licensees authorized to possess and use more than one effective kilogram of special nuclear material of low strategic significance to have material control and accounting systems able to (1) confirm the presence of special nuclear material, (2) resolve indications of missing material, and (3) aid in the investigation and recovery of missing material. This document presents criteria that can be used to aid in judging the acceptability of licensee plans that would be submitted to the NRC for implementing these capabilities. General performance objectives, system capabilities, and recordkeeping are addressed

  12. 78 FR 37217 - Ted P. Sorenson; Notice of Preliminary Permit Application Accepted for Filing and Soliciting...

    Science.gov (United States)

    2013-06-20

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 14519-000] Ted P. Sorenson; Notice of Preliminary Permit Application Accepted for Filing and Soliciting Comments, Motions To Intervene, and Competing Applications On May 1, 2013, Ted P. Sorenson filed an application for a preliminary permit, pursuant to section 4(f) of the...

  13. Preliminary criteria for the handling of radioactive tea

    International Nuclear Information System (INIS)

    Oezemre, A.Y.

    1993-01-01

    Two years after the Chernobyl accident, tea plantations in northeastern Turkey, at Rize and its surroundings especially, were affected by radioactive fallout. As a radiological countermeasure, the turkish Atomic energy commission (AEC) was called in before tea packing and set up a maximum permissible limit of 12,500 Bq/kg for dry tea in the market; 58,078 t of radioactive tea (≥ 25,000 Bq/kg) were set apart as radioactive waste. In its concern to determine the best solution about the handling of radioactive tea and considering the national conditions, the AEC developed four preliminary criteria that led to select the burial option. (author)

  14. Contact-Handled Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    2005-01-01

    The purpose of this document is to summarize the waste acceptance criteria applicable to the transportation, storage, and disposal of contact-handled transuranic (CH-TRU) waste at the Waste Isolation Pilot Plant (WIPP). These criteria serve as the U.S. Department of Energy's (DOE) primary directive for ensuring that CH-TRU waste is managed and disposed of in a manner that protects human health and safety and the environment.The authorization basis of WIPP for the disposal of CH-TRU waste includes the U.S.Department of Energy National Security and Military Applications of Nuclear EnergyAuthorization Act of 1980 (reference 1) and the WIPP Land Withdrawal Act (LWA;reference 2). Included in this document are the requirements and associated criteriaimposed by these acts and the Resource Conservation and Recovery Act (RCRA,reference 3), as amended, on the CH-TRU waste destined for disposal at WIPP.|The DOE TRU waste sites must certify CH-TRU waste payload containers to thecontact-handled waste acceptance criteria (CH-WAC) identified in this document. Asshown in figure 1.0, the flow-down of applicable requirements to the CH-WAC istraceable to several higher-tier documents, including the WIPP operational safetyrequirements derived from the WIPP CH Documented Safety Analysis (CH-DSA;reference 4), the transportation requirements for CH-TRU wastes derived from theTransuranic Package Transporter-Model II (TRUPACT-II) and HalfPACT Certificates ofCompliance (references 5 and 5a), the WIPP LWA (reference 2), the WIPP HazardousWaste Facility Permit (reference 6), and the U.S. Environmental Protection Agency(EPA) Compliance Certification Decision and approval for PCB disposal (references 7,34, 35, 36, and 37). The solid arrows shown in figure 1.0 represent the flow-down of allapplicable payload container-based requirements. The two dotted arrows shown infigure 1.0 represent the flow-down of summary level requirements only; i.e., the sitesmust reference the regulatory source

  15. Contact-Handled Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    Washington TRU Solutions LLC

    2005-12-29

    The purpose of this document is to summarize the waste acceptance criteria applicable to the transportation, storage, and disposal of contact-handled transuranic (CH-TRU) waste at the Waste Isolation Pilot Plant (WIPP). These criteria serve as the U.S. Department of Energy's (DOE) primary directive for ensuring that CH-TRU waste is managed and disposed of in a manner that protects human health and safety and the environment.The authorization basis of WIPP for the disposal of CH-TRU waste includes the U.S.Department of Energy National Security and Military Applications of Nuclear EnergyAuthorization Act of 1980 (reference 1) and the WIPP Land Withdrawal Act (LWA;reference 2). Included in this document are the requirements and associated criteriaimposed by these acts and the Resource Conservation and Recovery Act (RCRA,reference 3), as amended, on the CH-TRU waste destined for disposal at WIPP.|The DOE TRU waste sites must certify CH-TRU waste payload containers to thecontact-handled waste acceptance criteria (CH-WAC) identified in this document. Asshown in figure 1.0, the flow-down of applicable requirements to the CH-WAC istraceable to several higher-tier documents, including the WIPP operational safetyrequirements derived from the WIPP CH Documented Safety Analysis (CH-DSA;reference 4), the transportation requirements for CH-TRU wastes derived from theTransuranic Package Transporter-Model II (TRUPACT-II) and HalfPACT Certificates ofCompliance (references 5 and 5a), the WIPP LWA (reference 2), the WIPP HazardousWaste Facility Permit (reference 6), and the U.S. Environmental Protection Agency(EPA) Compliance Certification Decision and approval for PCB disposal (references 7,34, 35, 36, and 37). The solid arrows shown in figure 1.0 represent the flow-down of allapplicable payload container-based requirements. The two dotted arrows shown infigure 1.0 represent the flow-down of summary level requirements only; i.e., the sitesmust reference the regulatory source

  16. The revision of RP 91 on criteria for acceptability of radiological (including radiotherapy) and nuclear medicine installations

    International Nuclear Information System (INIS)

    Faulkner, K.; Malone, J. F.; Christofides, S.; Lillicrap, S.; Horton, P.

    2013-01-01

    In 1997 the European Commission published Radiation Protection 91: 'Criteria for acceptability of radiological (including radiotherapy) and nuclear medicine installations'(1). This document specified the minimum criteria for acceptability. It has been used to this effect in legislation, codes of practice and by individual professionals. In a single document, it defined a level of performance at which remedial action was required. The document specified a series of parameters which characterised equipment performance and acceptable levels of performance. In its time it proved to be a useful document which was applied in member states to various degrees. Since the publication of Report 91 in 1997(1), a series of weaknesses emerged over time. Development of new radiological systems and technologies, as well as improvements in traditional technologies, has created circumstances where the acceptability criteria were in need of review. These weaknesses were recognised by the European Commission and a tender for its revision was issued. The criteria were developed by a team drawn from a broad range of backgrounds including hospitals, industry, government bodies, regulators and standardisation organisations. Representatives were mainly from Europe, but individuals from the American Association of Physicists in Medicine and International Atomic Energy Agency were included in the drafting process. This study describes the process employed in developing the revised document and the consultation process involved. One of the major difficulties the revision team encountered was related to an understanding of the actual meaning of the EC Directive(2). The view taken by the revision team was that Article 8, paragraph 3 places responsibilities on both the holders of radiological equipment and competent authorities. The acceptability criteria have been produced consistent with the European Commission's Medical Exposures Directive(2), which requires that patient exposures are

  17. 48 CFR 915.607 - Criteria for acceptance and negotiation of an unsolicited proposal.

    Science.gov (United States)

    2010-10-01

    ... and negotiation of an unsolicited proposal. 915.607 Section 915.607 Federal Acquisition Regulations System DEPARTMENT OF ENERGY CONTRACTING METHODS AND CONTRACT TYPES CONTRACTING BY NEGOTIATION Unsolicited Proposals 915.607 Criteria for acceptance and negotiation of an unsolicited proposal. (c) DOE's cost...

  18. Safety analysis, risk assessment, and risk acceptance criteria

    International Nuclear Information System (INIS)

    Jamali, K.

    1997-01-01

    This paper discusses a number of topics that relate safety analysis as documented in the Department of Energy (DOE) safety analysis reports (SARs), probabilistic risk assessments (PRA) as characterized primarily in the context of the techniques that have assumed some level of formality in commercial nuclear power plant applications, and risk acceptance criteria as an outgrowth of PRA applications. DOE SARs of interest are those that are prepared for DOE facilities under DOE Order 5480.23 and the implementing guidance in DOE STD-3009-94. It must be noted that the primary area of application for DOE STD-3009 is existing DOE facilities and that certain modifications of the STD-3009 approach are necessary in SARs for new facilities. Moreover, it is the hazard analysis (HA) and accident analysis (AA) portions of these SARs that are relevant to the present discussions. Although PRAs can be qualitative in nature, PRA as used in this paper refers more generally to all quantitative risk assessments and their underlying methods. HA as used in this paper refers more generally to all qualitative risk assessments and their underlying methods that have been in use in hazardous facilities other than nuclear power plants. This discussion includes both quantitative and qualitative risk assessment methods. PRA has been used, improved, developed, and refined since the Reactor Safety Study (WASH-1400) was published in 1975 by the Nuclear Regulatory Commission (NRC). Much debate has ensued since WASH-1400 on exactly what the role of PRA should be in plant design, reactor licensing, 'ensuring' plant and process safety, and a large number of other decisions that must be made for potentially hazardous activities. Of particular interest in this area is whether the risks quantified using PRA should be compared with numerical risk acceptance criteria (RACs) to determine whether a facility is 'safe.' Use of RACs requires quantitative estimates of consequence frequency and magnitude

  19. Transuranic advanced disposal systems: preliminary 239Pu waste-disposal criteria for Hanford

    International Nuclear Information System (INIS)

    Kennedy, W.E. Jr.; Napier, B.A.; Soldat, J.K.

    1982-08-01

    An evaluation of the feasibility and potential application of advanced disposal systems is being conducted for defense transuranic (TRU) wastes at the Hanford Site. The advanced waste disposal options include those developed to provide greater confinement than provided by shallow-land burial. An example systems analysis is discussed with assumed performance objectives and various Hanford-specific disposal conditions, waste forms, site characteristics, and engineered barriers. Preliminary waste disposal criteria for 239 Pu are determined by applying the Allowable Residual Contamination Level (ARCL) method. This method is based on compliance with a radiation dose rate limit through a site-specific analysis of the potential for radiation exposure to individuals. A 10,000 year environmental performance period is assumed, and the dose rate limit for human intrusion is assumed to be 500 mrem/y to any exposed individual. Preliminary waste disposal criteria derived by this method for 239 Pu in soils at the Hanford Site are: 0.5 nCi/g in soils between the surface and a depth of 1 m, 2200 nCi/g of soil at a depth of 5 m, and 10,000 nCi/g of soil at depths 10 m and below. These waste disposal criteria are based on exposure scenarios that reflect the dependence of exposure versus burial depth. 2 figures, 5 tables

  20. 77 FR 31843 - Swan Lake North Hydro, LLC; Notice of Preliminary Permit Application Accepted For Filing and...

    Science.gov (United States)

    2012-05-30

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 13318-002] Swan Lake North Hydro, LLC; Notice of Preliminary Permit Application Accepted For Filing and Soliciting Comments, Motions to Intervene, and Competing Applications On April 3, 2012, Swan Lake North Hydro, LLC, filed an application for a successive preliminary permit...

  1. Final report on a study of coherence in acceptability criteria for the technical aspects of risks associated with potentially hazardous installations

    International Nuclear Information System (INIS)

    Chicken, J.C.

    1988-01-01

    This report describes the results of the study that was made, under Contract No ECI-1390-B7221-85D, for the European Atomic Energy Community. The aim of the study was to examine and assess the feasibility of developing coherent and uniform criteria for judging the acceptability of the technical aspects of the risks associated with potentially hazardous installations. The report is arranged in five main parts. First the nature of hazardous installations is considered and this provides the basis for examination of the currently-used technical risk acceptability criteria. Next, the possible forms of criteria are explored and then universally consistent partial and overall technical risk acceptability criteria are proposed. Following this the implications of using the criteria proposed at the design, regulatory and operating levels are examined. Then, by testing the criteria against some real decisions, the practical problems of using the proposed criteria are explored. This leads to consideration of possible alternatives to the proposed criteria. Finally the conclusions that appear to be justified are summarized and the need for further work is identified

  2. 76 FR 76156 - Grand Coulee Project Hydroelectric Authority; Notice of Preliminary Permit Application Accepted...

    Science.gov (United States)

    2011-12-06

    ... Project Hydroelectric Authority; Notice of Preliminary Permit Application Accepted for Filing and... Federal Power Act (FPA), proposing to study the feasibility of the Scooteney Outlet Drop Hydroelectric..., Grand Coulee Project Hydroelectric Authority, P.O. Box 219, Ephrata, WA 98823; phone: (509) 754-2227...

  3. 78 FR 69080 - Houtama Hydropower LLC; Notice of Preliminary Permit Application Accepted for Filing and...

    Science.gov (United States)

    2013-11-18

    ... Hydropower LLC; Notice of Preliminary Permit Application Accepted for Filing and Soliciting Comments, Motions To Intervene, and Competing Applications On August 14, 2013, Houtama Hydropower LLC filed an.... Hampton, CEO, Houtama Hydropower [[Page 69081

  4. Qualifications of and acceptance criteria for transporting special form radioactive material

    International Nuclear Information System (INIS)

    Hovingh, J.

    1991-01-01

    A special form radioactive material is a radioactive material that is in an inert, insoluble, indispersible form such that even in the event of an accident, it will not be dispersed into the environment in a way that could have an adverse impact on public health and safety. Methods of qualifying a special form radioactive material are discussed. Interpretation of acceptance criteria are proposed for the transportation of Type B quantities of a special form radioactive material. 11 refs

  5. Preliminary study on acceptability of scope of thermal discharge mixing zone for nuclear power plant

    International Nuclear Information System (INIS)

    Liu Yongye; Yang Yang; Wang Liang; Chen Xiaoqiu; Liu Senlin

    2012-01-01

    Based on the situation that the existing domestic temperature control standards are not performable, the preliminary study on the acceptability of the mixing zone scope of thermal discharge for nuclear power plant was conducted in this paper, taking a coastal power station SNP as a case. The following preliminary conclusions could be drawn from the results of cluster analysis of the SNP site under different results of mathematical modeling and physical model test: 1) The influence intensity of ecological function of the SNP site seawater is small and the scope of thermal discharge mixing zone is acceptable under SNP-1 (Unit 1 and 2) operating condition; 2) the influence intensity of ecological function of the SNP site seawater is small and the scope of thermal discharge mixing zone is acceptable in spring under SNP-1 (Unit 1 and 2) and SNP-2 (Unit 3 and 4) operating condition, while the influence intensity of ecological function of the SNP site seawater is large and the scope of mixing zone is unacceptable in autumn under the same operating condition. (authors)

  6. 77 FR 7574 - Grand Coulee Project Hydroelectric Authority; Notice of Preliminary Permit Application Accepted...

    Science.gov (United States)

    2012-02-13

    ... Project Hydroelectric Authority; Notice of Preliminary Permit Application Accepted for Filing and Soliciting Comments and Motions To Intervene On January 13, 2012, the Grand Coulee Project Hydroelectric... study the feasibility of the P.E. Scooteney Wasteway Hydroelectric Project, to be located on the P.E...

  7. 10 CFR 50.46a - Acceptance criteria for reactor coolant system venting systems.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Acceptance criteria for reactor coolant system venting systems. 50.46a Section 50.46a Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND... function of these systems. High point vents are not required for the tubes in U-tube steam generators...

  8. 76 FR 76153 - Grand Coulee Project Hydroelectric Authority; Notice of Preliminary Permit Application Accepted...

    Science.gov (United States)

    2011-12-06

    ... Project Hydroelectric Authority; Notice of Preliminary Permit Application Accepted for Filing and... Hydroelectric Project (Scooteney Inlet Project or project) to be located on the Potholes East Canal, which is an..., Grand Coulee Project Hydroelectric Authority, P.O. Box 219, Ephrata, WA 98823; phone: (509) 754-2227...

  9. Acceptability criteria for linear dependence in validating UV-spectrophotometric methods of quantitative determination in forensic and toxicological analysis

    Directory of Open Access Journals (Sweden)

    L. Yu. Klimenko

    2014-08-01

    Full Text Available Introduction. This article is the result of authors’ research in the field of development of the approaches to validation of quantitative determination methods for purposes of forensic and toxicological analysis and devoted to the problem of acceptability criteria formation for validation parameter «linearity/calibration model». The aim of research. The purpose of this paper is to analyse the present approaches to acceptability estimation of the calibration model chosen for method description according to the requirements of the international guidances, to form the own approaches to acceptability estimation of the linear dependence when carrying out the validation of UV-spectrophotometric methods of quantitative determination for forensic and toxicological analysis. Materials and methods. UV-spectrophotometric method of doxylamine quantitative determination in blood. Results. The approaches to acceptability estimation of calibration models when carrying out the validation of bioanalytical methods is stated in international papers, namely «Guidance for Industry: Bioanalytical method validation» (U.S. FDA, 2001, «Standard Practices for Method Validation in Forensic Toxicology» (SWGTOX, 2012, «Guidance for the Validation of Analytical Methodology and Calibration of Equipment used for Testing of Illicit Drugs in Seized Materials and Biological Specimens» (UNODC, 2009 and «Guideline on validation of bioanalytical methods» (ЕМА, 2011 have been analysed. It has been suggested to be guided by domestic developments in the field of validation of analysis methods for medicines and, particularly, by the approaches to validation methods in the variant of the calibration curve method for forming the acceptability criteria of the obtained linear dependences when carrying out the validation of UV-spectrophotometric methods of quantitative determination for forensic and toxicological analysis. The choice of the method of calibration curve is

  10. 77 FR 7143 - Grand Coulee Project Hydroelectric Authority; Notice of Preliminary Permit Application Accepted...

    Science.gov (United States)

    2012-02-10

    ... Project Hydroelectric Authority; Notice of Preliminary Permit Application Accepted for Filing and Soliciting Comments and Motions To Intervene On January 13, 2012, the Grand Coulee Project Hydroelectric... study the feasibility of the P.E. 46A Wasteway Hydroelectric Project, to be located on the P.E. 46A...

  11. The Spanish version of the 2010 American College of Rheumatology Preliminary Diagnostic Criteria for fibromyalgia: reliability and validity assessment.

    Science.gov (United States)

    Casanueva, Benigno; García-Fructuoso, Ferrán; Belenguer, Rafael; Alegre, Cayetano; Moreno-Muelas, José V; Hernández, José L; Pina, Tinitario; González-Gay, Miguel Á

    2016-01-01

    To investigate the reliability and validity of the Spanish version of the 2010 American College of Rheumatology (ACR) Preliminary Diagnostic Criteria for Fibromyalgia (FM) in patients with chronic pain. The 2010 ACR Preliminary Diagnostic Criteria for FM were adapted to a Spanish version following the guidelines of the Rheumatology Spanish Society Study Group of FM. Based on the 1990 ACR classi cation criteria for FM, patients with chronic pain were initially divided into two groups: a FM group and another group of non-FM individuals. Patients from the FM group were evaluated by tender points (TP) examination, Fibromyalgia Impact Questionnaire (FIQ), Widespread Pain Index (WPI), and Symptom Severity Scale (SSS). The non-FM (control) group included patients with rheumatoid arthritis (RA) and osteoarthritis (OA). They were evaluated by WPI and SSS. We included 1,169 patients divided into two groups: FM group (n=803; 777 women and 26 men) and non-FM group (n= 366; 147 patients with RA, and 219 with OA). The median value of TP and FIQ in the FM group was 16 and 74 respectively. The preliminary 2010 ACR criteria were met by 665 (82.8%) FM patients and by 112 (30.6%) patients from the non-FM group (pFIQ (p<0.0001), WPI (p<0.0001) and SSS (p<0.0001) were observed when FM patients fulfilling the 2010 ACR criteria were compared with the remaining FM patients who did not fulfill these criteria. Sensitivity of the Spanish version of the 2010 ACR criteria was 85.6% (95%CI: 83.1-88.1), speci city 73.2% (95%CI: 68.4-78), positive predictive value 87.7% (95%CI: 85.3-90.1) and negative predictive value 69.4% (95%CI: 64.5-74.2). Our results indicate that the 2010 ACR Preliminary Diagnostic Criteria for FM may be useful to establish a diagnosis of FM in Spanish individuals with chronic pain.

  12. 75 FR 8320 - Coastal Hydropower LLC; Notice of Preliminary Permit Application Accepted for Filing and...

    Science.gov (United States)

    2010-02-24

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 13621-000] Coastal Hydropower LLC; Notice of Preliminary Permit Application Accepted for Filing and Soliciting Comments, Motions To Intervene, and Competing Applications February 18, 2010. On November 5, 2009, Coastal Hydropower...

  13. 76 FR 1613 - Mahoning Hydropower, LLC; Notice of Preliminary Permit Application Accepted for Filing and...

    Science.gov (United States)

    2011-01-11

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 13877-000] Mahoning Hydropower, LLC; Notice of Preliminary Permit Application Accepted for Filing and Soliciting Comments, Motions To Intervene, and Competing Applications January 4, 2011. On November 4, 2010, Mahoning Hydro, LLC...

  14. A research for Class II defect Bored Pile’s Accept Criteria: A case of Penang Second Marine bridge

    Science.gov (United States)

    Huang, Kang

    2018-03-01

    The aim of this preliminary research is to study the accept criteria of class II bored pile with subtle defect. According to a detailed comparison of the existed different standards, Chinese ones are more applicable especially for the large diameter bored piles. Through the concrete coring at pile No P25-03 of this case and the comparison to the actual calculation, the Class II pile’s defects were very minor. Comparison was also made for the effects on pile structural capacities before and after repair of the defects. the feasible repair proposal may bring forward to more defects to the piles. The Class II piles don’t need any further repairation when piles have typical of similar character and sonic logging test result with P25-03‘s one. For other Class II piles with some differences in characters, verification is needed through further concrete coring on the pile. The recommendation of this research could be adopted for the similar huge marine structures which installed large diameter bored piles.

  15. 76 FR 75543 - Castle Creek Hydroelectric Project; Notice of Preliminary Permit Application Accepted for Filing...

    Science.gov (United States)

    2011-12-02

    ... Hydroelectric Project; Notice of Preliminary Permit Application Accepted for Filing and Soliciting Comments... (FPA), proposing to study the feasibility of the Castle Creek Hydroelectric Project to be located on... be located adjacent to the original hydroelectric plant, with a single shaft Pelton turbine...

  16. 78 FR 42520 - Control Technology, Inc.; Notice of Preliminary Permit Application Accepted for Filing and...

    Science.gov (United States)

    2013-07-16

    ... Technology, Inc.; Notice of Preliminary Permit Application Accepted for Filing and Soliciting Comments, Motions To Intervene, and Competing Applications On December 18, 2012, Control Technology, Inc. filed an... lower reservoir, (3) a reinforced concrete penstock with intake/outlet structure in the upper reservoir...

  17. 75 FR 8321 - Coastal Hydropower LLC; Notice of Preliminary Permit Application Accepted for Filing and...

    Science.gov (United States)

    2010-02-24

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission Project No. 13619-000 Coastal Hydropower LLC; Notice of Preliminary Permit Application Accepted for Filing and Soliciting Comments, Motions to Intervene, and Competing Applications February 18, 2010. On November 5, 2009, Coastal Hydropower LLC filed...

  18. An approach to societal risk acceptance criteria and risk management

    International Nuclear Information System (INIS)

    Okrent, D.; Whipple, C.

    1977-06-01

    A quantitative approach to risk acceptance criteria and risk management is proposed for activities involving risk to individuals not receiving direct benefits, such as employment, from the activity. Societal activities are divided into major facilities or technologies, all or part of which are categorized as essential, beneficial, or peripheral, and a decreasing level of acceptable risk to the most exposed individual is proposed (say, 0.0002/year for essential, 0.00001/year for beneficial, and 0.000002/year for peripheral activity). The risk would be assessed at a high confidence level (say, 90%), thereby providing an incentive to the gaining of better knowledge. Each risk-producing facility, technology, etc., would have to undergo assessment both of risk to the individual and to society. The cost of the latter would have to be internalized, probably via a tax paid to the Federal Government, which in turn would redistribute the benefit as national health insurance or reduced taxes to the individual. Risk aversion to large events would be built into the internalization of the cost of risk

  19. Methods for verifying compliance with low-level radioactive waste acceptance criteria

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-09-01

    This report summarizes the methods that are currently employed and those that can be used to verify compliance with low-level radioactive waste (LLW) disposal facility waste acceptance criteria (WAC). This report presents the applicable regulations representing the Federal, State, and site-specific criteria for accepting LLW. Typical LLW generators are summarized, along with descriptions of their waste streams and final waste forms. General procedures and methods used by the LLW generators to verify compliance with the disposal facility WAC are presented. The report was written to provide an understanding of how a regulator could verify compliance with a LLW disposal facility`s WAC. A comprehensive study of the methodology used to verify waste generator compliance with the disposal facility WAC is presented in this report. The study involved compiling the relevant regulations to define the WAC, reviewing regulatory agency inspection programs, and summarizing waste verification technology and equipment. The results of the study indicate that waste generators conduct verification programs that include packaging, classification, characterization, and stabilization elements. The current LLW disposal facilities perform waste verification steps on incoming shipments. A model inspection and verification program, which includes an emphasis on the generator`s waste application documentation of their waste verification program, is recommended. The disposal facility verification procedures primarily involve the use of portable radiological survey instrumentation. The actual verification of generator compliance to the LLW disposal facility WAC is performed through a combination of incoming shipment checks and generator site audits.

  20. Methods for verifying compliance with low-level radioactive waste acceptance criteria

    International Nuclear Information System (INIS)

    1993-09-01

    This report summarizes the methods that are currently employed and those that can be used to verify compliance with low-level radioactive waste (LLW) disposal facility waste acceptance criteria (WAC). This report presents the applicable regulations representing the Federal, State, and site-specific criteria for accepting LLW. Typical LLW generators are summarized, along with descriptions of their waste streams and final waste forms. General procedures and methods used by the LLW generators to verify compliance with the disposal facility WAC are presented. The report was written to provide an understanding of how a regulator could verify compliance with a LLW disposal facility's WAC. A comprehensive study of the methodology used to verify waste generator compliance with the disposal facility WAC is presented in this report. The study involved compiling the relevant regulations to define the WAC, reviewing regulatory agency inspection programs, and summarizing waste verification technology and equipment. The results of the study indicate that waste generators conduct verification programs that include packaging, classification, characterization, and stabilization elements. The current LLW disposal facilities perform waste verification steps on incoming shipments. A model inspection and verification program, which includes an emphasis on the generator's waste application documentation of their waste verification program, is recommended. The disposal facility verification procedures primarily involve the use of portable radiological survey instrumentation. The actual verification of generator compliance to the LLW disposal facility WAC is performed through a combination of incoming shipment checks and generator site audits

  1. 78 FR 44557 - Turnagain Arm Tidal Energy Corporation; Notice of Preliminary Permit Application Accepted for...

    Science.gov (United States)

    2013-07-24

    ... Tidal Energy Corporation; Notice of Preliminary Permit Application Accepted for Filing and Soliciting Comments, Motions To Intervene, and Competing Applications On February 1, 2013, the Turnagain Arm Tidal... Federal Power Act (FPA), proposing to study the feasibility of the Turnagain Arm Tidal Electric Generation...

  2. 77 FR 58375 - Inglis Hydropower, LLC; Notice of Preliminary Permit Application Accepted for Filing and...

    Science.gov (United States)

    2012-09-20

    ... Hydropower, LLC; Notice of Preliminary Permit Application Accepted for Filing and Soliciting Comments, Motions To Intervene, and Competing Applications On May 18, 2012, Inglis Hydropower, LLC filed an... study the feasibility of a hydropower project located at the Inglis Bypass Channel, located on the...

  3. 77 FR 31349 - Coastal Hydropower, LLC; Notice of Preliminary Permit Application Accepted for Filing and...

    Science.gov (United States)

    2012-05-25

    ... Hydropower, LLC; Notice of Preliminary Permit Application Accepted for Filing and Soliciting Comments, Motions To Intervene, and Competing Applications On April 12, 2012, Coastal Hydropower, LLC filed an... generation of 31.5 gigawatt-hours. Applicant Contact: Neil Anderson, Coastal Hydropower, LLC, Key Centre, 601...

  4. 76 FR 75542 - Porcupine Dam Hydropower Project; Notice of Preliminary Permit Application Accepted for Filing...

    Science.gov (United States)

    2011-12-02

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 14290-000] Porcupine Dam Hydropower Project; Notice of Preliminary Permit Application Accepted for Filing and Soliciting Comments...), proposing to study the feasibility of the Porcupine Dam Hydropower Project to be located on the East Fork of...

  5. Small bore pipe acceptance criteria for watts bar nuclear plant Tennessee Valley Authority

    International Nuclear Information System (INIS)

    Sun, W.S.; Lee, R.L.; Kalyanan, N.

    1991-01-01

    Small bore pipe (≤2 inches NPS) is traditionally analyzed by simplified techniques using Cook Book approach, which yield conservative results. However, reconciliation of these systems for as-built condition where the original criteria is observed to have been exceeded (or due to additions etc.) generally becomes a time consuming and expensive operation since a rigorous computer aided analysis or a detailed hand calculation becomes necessary. The acceptance criteria in this paper can be effectively used in such cases. The approach involves utilizing basic engineering principles and plant specific parameters (such as earthquake spectra) to estimate the system response such as pipe stress due to various loading conditions, piping frequency, support and anchor loads, valve acceleration etc

  6. Long-Term Safety Analysis of Baldone Radioactive Waste Repository and Updating of Waste Acceptance Criteria

    International Nuclear Information System (INIS)

    2001-12-01

    The main objective of the project was to provide advice to the Latvian authorities on the safety enhancements and waste acceptance criteria for near surface radioactive waste disposal facilities of the Baldone repository. The project included the following main activities: Analysis of the current status of the management of radioactive waste in Latvia in general and, at the Baldone repository in particular Development of the short and long-term safety analysis of the Baldone repository, including: the planned increasing of capacity for disposal and long term storage, the radiological analysis for the post-closure period Development of the Environment Impact Statement, for the new foreseen installations, considering the non radiological components Proposal of recommendations for future updating of radioactive waste acceptance criteria Proposal of recommendations for safety upgrades to the facility. The work programme has been developed in phases and main tasks as follows. Phase 0: Project inception, Phase 1: Establishment of current status, plans and practices (Legislation, regulation and standards, Radioactive waste management, Waste acceptance criteria), Phase 2: Development of future strategies for long-term safety management and recommendations for safety enhancements. The project team found the general approach use at the installation, the basic design and the operating practices appropriate to international standards. Nevertheless, a number of items subject to potential improvements were also identified. These upgrading recommendations deal with general aspects of the management (mainly storage versus disposal of long-lived sources), site and environmental surveillance, packaging (qualification of containers, waste characterization requirements), the design of an engineered cap and strategies for capping. (author)

  7. An open trial of Acceptance-based Separated Family Treatment (ASFT) for adolescents with anorexia nervosa.

    Science.gov (United States)

    Timko, C Alix; Zucker, Nancy L; Herbert, James D; Rodriguez, Daniel; Merwin, Rhonda M

    2015-06-01

    Family based-treatments have the most empirical support in the treatment of adolescent anorexia nervosa; yet, a significant percentage of adolescents and their families do not respond to manualized family based treatment (FBT). The aim of this open trial was to conduct a preliminary evaluation of an innovative family-based approach to the treatment of anorexia: Acceptance-based Separated Family Treatment (ASFT). Treatment was grounded in Acceptance and Commitment Therapy (ACT), delivered in a separated format, and included an ACT-informed skills program. Adolescents (ages 12-18) with anorexia or sub-threshold anorexia and their families received 20 treatment sessions over 24 weeks. Outcome indices included eating disorder symptomatology reported by the parent and adolescent, percentage of expected body weight achieved, and changes in psychological acceptance/avoidance. Half of the adolescents (48.0%) met criteria for full remission at the end of treatment, 29.8% met criteria for partial remission, and 21.3% did not improve. Overall, adolescents had a significant reduction in eating disorder symptoms and reached expected body weight. Treatment resulted in changes in psychological acceptance in the expected direction for both parents and adolescents. This open trial provides preliminary evidence for the feasibility, acceptability, and efficacy of ASFT for adolescents with anorexia. Directions for future research are discussed. Copyright © 2015 Elsevier Ltd. All rights reserved.

  8. Expanded criteria donor kidneys for younger recipients: acceptable outcomes.

    Science.gov (United States)

    Goplani, K R; Kute, V B; Vanikar, A V; Shah, P R; Gumber, M R; Patel, H V; Modi, P R; Trivedi, H L

    2010-12-01

    European senior programme (ESP) is well known for acceptable outcomes using expanded criteria donor (ECD) kidneys from donors older than 65 years for recipients older than 65 years. The incidence of end-stage renal disease (ESRD) is 229/million in India with a mean age of 45 years. We performed a retrospective analysis of transplantation of ECD versus standard criteria donor (SCD) kidneys into younger recipients. Forty-three ECD transplantations among 158 deceased donor organ transplantation (DDOT) were performed between January 2006 and December 2009. Among 43 transplantation from 30 donors, 14 were dual kidney transplantations (DKT) performed based upon biopsy evaluation. All recipients received thymoglobulin (rATG) induction followed by immunosuppression with a steroid, mycophenolate mofetil (MMF), and a calcineurin inhibitor. Statistical analysis used chi-square test and unpaired Student t test. Kaplan-Meier curves were used for survival analysis. For ECD the mean donor age was 64 ± 11 years. Cerebrovascular accidents (CVA) were the cause of death among 60% of donors, 73.13% of whom were hypertensive and 23.13% diabetic. Mean DKT donor age was 75 ± 9.17 years versus 60 ± 8.0 years for single kidney transplantation (SKT). Mean recipient age of DKT versus SKT was 44 ± 12.4 years versus 43 ± 14 years. Mean serum creatinine (SCr; mg/dL) of SKT patients was 1.64 ± 0.75 versus 1.68 ± 0.46 in DKT. Mean follow-up was 455 ± 352 days. Mean SCr of 43 ECD recipients of mean age, 43.4 ± 14.2 years was 1.61 ± 0.61 mg/dL. Among 43 recipients, 23.25% were diabetic, 41.86% displayed delayed graft function (DGF), and 23.25% experienced biopsy-proven acute rejection (BPAR). Patient survival rate was 72.09% and graft survival rate was 67.44%. For SCD transplantations (n = 115), the mean donor age was 36 ± 14 years and recipient mean age was 32.8 ± 14.07 years. Mean SCr was 1.32 ± 0.46 mg/dL with 26.95% recipients displaying DGF, whereas 20.86% had BPAR. In the SCD

  9. Study of waste acceptance criteria for low-level radioactive waste from medical, industrial, and research facilities (Contract research)

    International Nuclear Information System (INIS)

    Koibuchi, Hiroto; Dohi, Terumi; Ishiguro, Hideharu; Hayashi, Masaru; Senda, Masaki

    2008-12-01

    Japan Atomic Energy Agency (JAEA) is supposed to draw up the plan for the disposal program of the very low-level radioactive waste and low-level radioactive waste generated from medical, industrial and research facilities. For instance, there are these facilities in JAEA, universities, private companies, and so on. JAEA has to get to know about the waste and its acceptance of other institutions described above because it is important for us to hold the licenses for the disposal program regarding safety assessment. This report presents the basic data concerning radioactive waste of research institutes etc. except RI waste, domestic and foreign information related to acceptance criteria for disposal of the low-level radioactive waste, the current status of foreign medical waste management, waste acceptance, and such. In this report, Japan's acceptance criteria were summarized on the basis of present regulation. And, the criteria of foreign countries, United States, France, United Kingdom and Spain, were investigated by survey of each reference. In addition, it was reported that the amount of waste from laboratories etc. for near-surface disposal and their characterization in our country. The Subjects of future work: the treatment of hazardous waste, the problem of the double-regulation (the Nuclear Reactor Regulation Law and the Law Concerning Prevention from Radiation Hazards due to Radioisotopes and Others) and the possession of waste were discussed here. (author)

  10. Preliminary long-term stability criteria for compressed air energy storage caverns in salt domes

    Energy Technology Data Exchange (ETDEWEB)

    Thoms, R.L.; Martinez, J.D.

    1978-08-01

    Air storage caverns, which are an essential and integral component of a CAES plant, should be designed and operated so as to perform satisfactorily over the intended life of the overall facility. It follows that the long-term ''stability'' of air storage caverns must be considered as a primary concern in projecting the satisfactory operation of CAES facilities. As used in the report, ''stability'' of a storage cavern implies the extent to which an acceptable amount of cavern storage volume can be utilized with routine maintenance for a specified time interval, e.g., 35 years. In this context, cavern stability is relative to both planned utilization and time interval of operation. The objective of the study was to review the existing literature and consult knowledgeable workers in the storage industry, and then report state-of-the-art findings relative to long-term stability of compressed air energy storage caverns in salt domes. Further, preliminary cavern stability criteria were to be presented in a form consistent with the amount of information available on cavern performance in salt domes. Another objective of the study was to outline a methodology for determining the long-term stability of site-specific CAES cavern systems in salt domes.

  11. Acceptance criteria for the low enriched uranium reform amendments. Revision 1

    International Nuclear Information System (INIS)

    Emeigh, C.W.; Gundersen, G.E.; Withee, C.J.

    1985-04-01

    Revisions have been made to the material control and accounting requirements for NRC licensees authorized to possess and use more than one effective kilogram of special nuclear material of low strategic significance to have MC and A systems able to (1) confirm the presence of special nuclear material, (2) resolve indications of missing material, and (3) aid in the investigation and recovery of missing material. This document presents criteria that can be used to aid in judging the acceptability of licensee plans that would be submitted to the NRC for implementing these capabilities. General performance objectives, system capabilities, and recordkeeping are addressed

  12. Preliminary waste acceptance criteria for the ICPP spent fuel and waste management technology development program

    International Nuclear Information System (INIS)

    Taylor, L.L.; Shikashio, R.

    1993-09-01

    The purpose of this document is to identify requirements to be met by the Producer/Shipper of Spent Nuclear Fuel/High-LeveL Waste SNF/HLW in order for DOE to be able to accept the packaged materials. This includes defining both standard and nonstandard waste forms

  13. New contact boiling experiments to evaluate Calandria tube strain acceptance criteria

    Energy Technology Data Exchange (ETDEWEB)

    El-Hawary, M.; Szymanski, J.; Tanase, A.; Delja, A.; Oussoren, A., E-mail: Magdy.El-Hawary@cnsc-ccsn.gc.ca [Canadian Nuclear Safety Comission, Ottawa, ON (Canada); Neal, P. [Canadian Nuclear Laboratories, Chalk River, ON (Canada)

    2015-07-01

    The Canadian Nuclear Safety Commission(CNSC) has contracted the Canadian Nuclear Laboratories(CNL) to conduct additional Contact Boiling (CB) experiments with the main objective of evaluating the acceptance criterion of CalandriaTube (CT) strain limit of 2%, proposed by the industry for fuel channel integrity assessments. The test conditions are selected using analytical tools and guidance from existing CANDU Owners Group (COG) test results, so as to lead to CT strain close to this value. The experiments will also be used to evaluate the CT quench temperature correlation proposed. This paper presents conditions selected for the first three experiments, their most important results and their preliminary analysis, with a focus on the test which produced CT strain in excess of 2%. (author)

  14. 76 FR 25322 - Oklahoma Rose Water LLC; Notice of Preliminary Permit Application Accepted for Filing and...

    Science.gov (United States)

    2011-05-04

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 13854-000] Oklahoma Rose Water LLC; Notice of Preliminary Permit Application Accepted for Filing and Soliciting Comments, Motions To Intervene, and Competing Applications On September 30, 2010, Oklahoma Rose Water LLC filed an...

  15. 78 FR 9687 - Prineville Energy Storage, LLC; Notice of Preliminary Permit Application Accepted for Filing and...

    Science.gov (United States)

    2013-02-11

    ... Energy Storage, LLC; Notice of Preliminary Permit Application Accepted for Filing and Soliciting Comments, Motions To Intervene, and Competing Applications On August 31, 2012, Prineville Energy Storage, LLC, filed... Contact: Mr. Matthew Shapiro, Chief Executive Officer, Prineville Energy Storage, LLC, 1210 W. Franklin...

  16. 75 FR 78235 - Dodge Mill Realty, LLC; Notice of Preliminary Permit Application Accepted for Filing and...

    Science.gov (United States)

    2010-12-15

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 13890-000] Dodge Mill Realty, LLC; Notice of Preliminary Permit Application Accepted for Filing and Soliciting Comments, Motions To Intervene, and Competing Applications December 8, 2010. On December 3, 2010, Dodge Mill Realty...

  17. 77 FR 4290 - Conway Ranch Hydropower Project; Notice of Preliminary Permit Application Accepted for Filing and...

    Science.gov (United States)

    2012-01-27

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 13089-002] Conway Ranch Hydropower Project; Notice of Preliminary Permit Application Accepted for Filing and Soliciting Comments... study the feasibility of the Conway Ranch Hydropower Project to be located on Virginia Creek, near the...

  18. 78 FR 71601 - KC Small Hydro LLC; Advanced Hydropower, Inc.; Notice of Preliminary Permit Application Accepted...

    Science.gov (United States)

    2013-11-29

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project Nos. 14521-001, 14561-000] KC Small Hydro LLC; Advanced Hydropower, Inc.; Notice of Preliminary Permit Application Accepted for Filing and Soliciting Comments, Motions To Intervene, and Competing Applications On May 13, 2013, KC Scoby...

  19. Summary of the Preliminary Analysis of Savannah River Depleted Uranium Trioxide

    International Nuclear Information System (INIS)

    2010-01-01

    This report summarizes a preliminary special analysis of the Savannah River Depleted Uranium Trioxide waste stream (SVRSURANIUM03, Revision 2). The analysis is considered preliminary because a final waste profile has not been submitted for review. The special analysis is performed to determine the acceptability of the waste stream for shallow land burial at the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada National Security Site (NNSS). The Savannah River Depleted Uranium Trioxide waste stream requires a special analysis because the waste stream's sum of fractions exceeds one. The 99Tc activity concentration is 98 percent of the NNSS Waste Acceptance Criteria and the largest single contributor to the sum of fractions.

  20. 75 FR 78236 - Pennamaquan Tidal Power, LLC; Notice of Preliminary Permit Application Accepted for Filing and...

    Science.gov (United States)

    2010-12-15

    ... Tidal Power, LLC; Notice of Preliminary Permit Application Accepted for Filing and Soliciting Comments, Motions To Intervene, and Competing Applications December 8, 2010. On November 22, 2010, Pennamaquan Tidal... Act (FPA), proposing to study the feasibility of the Pennamaquan Tidal Power Plant Project to be...

  1. 75 FR 18190 - New Jersey Water Supply Authority; Notice of Preliminary Permit Application Accepted for Filing...

    Science.gov (United States)

    2010-04-09

    ... Contact: Edward Buss, P.E., New Jersey Water Supply Authority, 1851 State Hwy. 31, Clinton, NJ 08800, (908... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 13399-000] New Jersey Water Supply Authority; Notice of Preliminary Permit Application Accepted for Filing and Soliciting Comments...

  2. 76 FR 9340 - Mill Town Power Project; Notice of Preliminary Permit Application Accepted for Filing and...

    Science.gov (United States)

    2011-02-17

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 13995-000] Mill Town Power Project; Notice of Preliminary Permit Application Accepted for Filing and Soliciting Comments, Motions To Intervene, and Competing Applications On January 4, 2011, Mill Town Power Project filed an application for a...

  3. 78 FR 5798 - Ceresco Hydroelectric Dam, LLC; Notice of Preliminary Permit Application Accepted for Filing and...

    Science.gov (United States)

    2013-01-28

    ... Hydroelectric Dam, LLC; Notice of Preliminary Permit Application Accepted for Filing and Soliciting Comments, Motions To Intervene, and Competing Applications On October 19, 2012, Ceresco Hydroelectric Dam, LLC...), proposing to study the feasibility of the Ceresco Hydroelectric Project (Ceresco Project or project) to be...

  4. 75 FR 61479 - Kendall Head Tidal Energy Project; Notice of Preliminary Permit Application Accepted for Filing...

    Science.gov (United States)

    2010-10-05

    ... Tidal Energy Project; Notice of Preliminary Permit Application Accepted for Filing and Soliciting... Federal Power Act, proposing to study the feasibility of the Kendall Head Tidal Energy Project, located in.... The proposed project would consist of: (1) 4 OCGen\\TM\\ hydrokinetic tidal devices each consisting of...

  5. 75 FR 2128 - Basin Farm Renewable, LLC; Notice of Preliminary Permit Application Accepted for Filing and...

    Science.gov (United States)

    2010-01-14

    ... Renewable, LLC; Notice of Preliminary Permit Application Accepted for Filing and Soliciting Comments... Renewable, LLC filed an application, pursuant to section 4(f) of the Federal Power Act, proposing to study the feasibility of the Basin Farm Renewable Energy Project, to be located on Saxtons River, in...

  6. 78 FR 61958 - New England Hydropower Company, LLC; Notice of Preliminary Permit Application Accepted for Filing...

    Science.gov (United States)

    2013-10-08

    ... Hydropower Company, LLC; Notice of Preliminary Permit Application Accepted for Filing and Soliciting Comments, Motions To Intervene, and Competing Applications On August 20, 2013, the New England Hydropower Company... river are owned by the city of Meriden. Applicant Contact: Mr. Michael C. Kerr, New England Hydropower...

  7. Preliminary safety criteria for organic watch list tanks at the Hanford site

    International Nuclear Information System (INIS)

    Webb, A.B.; Stewart, J.L.; Turner, O.A.; Plys, M.G.; Malinovic, B.; Grigsby, J.M.; Camaioni, D.M.; Heasler, P.G.; Samuels, W.O.; Toth, J.J.

    1995-11-01

    Condensed-phase, rapid reactions of organic salts with nitrates/nitrites in Hanford High Level Radioactive Waste single-shell tanks could lead to structural failure of the tanks resulting in significant releases of radionuclides and toxic materials. This report establishes appropriate preliminary safety criteria to ensure that tank wastes will be maintained safe. These criteria show that if actual dry wastes contain less than 1.2 MJ/kg of reactants reaction energy or less 4.5 wt % of total organic carbon, then the waste will be safe and will not propagate if ignited. Waste moisture helps to retard reactions; when waste moisture exceeds 20 wt %, rapid reactions are prevented, regardless of organic carbon concentrations. Aging and degradation of waste materials has been considered to predict the types and amounts to organic compounds present in the waste. Using measurements of 3 waste phases (liquid, salt cake, and sludge) obtained from tank waste samples analyzed in the laboratory, analysis of variance (ANOVA) models were used to estimate waste states for unmeasured tanks. The preliminary safety criteria are based upon calorimetry and propagation testing of likely organic compounds which represent actual tank wastes. These included sodium salts of citrate, formate, acetate and hydroxyethylethylenediaminetricetate (HEDTA). Hot cell tests of actual tank wastes are planned for the future to confirm propagation tests performed in the laboratory. The effects of draining liquids from the tanks which would remove liquids and moisture were considered because reactive waste which is too dry may propagate. Evaporation effects which could remove moisture from the tanks were also calculated. The various ways that the waste could be heated or ignited by equipment failures or tank operations activities were considered and appropriate monitoring and controls were recommended

  8. Preliminary safety criteria for organic watch list tanks at the Hanford site

    Energy Technology Data Exchange (ETDEWEB)

    Webb, A.B.; Stewart, J.L.; Turner, O.A. [Westinghouse Hanford Co., Richland, WA (United States); Plys, M.G.; Malinovic, B. [Fauske and Associates, Inc., Burr Ridge, IL (United States); Grigsby, J.M. [G & P Consulting, Inc. (United States); Camaioni, D.M.; Heasler, P.G.; Samuels, W.O.; Toth, J.J. [Pacific Northwest Lab., Portland, OR (United States)

    1995-11-01

    Condensed-phase, rapid reactions of organic salts with nitrates/nitrites in Hanford High Level Radioactive Waste single-shell tanks could lead to structural failure of the tanks resulting in significant releases of radionuclides and toxic materials. This report establishes appropriate preliminary safety criteria to ensure that tank wastes will be maintained safe. These criteria show that if actual dry wastes contain less than 1.2 MJ/kg of reactants reaction energy or less 4.5 wt % of total organic carbon, then the waste will be safe and will not propagate if ignited. Waste moisture helps to retard reactions; when waste moisture exceeds 20 wt %, rapid reactions are prevented, regardless of organic carbon concentrations. Aging and degradation of waste materials has been considered to predict the types and amounts to organic compounds present in the waste. Using measurements of 3 waste phases (liquid, salt cake, and sludge) obtained from tank waste samples analyzed in the laboratory, analysis of variance (ANOVA) models were used to estimate waste states for unmeasured tanks. The preliminary safety criteria are based upon calorimetry and propagation testing of likely organic compounds which represent actual tank wastes. These included sodium salts of citrate, formate, acetate and hydroxyethylethylenediaminetricetate (HEDTA). Hot cell tests of actual tank wastes are planned for the future to confirm propagation tests performed in the laboratory. The effects of draining liquids from the tanks which would remove liquids and moisture were considered because reactive waste which is too dry may propagate. Evaporation effects which could remove moisture from the tanks were also calculated. The various ways that the waste could be heated or ignited by equipment failures or tank operations activities were considered and appropriate monitoring and controls were recommended.

  9. CTOD-based acceptance criteria for heat exchanger head staybolts

    International Nuclear Information System (INIS)

    Lam, P.S.; Sindelar, R.L.; Barnes, D.M.; Awadalla, N.G.

    1992-01-01

    The primary coolant piping system of the Savannah River Site (SRS) reactors contains twelve heat exchangers to remove the waste heat from the nuclear materials production. A large break at the inlet or outlet heads of the heat exchangers would occur if the restraint members of the heads become inactive. The heat exchanger head is attached to the tubesheet by 84 staybolts. The structural integrity of the heads is demonstrated by showing the redundant capacity of the staybolts to restrain the head at design conditions and under seismic loadings. The beat exchanger head is analyzed with a three- dimensional finite element model. The restraint provided by the staybolts is evaluated for several postulated cases of inactive or missing staybolts, that is, bolts that have a flaw exceeding the ultrasonic testing (UT) threshold depth of 25% of the bolt diameter. A limit of 6 inactive staybolts is reached with a fracture criterion based on the maximum allowable local displacement at the active staybolts which corresponds to the crack tip opening displacement (CTOD) of 0.032 inches. An acceptance criteria methodology has been developed to disposition flaws reported in the staybolt inspections while ensuring adequate restraint capacity of the staybolts to maintain integrity of the heat exchanger heads against collapse. The methodology includes an approach for the baseline and periodic inspections of the staybolts. A total of up to 6 staybolts, reported as containing flaws with depths at or exceeding 25% would be acceptable in the heat exchanger

  10. 75 FR 2127 - Basin Farm Renewable, LLC; Notice of Preliminary Permit Application Accepted for Filing and...

    Science.gov (United States)

    2010-01-14

    ... Renewable, LLC; Notice of Preliminary Permit Application Accepted for Filing and Soliciting Comments... Renewable, LLC filed an application, pursuant to section 4(f) of the Federal Power Act, proposing to study the feasibility of the Basin Farm Renewable Energy Project Project, to be located on Saxtons River, in...

  11. Presentation of a methodology for measuring social acceptance of three hydrogen storage technologies and preliminary results

    Energy Technology Data Exchange (ETDEWEB)

    Noirot, I.; Bigay, C. N.

    2005-07-01

    Hydrogen storage is a key technology for the extensive use of H2 as energy carrier. As none of the current technologies satisfies all of the hydrogen storage attributes required by manufacturers and end users, there is intense research works aiming at developing viable solutions. A broad objective of the StorHy European project is to provide technological storage solutions, which are attractive from an economical, environmental and safety point of view. A specific sub-project is dedicated to the comparison of three different potential storage technologies for transport applications (compressed gas, cryogenic liquid, solid media). This evaluation is carried out in a harmonised way, based on common tools and assessment strategies that could be useful for decision makers and stakeholders. The assessment is achieved in a 'sustainable development' spirit, taking into consideration the technical, environmental, economical, safety and social requirements. The latter ones have newly emerged in such evaluations, based on the Quality Function Deployment (QFD) approach, and would require to be further studied. Hydrogen acceptability studies have been conducted in previous projects. They have been reviewed by LBST in the AcceptH2 project Public acceptance of Hydrogen Transport Technologies : Analysis and comparisons of existing studies (www. accepth2. com - August 2003). During these hydrogen acceptance surveys, mainly fuel cell bus passengers from demonstration projects around the world have been questioned. The work presented in this paper goes further in the methodology refinement as it focuses on the evaluation of hydrogen storage solutions. It proposes a methodological tool for efficient social evaluation of new technologies and associated preliminary results concerning France. In a global approach to sustainable development, the CEA has developed a new methodology to evaluate its current research projects : Multicriteria Analysis for Sustainable Industrial

  12. Structural acceptance criteria for the evaulation of existing double-shell waste storage tanks located at the Hanford site, Richland, Washington

    International Nuclear Information System (INIS)

    Julyk, L.J.; Day, A.D.; Dyrness, A.D.; Moore, C.J.; Peterson, W.S.; Scott, M.A.; Shrivastava, H.P.; Sholman, J.S.; Watts, T.N.

    1995-09-01

    The structural acceptance criteria contained herein for the evaluation of existing underground double-shell waste storage tanks located at the Hanford Site is part of the Life Management/Aging Management Program of the Tank Waste Remediation System. The purpose of the overall life management program is to ensure that confinement of the waste is maintained over the required service life of the tanks. Characterization of the present condition of the tanks, understanding and characterization of potential degradation mechanisms, and development of tank structural acceptance criteria based on previous service and projected use are prerequisites to assessing tank integrity, to projecting the length of tank service, and to developing and applying prudent fixes or repairs. The criteria provided herein summarize the requirements for the analysis and structural qualification of the existing double-shell tanks for continued operation. Code reconciliation issues and material degradation under aging conditions are addressed. Although the criteria were developed for double-shell tanks, many of the provisions are equally applicable to single-shell tanks. However, the criteria do not apply to the evaluation of tank appurtenances and buried piping

  13. 75 FR 21289 - Oregon Wave Energy Partners I, LLC; Notice of Preliminary Permit Application Accepted for Filing...

    Science.gov (United States)

    2010-04-23

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 12749-002] Oregon Wave Energy Partners I, LLC; Notice of Preliminary Permit Application Accepted for Filing and Soliciting.... Charles F. Dunleavy, Oregon Wave Energy Partners I, LLC, 1590 Reed Road, Pennington, NJ 08534. FERC...

  14. Acceptance criteria for disposal of radioactive waste in Romania

    International Nuclear Information System (INIS)

    Dogaru, D.

    2001-01-01

    In Romania the institutional radioactive waste are managed by National Institute of R and D for Physics and Nuclear Engineering. The institutional radioactive waste are collected, treated and conditioned at the Radioactive Waste Treatment Plant then transferred and disposed to the National Repository of Radioactive Waste at Baita Bihor. National Repository for Radioactive Waste is a long term storage facility. The repository is placed in a former worked out uranium ore mine, being excavated in the Bihor peak. The repository has been sited taking into account the known geological, hydrogeoloical, seismic and meteorological and mining properties of a uranium mining site. In the absence of an updated Safety Analysis Report, the maximum radioactive content permitted by the regulatory authority in the operation license is below the values reported for other engineered repositories in mine galleries. The paper presents the acceptance criteria for disposal of radioactive waste in National Repository for Radioactive Waste at Baita Bihor. (author)

  15. Determination of acceptable risk criteria for nuclear waste management

    International Nuclear Information System (INIS)

    Cohen, J.J.

    1977-01-01

    The initial phase of the work performed during FY 1977 consisted of performing a ''scoping'' study to define issues, determine an optimal methodology for their resolution, and compile a data base for acceptable risk criteria development. The issues, spanning technical, psychological, and ethical dimensions, were categorized in seven major areas: (1) unplanned or accidental events, (2) present vs future risks, (3) institutional controls and retrievability, (4) dose-response mechanism and uncertainty, (5) spatial distribution of exposed populations, (6) different types of nuclear wastes, and (7) public perception. The optimum methodology for developing ARC was determined to be multi-attribute decision analysis encompassing numerous specific techniques for choosing, from among several alternatives, the optimal course of action when the alternatives are constrained to meet specified attributes. The data base developed during the study comprises existing regulations and guidelines, maximum permissible dose, natural geologic hazards, nonradioactive hazardous waste practices, bioethical perspectives, and data from an opinion survey

  16. Determination of acceptable risk criteria for nuclear waste management

    Energy Technology Data Exchange (ETDEWEB)

    Cohen, J.J.

    1977-10-21

    The initial phase of the work performed during FY 1977 consisted of performing a ''scoping'' study to define issues, determine an optimal methodology for their resolution, and compile a data base for acceptable risk criteria development. The issues, spanning technical, psychological, and ethical dimensions, were categorized in seven major areas: (1) unplanned or accidental events, (2) present vs future risks, (3) institutional controls and retrievability, (4) dose-response mechanism and uncertainty, (5) spatial distribution of exposed populations, (6) different types of nuclear wastes, and (7) public perception. The optimum methodology for developing ARC was determined to be multi-attribute decision analysis encompassing numerous specific techniques for choosing, from among several alternatives, the optimal course of action when the alternatives are constrained to meet specified attributes. The data base developed during the study comprises existing regulations and guidelines, maximum permissible dose, natural geologic hazards, nonradioactive hazardous waste practices, bioethical perspectives, and data from an opinion survey.

  17. Criteria of acceptability relating to the approval of consumer goods containing radioactive substances

    International Nuclear Information System (INIS)

    Paynter, R.A.

    1992-01-01

    The criteria are described which the Board intends to use when considering goods containing radioactive substances for approval under the regulations that the Government intends to make with respect to such goods. Some products are deemed unacceptable in principle because there would appear to be no justification for the use of radioactive substances in them. Examples of such products are given. Other products may be approved for supply to the public depending on the doses likely to be received by individuals, principally those who use the products. A lower dose is considered acceptable from products that do not contribute to safety than from products that do. In the interim, before the regulations are made, the criteria will be used as the basis of the Board's advice to suppliers and manufacturers of goods containing radioactive substances. (Author)

  18. 76 FR 34975 - U.S. Farmers, LLC; Notice of Preliminary Permit Application Accepted for Filing and Soliciting...

    Science.gov (United States)

    2011-06-15

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 14102-000] U.S. Farmers, LLC; Notice of Preliminary Permit Application Accepted for Filing and Soliciting Comments, Motions To Intervene, and Competing Applications On February 22, 2011, U.S. Farmers, LLC filed an application for a...

  19. 77 FR 60424 - FFP Project 73 LLC; Notice of Preliminary Permit Application Accepted for Filing and Soliciting...

    Science.gov (United States)

    2012-10-03

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 13484-001] FFP Project 73 LLC; Notice of Preliminary Permit Application Accepted for Filing and Soliciting Comments, Motions To Intervene, and Competing Applications On September 4, 2012, FFP Project 73, LLC filed an application for a...

  20. Preliminary criteria for shallow-land storage/disposal of low-level radioactive solid waste in an arid environment

    International Nuclear Information System (INIS)

    Shord, A.L.

    1979-09-01

    Preliminary criteria for shallow land storage/disposal of low level radioactive solid waste in an arid environment were developed. Criteria which address the establishment and operation of a storage/disposal facility for low-level radioactive solid wastes are discussed. These were developed from the following sources: (1) a literature review of solid waste burial; (2) a review of the regulations, standards, and codes pertinent to the burial of radioactive wastes; (3) on site experience; and (4) evaluation of existing burial grounds and practices

  1. 76 FR 30936 - West Maui Pumped Storage Water Supply, LLC; Notice of Preliminary Permit Application Accepted for...

    Science.gov (United States)

    2011-05-27

    ... Storage Water Supply, LLC; Notice of Preliminary Permit Application Accepted for Filing and Soliciting...-acre reservoir; (4) a turnout to supply project effluent water to an existing irrigation system; (5) a...,000 megawatt-hours. Applicant Contact: Bart M. O'Keeffe, West Maui Pumped Storage Water Supply, LLC, P...

  2. 78 FR 77118 - KC Small Hydro, LLC; Notice of Amended Preliminary Permit Application Accepted for Filing and...

    Science.gov (United States)

    2013-12-20

    ..., Motions To Intervene, and Competing Applications On May 28, 2013, KC Scoby Hydro, LLC, filed an... 28, 2013, application and sent an acceptance letter to KC Scoby Hydro, LLC. Subsequently, On October 28, 2013, KC Scoby Hydro, LLC, amended its preliminary permit application to change its name to KC...

  3. Evaluation of ISDP Batch 2 Qualification Compliance to 512-S, DWPF, Tank Farm, and Saltstone Waste Acceptance Criteria

    Energy Technology Data Exchange (ETDEWEB)

    Shafer, A.

    2010-05-05

    The purpose of this report is to document the acceptability of the second macrobatch (Salt Batch 2) of Tank 49H waste to H Tank Farm, DWPF, and Saltstone for operation of the Interim Salt Disposition Project (ISDP). Tank 49 feed meets the Waste Acceptance Criteria (WAC) requirements specified by References 11, 12, and 13. Salt Batch 2 material is qualified and ready to be processed through ARP/MCU to the final disposal facilities.

  4. 76 FR 28025 - East Maui Pumped Storage Water Supply LCC; Notice of Preliminary Permit Application Accepted for...

    Science.gov (United States)

    2011-05-13

    ... Storage Water Supply LCC; Notice of Preliminary Permit Application Accepted for Filing and Soliciting... Act (FPA), proposing to study the feasibility of the East Maui Pumped Storage Water Supply Project to.... Bart M. O'Keeffe, East Maui Pumped Storage Water Supply LLC; P.O. Box 1916; Discovery Bay, CA 94505...

  5. Self-acceptance of stuttering: A preliminary study.

    Science.gov (United States)

    De Nardo, Thales; Gabel, Rodney M; Tetnowski, John A; Swartz, Eric R

    2016-01-01

    This study explored the relationship between self-acceptance of stuttering and (1) psychosocial factors (self-esteem, hostility towards others, emotional support, and perceived discrimination); (2) treatment history (support group participation, therapy duration, and perceived therapy success); and (3) previously reported variables in self-acceptance of stuttering, which include age and stuttering severity. Participants were 80 adults who stutter who were recruited with assistance from the National Stuttering Association and Board Certified Specialists in Fluency Disorders. Participants completed an electronic survey composed of an acceptance of stuttering scale, psychosocial scales, and a participant information questionnaire. Statistical analysis identified significant correlations between participants' reports of self-acceptance of stuttering and self-esteem, perceived discrimination, hostility towards others, and perceived therapy outcome. Self-esteem was positively correlated with self-acceptance, while hostility towards others and perceived discrimination was negatively correlated with self-acceptance. Participants who perceived their therapy outcome to be successful were significantly more likely to report higher levels of self-acceptance. No significant relationships were found between self-acceptance of stuttering and support group participation, emotional support, stuttering severity, and participant age. This exploratory investigation has provided a foundation for future studies on the self-acceptance of stuttering. The findings indicate common psychosocial variables in self-acceptance of stuttering and of other disabilities. The significant relationships between self-acceptance of stuttering and psychosocial and therapeutic variables found need to be further explored to identify its causalities and clinical implications. The reader will be able to (1) discuss the importance of assessing self-acceptance of stuttering, (2) summarize the literature on self-acceptance

  6. Advances in flaw evaluation procedures and acceptance criteria for reactor piping

    International Nuclear Information System (INIS)

    Gamble, R.M.; Zahoor, A.; Norris, D.M.

    1986-01-01

    During the past several years, intergranular stress corrosion cracks (IGSCC) have been detected in stainless steel piping in boiling water reactors (BWRs) and have resulted in an increased number of flaw evaluations. To reduce the outage time associated with evaluating IGSCC, various research and ASME code groups have spent significant effort to provide utility personnel with efficient means to detect, classify, and size flaws, and to determine suitability for return to service for flawed stainless steel piping. One of the several nondestructive evaluation technologies that has received considerable attention is fracture mechanics, the discipline that considers the failure of flawed material. Fracture mechanics can be used to answer two key questions concerning return to service of flawed pipe: (a) what is the largest flaw size that can be returned to service and still maintain adequate safety margins at the applied loads, and (b) how much operating time remains before the crack reaches the largest allowable size? The purpose of this paper is to provide an overview of the recently developed ASME code Section XI flaw size evaluation procedure and acceptance criteria for stainless steel piping and their application by BWR owners to efficiently determine if flaws found by nondestructive examination are acceptable for continued service

  7. Advances in flaw evaluation procedures and acceptance criteria for reactor piping

    Energy Technology Data Exchange (ETDEWEB)

    Gamble, R.M.; Zahoor, A.; Norris, D.M.

    1986-01-01

    During the past several years, intergranular stress corrosion cracks (IGSCC) have been detected in stainless steel piping in boiling water reactors (BWRs) and have resulted in an increased number of flaw evaluations. To reduce the outage time associated with evaluating IGSCC, various research and ASME code groups have spent significant effort to provide utility personnel with efficient means to detect, classify, and size flaws, and to determine suitability for return to service for flawed stainless steel piping. One of the several nondestructive evaluation technologies that has received considerable attention is fracture mechanics, the discipline that considers the failure of flawed material. Fracture mechanics can be used to answer two key questions concerning return to service of flawed pipe: (a) what is the largest flaw size that can be returned to service and still maintain adequate safety margins at the applied loads, and (b) how much operating time remains before the crack reaches the largest allowable size. The purpose of this paper is to provide an overview of the recently developed ASME code Section XI flaw size evaluation procedure and acceptance criteria for stainless steel piping and their application by BWR owners to efficiently determine if flaws found by nondestructive examination are acceptable for continued service.

  8. HOW TO DEAL WITH WASTE ACCEPTANCE UNCERTAINTY USING THE WASTE ACCEPTANCE CRITERIA FORECASTING AND ANALYSIS CAPABILITY SYSTEM (WACFACS)

    Energy Technology Data Exchange (ETDEWEB)

    Redus, K. S.; Hampshire, G. J.; Patterson, J. E.; Perkins, A. B.

    2002-02-25

    The Waste Acceptance Criteria Forecasting and Analysis Capability System (WACFACS) is used to plan for, evaluate, and control the supply of approximately 1.8 million yd3 of low-level radioactive, TSCA, and RCRA hazardous wastes from over 60 environmental restoration projects between FY02 through FY10 to the Oak Ridge Environmental Management Waste Management Facility (EMWMF). WACFACS is a validated decision support tool that propagates uncertainties inherent in site-related contaminant characterization data, disposition volumes during EMWMF operations, and project schedules to quantitatively determine the confidence that risk-based performance standards are met. Trade-offs in schedule, volumes of waste lots, and allowable concentrations of contaminants are performed to optimize project waste disposition, regulatory compliance, and disposal cell management.

  9. HOW TO DEAL WITH WASTE ACCEPTANCE UNCERTAINTY USING THE WASTE ACCEPTANCE CRITERIA FORECASTING AND ANALYSIS CAPABILITY SYSTEM (WACFACS)

    International Nuclear Information System (INIS)

    Redus, K. S.; Hampshire, G. J.; Patterson, J. E.; Perkins, A. B.

    2002-01-01

    The Waste Acceptance Criteria Forecasting and Analysis Capability System (WACFACS) is used to plan for, evaluate, and control the supply of approximately 1.8 million yd3 of low-level radioactive, TSCA, and RCRA hazardous wastes from over 60 environmental restoration projects between FY02 through FY10 to the Oak Ridge Environmental Management Waste Management Facility (EMWMF). WACFACS is a validated decision support tool that propagates uncertainties inherent in site-related contaminant characterization data, disposition volumes during EMWMF operations, and project schedules to quantitatively determine the confidence that risk-based performance standards are met. Trade-offs in schedule, volumes of waste lots, and allowable concentrations of contaminants are performed to optimize project waste disposition, regulatory compliance, and disposal cell management

  10. Nevada test site waste acceptance criteria

    International Nuclear Information System (INIS)

    1996-01-01

    This document provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive and mixed waste for disposal; and transuranic and transuranic mixed waste for interim storage at the NTS. Review each section of this document. This document is not intended to include all of the requirements; rather, it is meant as a guide toward meeting the regulations. All references in this document should be observed to avoid omission of requirements on which acceptance or rejection of waste will be based. The Department of Energy/Nevada Operations Office (DOE/NV) and support contractors are available to assist you in understanding or interpreting this document

  11. Nevada test site waste acceptance criteria

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-09-01

    This document provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive and mixed waste for disposal; and transuranic and transuranic mixed waste for interim storage at the NTS. Review each section of this document. This document is not intended to include all of the requirements; rather, it is meant as a guide toward meeting the regulations. All references in this document should be observed to avoid omission of requirements on which acceptance or rejection of waste will be based. The Department of Energy/Nevada Operations Office (DOE/NV) and support contractors are available to assist you in understanding or interpreting this document.

  12. Derivation of Waste Acceptance Criteria for Low and Intermediate Level Waste in Surface Disposal Facility

    International Nuclear Information System (INIS)

    Gagner, L.; Voinis, S.

    2000-01-01

    In France, low- and intermediate-level radioactive wastes are disposed in a near-surface facility, at Centre de l'Aube disposal facility. This facility, which was commissioned in 1992, has a disposal capacity of one million cubic meters, and will be operated up to about 2050. It took over the job from Centre de la Manche, which was commissioned in 1969 and shut down in 1994, after having received about 520,000 cubic meters of wastes. The Centre de l'Aube disposal facility is designed to receive a many types of waste produced by nuclear power plants, reprocessing, decommissioning, as well as by the industry, hospitals and armed forces. The limitation of radioactive transfer to man and the limitation of personnel exposure in all situations considered plausible require limiting the total activity of the waste disposed in the facility as well as the activity of each package. The paper presents how ANDRA has derived the activity-related acceptance criteria, based on the safety analysis. In the French methodology, activity is considered as end-point for deriving the concentration limits per package, whereas it is the starting point for deriving the total activity limits. For the concentration limits (called here LMA) the approach consists of five steps: the determination of radionuclides important for safety with regards to operational and long-term safety, the use of relevant safety scenarios as a tool to derive quantitative limits, the setting of dose constraint per situation associated with scenarios, the setting of contribution factor per radionuclide, and the calculation of concentration activity limits. An exhaustive survey has been performed and has shown that the totality of waste packages which should be delivered by waste generators are acceptable in terms of activity limits in the Centre de l'Aube. Examples of concentration activity limits derived from this methodology are presented. Furthermore those limits have been accepted by the French regulatory body and

  13. Technical basis for acceptance criteria on the susceptibility of digital systems to electromagnetic interference

    International Nuclear Information System (INIS)

    Ewing, P.D.; Korsah, K.; Antonescu, C.

    1992-01-01

    This paper discusses the development of the technical basis for establishing acceptance criteria on the susceptibility of digital systems to electromagnetic interference (EMI). The effort is sponsored by the US Nuclear Regulatory Commission and stems from the safety-related issues that need to be addressed with the application of digital instrumentation and controls systems in nuclear power plants. Designers of digital circuits are incorporating increasingly higher clock frequencies and lower logic voltage levels, thereby leading to the risk of susceptibility when spurious interference is misinterpreted as legitimate logic. Development of the technical basis for acceptance criteria centers around establishing good engineering practices to ensure that sufficient levels of electromagnetic compatibility (EMC) are maintained between the nuclear power plant's electronic and electromechanical systems. First, good EMC design and installation practices are needed to control the emissions from interference sources and their impact on other nearby circuits and systems. Then, a test and evaluation program is needed to outline the EMI tests to be performed, the associated test methods to be followed, and adequate test limits to ensure that the circuit or system under test meets the recommended guidelines. Test and evaluation should be followed by periodic maintenance to assess whether the recommended EMI control practices continue to be adhered to as part of the routine operation of the nuclear power plant. By following these steps, the probability of encountering safety-related problems associated with EMI will be greatly reduced

  14. RSE-M code progress in the field of examination evaluation and flaw acceptance criteria

    International Nuclear Information System (INIS)

    Barthelet, B.; Le Delliou, P.; Heliot, J.; Faidy, C.; Drubay, B.

    1995-01-01

    The RSE-M Code provides rules and requirements for in service inspection of light water cooled nuclear power plants. The code first edition was established by EDF and published in 1990 by AFCEN. In 1992, a second RSE-M project was launched by EDF and FRAMATOME with the objective to address a 1995 edition more completed considering the needs of owners, users, manufacturers and inspectors. This paper focuses on evaluation of examination results and presents the work done in the field of flaw acceptance criteria over the last three years. (author). 5 refs., 3 figs

  15. A Preliminary Investigation of Acceptance and Commitment Therapy as a Treatment for Marijuana Dependence in Adults

    Science.gov (United States)

    Twohig, Michael P.; Shoenberger, Deacon; Hayes, Steven C.

    2007-01-01

    In this investigation, 3 adults who met criteria for marijuana dependence were treated using an abbreviated version of acceptance and commitment therapy (ACT). The treatment was delivered in eight weekly 90-min individual sessions. The effects of the intervention were assessed using a nonconcurrent multiple baseline across participants design.…

  16. Criteria for safety-related nuclear plant operator actions: a preliminary assessment of available data

    International Nuclear Information System (INIS)

    Haas, P.M.; Bott, T.F.

    1980-01-01

    In the US, an effort has been underway for a number of years to develop a design standard to define when required manual operator action can be accepted as part of a nuclear plant design basis. Insufficient data are available to provide quantitative guidelines for the standard. To provide the necessary data base to support such standards and the necessary quantitative assessment of operator reliability, the US Nuclear Regulatory Commission is sponsoring a study at Oak National Laboratory to develop the data base. A preliminary assessment completed in April, 1979 concluded that sufficient data from US operating experience did not exist to provide an adequate data base. A program of research using full-scope nuclear plant simulators and results that are correlated to field data was suggested. That program was recently initiated. The approach, results and conclusions of the preliminary assessment are reviewed and the planned research program of simulator studies is summarised. (author)

  17. Nevada Test Site Waste Acceptance Criteria

    International Nuclear Information System (INIS)

    U.S. Department of Energy, Nevada Operations Office, Waste Acceptance Criteria

    1999-01-01

    This document provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive and mixed waste for disposal; and transuranic and transuranic mixed waste for interim storage at the Nevada Test Site

  18. Industry Application Emergency Core Cooling System Cladding Acceptance Criteria Early Demonstration

    Energy Technology Data Exchange (ETDEWEB)

    Szilard, Ronaldo H. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Youngblood, Robert W. [FPoliSolutions LLC, Murrysville, PA (United States); Zhang, Hongbin [Idaho National Lab. (INL), Idaho Falls, ID (United States); Zhao, Haihua [Idaho National Lab. (INL), Idaho Falls, ID (United States); Bayless, Paul D. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Rabiti, Cristian [Idaho National Lab. (INL), Idaho Falls, ID (United States); Alfonsi, Andrea [Idaho National Lab. (INL), Idaho Falls, ID (United States); Smith, Curtis L. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Frepoli, Cesare [FPoliSolutions LLC, Murrysville, PA (United States); Yurko, Joseph P. [FPoliSolutions LLC, Murrysville, PA (United States); Swindlehurst, Gregg [GS Nuclear Consulting, Charlotte, NC (United States); Zoino, Angelo [Univ. of Rome Tor Vergata (Italy)

    2015-09-01

    The U. S. NRC is currently proposing rulemaking designated as “10 CFR 50.46c” to revise the loss-of-coolant-accident (LOCA)/emergency core cooling system (ECCS) acceptance criteria to include the effects of higher burnup on cladding performance as well as to address other technical issues. The NRC is also currently resolving the public comments with the final rule expected to be issued in April 2016. The impact of the final 50.46c rule on the industry may involve updating of fuel vendor LOCA evaluation models, NRC review and approval, and licensee submittal of new LOCA evaluations or re-analyses and associated technical specification revisions for NRC review and approval. The rule implementation process, both industry and NRC activities, is expected to take 4-6 years following the rule effective date. As motivated by the new rule, the need to use advanced cladding designs may be a result. A loss of operational margin may result due to the more restrictive cladding embrittlement criteria. Initial and future compliance with the rule may significantly increase vendor workload and licensee cost as a spectrum of fuel rod initial burnup states may need to be analyzed to demonstrate compliance. Consequently, there will be an increased focus on licensee decision making related to LOCA analysis to minimize cost and impact, and to manage margin. The proposed rule would apply to a light water reactor and to all cladding types.

  19. Acceptance criteria for the physical protection upgrade rule requirements for fixed sites. Information guide

    International Nuclear Information System (INIS)

    Dwyer, P.

    1980-09-01

    This document has been developed as a tool to assist in providing consistent evaluation of upgraded physical security plans submitted in response to the Physical Protection Upgrade Rule, effective March 25, 1980. It presents a means for assuring licensee compliance with every regulatory requirement of particular significance to the protection of the public health and safety. Acceptance criteria are included to determine the extent to which each licensee meets the regulatory requirements. The format parallels Regulatory Guide 5.52, Standard Format and Content of a Licensee Physical Protection Plan for Strategic Special Nuclear Material at Fixed Sites

  20. Feasibility, safety, acceptability, and preliminary efficacy of measurement-based care depression treatment for HIV patients in Bamenda, Cameroon.

    Science.gov (United States)

    Pence, Brian W; Gaynes, Bradley N; Atashili, Julius; O'Donnell, Julie K; Kats, Dmitry; Whetten, Kathryn; Njamnshi, Alfred K; Mbu, Tabenyang; Kefie, Charles; Asanji, Shantal; Ndumbe, Peter

    2014-06-01

    Depression affects 18-30 % of HIV-infected patients in Africa and is associated with greater stigma, lower antiretroviral adherence, and faster disease progression. However, the region's health system capacity to effectively identify and treat depression is limited. Task-shifting models may help address this large mental health treatment gap. Measurement-Based Care (MBC) is a task-shifting model in which a Depression Care Manager guides a non-psychiatric (e.g., HIV) provider in prescribing and managing antidepressant treatment. We adapted MBC for depressed HIV-infected patients in Cameroon and completed a pilot study to assess feasibility, safety, acceptability, and preliminary efficacy. We enrolled 55 participants; all started amitriptyline 25-50 mg daily at baseline. By 12 weeks, most remained at 50 mg daily (range 25-125 mg). Median (interquartile range) PHQ-9 depressive severity scores declined from 13 (12-16) (baseline) to 2 (0-3) (week 12); 87 % achieved depression remission (PHQ-9 feasibility, safety, acceptability, and preliminary efficacy in this uncontrolled pilot study. Further research should assess whether MBC could improve adherence and HIV outcomes in this setting.

  1. Radiological control criteria for materials considered for recycle and reuse

    International Nuclear Information System (INIS)

    Kennedy, W.E. Jr.; Hill, R.L.; Aaberg, R.L.; Wallo, A. III

    1994-11-01

    Pacific Northwest Laboratory (PNL) is conducting technical analyses to support the US Department of Energy (DOE), Office of Environmental Guidance, Air, Water, and Radiation Division (DOE/EH-232) in developing radiological control criteria for recycling or reuse of metals or equipment containing residual radioactive contamination from DOE operations. The criteria, framed as acceptable concentrations for release of materials for recycling or reuse, are risk-based and were developed through analysis of generic radiation exposure scenarios and pathways. The analysis includes evaluation of relevant radionuclides, potential mechanisms of exposure, and non-health-related impacts of residual radioactivity on electronics and film. The analysis considers 42 key radionuclides that DOE operations are known to generate and that may be contained in recycled or reused metals or equipment. Preliminary results are compared with similar results reported by the International Atomic Energy Agency, by radionuclide grouping

  2. Waste Feed Delivery System Phase 1 Preliminary RAM Analysis

    International Nuclear Information System (INIS)

    DYKES, A.A.

    2000-01-01

    This report presents the updated results of the preliminary reliability, availability, and maintainability (RAM) analysis of selected waste feed delivery (WFD) operations to be performed by the Tank Farm Contractor (TFC) during Phase I activities in support of the Waste Treatment and Immobilization Plant (WTP). For planning purposes, waste feed tanks are being divided into five classes in accordance with the type of waste in each tank and the activities required to retrieve, qualify, and transfer waste feed. This report reflects the baseline design and operating concept, as of the beginning of Fiscal Year 2000, for the delivery of feed from three of these classes, represented by source tanks 241-AN-102, 241-AZ-101 and 241-AN-105. The preliminary RAM analysis quantifies the potential schedule delay associated with operations and maintenance (OBM) field activities needed to accomplish these operations. The RAM analysis is preliminary because the system design, process definition, and activity planning are in a state of evolution. The results are being used to support the continuing development of an O and M Concept tailored to the unique requirements of the WFD Program, which is being documented in various volumes of the Waste Feed Delivery Technical Basis (Carlson. 1999, Rasmussen 1999, and Orme 2000). The waste feed provided to the WTP must: (1) meet limits for chemical and radioactive constituents based on pre-established compositional envelopes (i.e., feed quality); (2) be in acceptable quantities within a prescribed sequence to meet feed quantities; and (3) meet schedule requirements (i.e., feed timing). In the absence of new criteria related to acceptable schedule performance due to the termination of the TWRS Privatization Contract, the original criteria from the Tank Waste Remediation System (77443s) Privatization Contract (DOE 1998) will continue to be used for this analysis

  3. Criteria for safety related nuclear plant operator actions: a preliminary assessment of available data

    International Nuclear Information System (INIS)

    Haas, P.M.; Bott, T.F.

    1982-01-01

    The need for a quantitative data base on the reliability of nuclear power plant operators has long been recognised by human factors and reliability analysts, and the great need for further assessment of operator performance under accident conditions has been dramatically emphasised by the incident at Three Mile Island-2. In the US, an effort has been under way for a number of years to develop a design standard to define when required manual operator action can be accepted as part of a nuclear plant design basis. To provide the necessary data base to support such standards and the necessary quantitative assessment of operator reliability, the US Nuclear Regulatory Commission is sponsoring a study at Oak Ridge National Laboratory to develop the data base. A preliminary assessment, completed in April 1979, concluded that sufficient data from US operating experience did not exist to provide an adequate data base. A programme of research using full-scope nuclear plant simulators and results that are correlated to field data was suggested. That programme was recently initiated. This paper reviews the approach, results and conclusions of the preliminary assessment and summarises the planned research programme of simulator studies. (author)

  4. A Preliminary Investigation of Acceptance and Commitment Therapy as a Treatment for Marijuana Dependence in Adults

    OpenAIRE

    Twohig, Michael P; Shoenberger, Deacon; Hayes, Steven C

    2007-01-01

    In this investigation, 3 adults who met criteria for marijuana dependence were treated using an abbreviated version of acceptance and commitment therapy (ACT). The treatment was delivered in eight weekly 90-min individual sessions. The effects of the intervention were assessed using a nonconcurrent multiple baseline across participants design. Self-reported marijuana use, confirmed through oral swabs, reached zero levels for all participants at posttreatment. At a 3-month follow-up, 1 partici...

  5. Radiological control criteria for materials considered for recycle and reuse

    International Nuclear Information System (INIS)

    Kennedy, W.E. Jr.; Hill, R.L.; Aaberg, R.L.; Wallo, A. III.

    1995-01-01

    Pacific Northwest Laboratory (PNL) is conducting technical analyses to support the U.S. Department of Energy (DOE), Office of Environmental Guidance, Air, Water, and Radiation Division (DOE/EH-232) in developing radiological control criteria for recycling or reuse of metals or equipment containing residual radioactive contamination from DOE operations. The criteria, framed as acceptable concentrations for release of materials for recycling or reuse, are risk-based and were developed through analysis of generic radiation exposure scenarios and pathways. The analysis includes evaluation of relevant radionuclides, potential mechanisms of exposure, and non-health-related impacts of residual radioactivity on electronics and film. The analysis considers 42 key radionuclides that DOE operations are known to generate and that may be contained in recycled or reused metals or equipment. The preliminary results are compared with similar results reported by the International Atomic Energy Agency, by radionuclide grouping. (author)

  6. Early response to sibutramine in patients not meeting current label criteria: preliminary analysis of SCOUT lead-in period

    DEFF Research Database (Denmark)

    Caterson, Ian; Coutinho, Walmir; Finer, Nick

    2010-01-01

    The Sibutramine Cardiovascular Outcomes (SCOUT) trial protocol defines a patient population predominantly outside current European Union label criteria. This article explores responses to sibutramine during the 6-week, single-blind, lead-in period between patients who conformed to the label...... requirements ("conformers") and those who did not ("nonconformers"). SCOUT is an ongoing, randomized, double-blind, placebo-controlled outcome trial in overweight/obese patients at high risk of a cardiovascular event. In total, 10,742 patients received sibutramine and weight management during the lead...... with sibutramine confirms its good tolerability and efficacy in patients who meet current label criteria. Preliminary data from high-risk patients for whom sibutramine is currently contraindicated suggest a low discontinuation rate and few serious adverse events but confirmation from the SCOUT outcome data...

  7. Data Quality Objectives for WTP Feed Acceptance Criteria - 12043

    Energy Technology Data Exchange (ETDEWEB)

    Arakali, Aruna V.; Benson, Peter A.; Duncan, Garth; Johnston, Jill C.; Lane, Thomas A.; Matis, George; Olson, John W. [Hanford Tank Waste Treatment and Immobilization Plant (United States); Banning, Davey L.; Greer, Daniel A.; Seidel, Cary M.; Thien, Michael G. [Hanford Tank Operations Contractor - Washington River Protection Solutions, Richland, WA 99354 (United States)

    2012-07-01

    The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is under construction for the U.S. Department of Energy by Bechtel National, Inc. and subcontractor URS Corporation (contract no. DE-AC27-01RV14136). The plant when completed will be the world's largest nuclear waste treatment facility. Bechtel and URS are tasked with designing, constructing, commissioning, and transitioning the plant to the long term operating contractor to process the legacy wastes that are stored in underground tanks (from nuclear weapons production between the 1940's and the 1980's). Approximately 56 million gallons of radioactive waste is currently stored in these tanks at the Hanford Site in southeastern Washington. There are three major WTP facilities being constructed for processing the tank waste feed. The Pretreatment (PT) facility receives feed where it is separated into a low activity waste (LAW) fraction and a high level waste (HLW) fraction. These fractions are transferred to the appropriate (HLW or LAW) facility, combined with glass former material, and sent to high temperature melters for formation of the glass product. In addition to PT, HLW and LAW, other facilities in WTP include the Laboratory (LAB) for analytical services and the Balance of Facilities (BOF) for plant maintenance, support and utility services. The transfer of staged feed from the waste storage tanks and acceptance in WTP receipt vessels require data for waste acceptance criteria (WAC) parameters from analysis of feed samples. The Data Quality Objectives (DQO) development was a joint team effort between WTP and Tank Operations Contractor (TOC) representatives. The focus of this DQO effort was to review WAC parameters and develop data quality requirements, the results of which will determine whether or not the staged feed can be transferred from the TOC to WTP receipt vessels. The approach involved systematic planning for data collection consistent with EPA guidance for the seven

  8. Towards the development of workable acceptance criteria for the divertor CFC monoblock armour

    Energy Technology Data Exchange (ETDEWEB)

    D' Agata, E. [ITER International Team, ITER Joint Work Site, Boltzmannstr. 2, D-85748 Garching (Germany)]. E-mail: dagatae@itereu.de; Tivey, R. [ITER International Team, ITER Joint Work Site, Boltzmannstr. 2, D-85748 Garching (Germany)

    2005-11-15

    The plasma-facing components (PFCs) of the ITER divertor will be subjected to high heat flux (HHF). Carbon-fibre composite (CFC) is selected as the armour for the region of highest heat flux where the scrape-off layer of the plasma intercepts the vertical targets (VT). Failure of the armour to heat sink joints will compromise the performance of the divertor and could ultimately result in its failure and the shut down of the ITER machine. There are tens of thousands of CFCs to CuCrZr joints. The aim of the PFC design is to ensure that the divertor can continue to function even with the failure of a few joints. In preparation for writing the procurement specification for the ITER vertical target PFCs, a programme of work is underway with the objective of defining workable acceptance criteria for the PFC armour joints.

  9. Towards the development of workable acceptance criteria for the divertor CFC monoblock armour

    International Nuclear Information System (INIS)

    D'Agata, E.; Tivey, R.

    2005-01-01

    The plasma-facing components (PFCs) of the ITER divertor will be subjected to high heat flux (HHF). Carbon-fibre composite (CFC) is selected as the armour for the region of highest heat flux where the scrape-off layer of the plasma intercepts the vertical targets (VT). Failure of the armour to heat sink joints will compromise the performance of the divertor and could ultimately result in its failure and the shut down of the ITER machine. There are tens of thousands of CFCs to CuCrZr joints. The aim of the PFC design is to ensure that the divertor can continue to function even with the failure of a few joints. In preparation for writing the procurement specification for the ITER vertical target PFCs, a programme of work is underway with the objective of defining workable acceptance criteria for the PFC armour joints

  10. Selecting the Acceptance Criteria of Medicines in the Reimbursement List of Public Health Insurance of Iran, Using the "Borda" Method: a Pilot Study.

    Science.gov (United States)

    Viyanchi, Amir; Rasekh, Hamid Reza; Rajabzadeh Ghatari, Ali; SafiKhani, Hamid Reza

    2015-01-01

    Decision-making for medicines to be accepted in Iran's public health insurance reimbursement list is a complex process and involves factors, which should be considered in applying a coverage for medicine costs. These processes and factors are not wholly assessed, while assessment of these factors is an essential need for getting a transparent and evidence-based approach toward medicine reimbursement in Iran. This paper aims to show an evidence-based approach toward medicine selection criteria to inform the medical reimbursement decision makers in Iranian health insurance organizations. To explore an adaptable decision-making framework while incorporating a method called "Borda" in medicine reimbursement assessment, we used the help of an expert group including decision makers and clinical researchers who are also policy makers to appraise the five chief criteria that have three sub criteria (Precision, Interpretability, and Cost). Also software "Math-lab"7, "SPSS" 17 and Excel 2007 were used in this study. "Borda" estimates the amount of perceived values from different criteria and creates a range from one to five while providing a comprehensive measurement of a large spectrum of criteria. Participants reported that the framework provided an efficient approach to systematic consideration in a pragmatic format consisting of many parts to guide decision-makings, including criteria and value (a model with the core of Borda) and evidences (medicine reimbursement based on criteria). The most important criterion for medicine acceptance in health insurance companies, in Iran, is the "life-threatening" factor and "evidence quality" is accounted as the fifth important factor. This pilot study showed the usefulness of incorporating Borda in medicine reimbursement decisions to support a transparent and systematic appraisal of health insurance companies' deeds. Further research is needed to advance Borda-based approaches that are effective on health insurance decision making.

  11. Preliminary Evaluation Methodology of ECCS Performance for Design Basis LOCA Redefinition

    International Nuclear Information System (INIS)

    Kang, Dong Gu; Ahn, Seung Hoon; Seul, Kwang Won

    2010-01-01

    To improve their existing regulations, the USNRC has made efforts to develop the risk-informed and performance-based regulation (RIPBR) approaches. As a part of these efforts, the rule revision of 10CFR50.46 (ECCS Acceptance Criteria) is underway, considering some options for 4 categories of spectrum of break sizes, ECCS functional reliability, ECCS evaluation model, and ECCS acceptance criteria. Since the potential for safety benefits and unnecessary burden reduction from design basis LOCA redefinition is high relative to other options, the USNRC is proceeding with the rulemaking for design basis LOCA redefinition. An instantaneous break with a flow rate equivalent to a double ended guillotine break (DEGB) of the largest primary piping system in the plant is widely recognized as an extremely unlikely event, while redefinition of design basis LOCA can affect the existing regulatory practices and approaches. In this study, the status of the design basis LOCA redefinition and OECD/NEA SMAP (Safety Margin Action Plan) methodology are introduced. Preliminary evaluation methodology of ECCS performance for LOCA is developed and discussed for design basis LOCA redefinition

  12. Processing of Irradiated Graphite to Meet Acceptance Criteria for Waste Disposal. Results of a Coordinated Research Project

    International Nuclear Information System (INIS)

    2016-05-01

    Graphite is widely used in the nuclear industry and in research facilities and this has led to increasing amounts of irradiated graphite residing in temporary storage facilities pending disposal. This publication arises from a coordinated research project (CRP) on the processing of irradiated graphite to meet acceptance criteria for waste disposal. It presents the findings of the CRP, the general conclusions and recommendations. The topics covered include, graphite management issues, characterization of irradiated graphite, processing and treatment, immobilization and disposal. Included on the attached CD-ROM are formal reports from the participants

  13. Preliminary Disposal Analysis for Selected Accelerator Production of Tritium Waste Streams

    International Nuclear Information System (INIS)

    Ades, M.J.; England, J.L.

    1998-06-01

    A preliminary analysis was performed for two selected Accelerator Production of Tritium (APT) generated mixed and low-level waste streams to determine if one mixed low-level waste (MLLW) stream that includes the Mixed Waste Lead (MWL) can be disposed of at the Nevada Test Site (NTS) and at the Hanford Site and if one low-level radioactive waste (LLW) stream, that includes the Tungsten waste stream (TWS) generated by the Tungsten Neutron Source modules and used in the Target/Blanket cavity vessel, can be disposed of in the LLW Vaults at the Savannah River Plant (SRP). The preliminary disposal analysis that the radionuclide concentrations of the two selected APT waste streams are not in full compliance with the Waste Acceptance Criteria (WAC) and the Performance Assessment (PA) radionuclide limits of the disposal sites considered

  14. Radiation protection criteria in the long-range view

    International Nuclear Information System (INIS)

    Snihs, J.O.; Bergman, C.

    1989-01-01

    The report presents by way of introduction radiation protection criteria applied to radiological activities and to disposal of low-level and intermediate-level radioactive waste. In these cases it is primarily short-range views that are relevant, up to a few thousand years as a maximum. In the case of high-level wastes where the views may extend to more than hundreds of thousands years, there are not for the present any equally well stablished criteria. Based upon preliminary results from a Nordic team for criteria for high-level radioactive wastes, dose estimates in the long-range view and alternative assessment criteria are discussed. Proposals are also presented for 12 criteria that may be applicable. As the work is not yet finshed, the criteria are however merely preliminary

  15. Nevada Test Site waste acceptance criteria [Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    None

    1997-08-01

    Revision one updates the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive and mixed waste for disposal; and transuranic and transuranic mixed waste for interim storage at the NTS. Review each section of this document. This document is not intended to include all of the requirements; rather, it is meant as a guide toward meeting the regulations. All references in this document should be observed to avoid omission of requirements on which acceptance or rejection of waste will be based. The Department of Energy/Nevada Operations Office (DOE/NV) and support contractors are available to assist you in understanding or interpreting this document.

  16. Nevada Test Site waste acceptance criteria [Revision 1

    International Nuclear Information System (INIS)

    None

    1997-01-01

    Revision one updates the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive and mixed waste for disposal; and transuranic and transuranic mixed waste for interim storage at the NTS. Review each section of this document. This document is not intended to include all of the requirements; rather, it is meant as a guide toward meeting the regulations. All references in this document should be observed to avoid omission of requirements on which acceptance or rejection of waste will be based. The Department of Energy/Nevada Operations Office (DOE/NV) and support contractors are available to assist you in understanding or interpreting this document

  17. Derivation of quantitative acceptance criteria for disposal of radioactive waste to near surface facilities: Development and implementation of an approach for the post-closure phase

    International Nuclear Information System (INIS)

    Torres, C.

    2000-01-01

    The International Atomic Energy Agency has established a project to develop and illustrate, through practical examples, an approach that allows the derivation of quantitative waste acceptance criteria for near surface disposal of radioactive waste. The first phase focussed on the derivation of example post-closure safety waste acceptance criteria through the use of a safety assessment approach that allows for the derivation of values in a clear and well documented manner. The approach consists of five steps: the specification of the assessment context; the description of the disposal system; the development and justification of scenarios; the formulation and implementation of models; and the calculation and derivation of example values. The approach has been successfully used to derive activity values for the disposal of radioactive waste to illustrative near surface facilities. (author)

  18. Acceptance criteria considerations for miscellaneous wastes

    International Nuclear Information System (INIS)

    Irvine, A.R.; Forsberg, C.W.

    1987-01-01

    EPA standards set forth limitations regarding releases to the accessible environment adjacent to a geologic repository. The NRC criteria pertaining to waste form and engineered barrier performance place certain restrictions on the physical and chemical nature of the waste form and require substantially complete confinement of radioactivity until the high-heat-production period is past. After this period, the annual release of radionuclides from the waste package is normally limited to 1 part in 100,000 of the amounts calculated to be present at 1000-y decay. The regulation permits deviation from these criteria in exceptional circumstances. One such circumstance might be the absence of a significant perturbation in temperature around the stored waste. The lack of significant heat release will eliminate the hydrologic driving force for dispersal of radionuclides. Exceptional circumstances which potentially could justify a less stringent long-term release criterion are: small quantity of radioactivity, the nature of the radioactive species, and the nature of the geology in which the waste is to be emplaced. Because the MW after a suitable decay period have low heat release rates per unit volume, they apparently could be so emplaced in a repository that there would be no compelling need, according to the reasoning presented in 10 CFR 60, for a 1000-y container. Regarding attainment of the specified long-term release rate criterion, neither the solubility limits for the various waste forms nor the conductance of potential migration barriers are currently adequately characterized. The relatively small total heat generation rate for the MW in combination with the usual low volumetric heat generation rate apparently will allow application of migration barriers in a low temperature environment where barrier performance would be expected to be unchanged with time

  19. Waste Feed Delivery System Phase 1 Preliminary RAM Analysis [SEC 1 and 2

    Energy Technology Data Exchange (ETDEWEB)

    DYKES, A.A.

    2000-10-11

    This report presents the updated results of the preliminary reliability, availability, and maintainability (RAM) analysis of selected waste feed delivery (WFD) operations to be performed by the Tank Farm Contractor (TFC) during Phase I activities in support of the Waste Treatment and Immobilization Plant (WTP). For planning purposes, waste feed tanks are being divided into five classes in accordance with the type of waste in each tank and the activities required to retrieve, qualify, and transfer waste feed. This report reflects the baseline design and operating concept, as of the beginning of Fiscal Year 2000, for the delivery of feed from three of these classes, represented by source tanks 241-AN-102, 241-AZ-101 and 241-AN-105. The preliminary RAM analysis quantifies the potential schedule delay associated with operations and maintenance (OBM) field activities needed to accomplish these operations. The RAM analysis is preliminary because the system design, process definition, and activity planning are in a state of evolution. The results are being used to support the continuing development of an O&M Concept tailored to the unique requirements of the WFD Program, which is being documented in various volumes of the Waste Feed Delivery Technical Basis (Carlson. 1999, Rasmussen 1999, and Orme 2000). The waste feed provided to the WTP must: (1) meet limits for chemical and radioactive constituents based on pre-established compositional envelopes (i.e., feed quality); (2) be in acceptable quantities within a prescribed sequence to meet feed quantities; and (3) meet schedule requirements (i.e., feed timing). In the absence of new criteria related to acceptable schedule performance due to the termination of the TWRS Privatization Contract, the original criteria from the Tank Waste Remediation System (77443s) Privatization Contract (DOE 1998) will continue to be used for this analysis.

  20. Recommendations for Glass Durability Test Criteria

    International Nuclear Information System (INIS)

    Strachan, D.M.

    1999-01-01

    The objective of this short report is to define a set of activities that should lead to a specification for a test that can be used as one of the acceptance criteria and as an indicator of acceptable long-term behavior in contact with water. Since the glass composition is not yet defined and is likely to change as the composition of the waste changes, a strategy for developing criteria for what is acceptable involves a series of tests and modeling activities. The results of these activities lead to a criterion for an acceptable product and the data that are needed to reliably determine the behavior of the glass in the storage environment

  1. DOE natural phenomenal hazards design and evaluation criteria

    International Nuclear Information System (INIS)

    Murray, R.C.; Nelson, T.A.; Short, S.A.; Kennedy, R.P.; Chander, H.; Hill, J.R.; Kimball, J.K.

    1994-10-01

    It is the policy of the Department of Energy (DOE) to design, construct, and operate DOE facilities so that workers, the general public, and the environment are protected from the impacts of natural phenomena hazards (NPH). Furthermore, DOE has established explicit goals of acceptable risk for NPH performance. As a result, natural phenomena hazard (earthquake, extreme wind, and flood) design and evaluation criteria for DOE facilities have been developed based on target probabilistic performance goals. These criteria include selection of design/evaluation NPH input from probabilistic hazard curves combined with commonly practiced deterministic response evaluation methods and acceptance criteria with controlled levels of conservatism. For earthquake considerations, conservatism is intentionally introduced in specification of material strengths and capacities, in the allowance of limited inelastic behavior, and by a seismic scale factor. Criteria have been developed following a graded approach for several performance goals ranging from that appropriate for normal-use facilities to that appropriate for facilities involving hazardous or critical operations. Performance goals are comprised of qualitative expressions of acceptable behavior and of target quantitative probabilities that acceptable limits of behavior are maintained. The criteria are simple procedures but have a rigorous basis. This paper addresses DOE seismic design and evaluation criteria

  2. Acceptance criteria for non-destructive examination of double-shell tanks

    International Nuclear Information System (INIS)

    Jensen, C.E.

    1995-09-01

    This supporting document provides requirements for acceptance of relevant indications found during non-destructive examination of double-shell tanks (DSTs) at Hanford 200 areas. Requirements for evaluation of relevant indications are provided to determine acceptability of continued safe operation of the DSTs. Areas of the DSTs considered include the tank wall vapor space, liquid-vapor interface, wetted tank wall, sludge-liquid interface, and the knuckle region

  3. Ammunition Peculiar Equipment (APE) 1995, NIR Propellant Analyzer, to MIL-STD-398, Military Standard Shields, Operational for Ammunition Operations, Criteria for Design of and Tests for Acceptance

    National Research Council Canada - National Science Library

    2003-01-01

    ... (SJMAC-DEM) to test the Ammunition Peculiar Equipment (APE) 1995 NIR Propellant Analyzer, to MIL-STD-398, "Military Standard Shields, Operational for Ammunition Operations, Criteria for Design of and Tests for Acceptance...

  4. Preliminary Acceptance Criteria for Safety Analysis of KALIMER-600 SFR

    International Nuclear Information System (INIS)

    Kwon, Young Min; Lee, Kwi Lim; Ha, Kwi Seok; Chang, Won Pyo; Jeong, Hae Yong

    2010-01-01

    The KALIMER-600 event categorization in the function of occurrence frequency has been made by traditional engineering judgment with information from some reference plants such as CRBR, PRISM and EFR. The dividing line between DBE and BDBE is the frequency of 10 -7 per plant-year. Each event belongs to one of five categories based upon its nominal frequency per reactor-year (f) as a criterion. (1) Moderate frequency Event (MF): f ≥ 10 -1 (2) Infrequent Event (IE): 10 -1 > f ≥ 10 -2 (3) Unlikely Event (UE): 10 -2 > f ≥ 10 -4 (4) Extremely Unlikely Event (XU): 10 -4 > f ≥ 10 -7 (5) Beyond DBE (BDBE): > f ≥ 10 -4

  5. Acceptance Probability (P a) Analysis for Process Validation Lifecycle Stages.

    Science.gov (United States)

    Alsmeyer, Daniel; Pazhayattil, Ajay; Chen, Shu; Munaretto, Francesco; Hye, Maksuda; Sanghvi, Pradeep

    2016-04-01

    This paper introduces an innovative statistical approach towards understanding how variation impacts the acceptance criteria of quality attributes. Because of more complex stage-wise acceptance criteria, traditional process capability measures are inadequate for general application in the pharmaceutical industry. The probability of acceptance concept provides a clear measure, derived from specific acceptance criteria for each quality attribute. In line with the 2011 FDA Guidance, this approach systematically evaluates data and scientifically establishes evidence that a process is capable of consistently delivering quality product. The probability of acceptance provides a direct and readily understandable indication of product risk. As with traditional capability indices, the acceptance probability approach assumes that underlying data distributions are normal. The computational solutions for dosage uniformity and dissolution acceptance criteria are readily applicable. For dosage uniformity, the expected AV range may be determined using the s lo and s hi values along with the worst case estimates of the mean. This approach permits a risk-based assessment of future batch performance of the critical quality attributes. The concept is also readily applicable to sterile/non sterile liquid dose products. Quality attributes such as deliverable volume and assay per spray have stage-wise acceptance that can be converted into an acceptance probability. Accepted statistical guidelines indicate processes with C pk > 1.33 as performing well within statistical control and those with C pk  1.33 is associated with a centered process that will statistically produce less than 63 defective units per million. This is equivalent to an acceptance probability of >99.99%.

  6. Preliminary study on the establishment of the radionuclide declaration methods for radionuclides in LILW radioactive waste

    International Nuclear Information System (INIS)

    Hwang, K. H.; Lee, K. J.; Jung, C. W.

    2003-01-01

    The preliminary study on declaration methods has been done for each radionuclide in LILW radwaste drum in Korean NPPs. View from the preliminary establishment of radio nuclide declaration methods, The selection of assessment target nuclide through the qualitative method and preliminary criteria for routine declaration methods in each radio nuclide was derived. First of all, selection criteria and preliminary assessment method for each target radionuclide was surveyed and investigated. And, the selection criteria and selected the target radio nuclides from the basis on criteria was derived. And the preliminary suggestion about the declaration methods for each target radio nuclide was established

  7. Development of comprehensive waste acceptance criteria for commercial nuclear waste

    International Nuclear Information System (INIS)

    O'Hara, F.A.; Miller, N.E.; Ausmus, B.S.; Yates, K.R.; Means, J.L.; Christensen, R.N.; Kulacki, F.A.

    1979-01-01

    A detailed methodology is presented for the identification of the characteristics of commercial nuclear waste which may require criteria. This methodology is analyzed as a six-step process which begins with identification of waste operations and proceeds until the waste characteristics affecting the potential release of radionuclides are determined. All waste types and operations were analyzed using the methodology presented. Several illustrative example are included. It is found that thirty-three characteristics can be identified as possibly requiring criteria

  8. Social aspects of the nuclear energy. Public acceptance. Preliminary

    International Nuclear Information System (INIS)

    1992-06-01

    This report approaches the social aspects of the nuclear energy an public acceptance. It presents the following main topics: historical of the public opposition to the nuclear energy; emergency planning; legislation related to the popular participation; best strategies to acceptance; insurance of nuclear risks; protection of the population and the environment in the licensing; and organization of the licensing system

  9. Are regulation-driven performance criteria still acceptable? - The German point of view.

    Science.gov (United States)

    Orth, Matthias

    2015-05-01

    Performance criteria should be a challenge for the laboratories to improve their quality. In countries with mandatory proficiency testing, the definition of performance criteria is a particular issue. If the definition of performance criteria is mandated from the regulatory bodies to medico-scientific institutions, scientific approaches (i.e., based on biological variation), the state-of-the-art approach (i.e., based on technical feasibility) as well as medical needs can be used to set up performance criteria such as the Richtlinie der Bundesärztekammer (RiliBÄK; Guideline of the German Medical Association on Quality Assurance in Medical Laboratory Examinations) in Germany. The experiences with RiliBÄK show that these performance criteria have to be revised on an ongoing basis.

  10. Sustainability and acceptance - new challenges for nuclear energy

    International Nuclear Information System (INIS)

    Lensa, W. von

    2001-01-01

    This paper discusses the concept of sustainability in relation to acceptance of nuclear energy. Acceptance is viewed in terms of public acceptance, industrial acceptance, and internal acceptance/consensus within the nuclear community. It addresses sustainability criteria, the need for innovation, and the different levels of acceptability. The mechanisms of risk perception are discussed along with the technological consequences from risk perception mechanisms leading to specific objections against nuclear energy. (author)

  11. Development of threshold action criteria for light water reactors

    International Nuclear Information System (INIS)

    Okrent, D.; Baldewicz, W.L.

    1982-06-01

    A survey of recently threshold criteria for regulatory action on LWRs is presented together with some commentary. This is followed by a new proposal for threshold action criteria which includes some different risk attributes than are found in previous criteria. Some preliminary risk values are suggested for the criteria and then evaluated in terms of a few hypothetical accident scenarios. Finally, several licensing issues are examined in terms of various threshold action criteria

  12. Scale and the acceptability of nuclear energy

    International Nuclear Information System (INIS)

    Wilbanks, T.J.

    1984-01-01

    A rather speculative exploration is presented of scale as it may affect the acceptability of nuclear energy. In our utilization of this energy option, how does large vs. small relate to attitudes toward it, and what can we learn from this about technology choices in the United States more generally. In order to address such a question, several stepping-stones are needed. First, scale is defined for the purposes of the paper. Second, recent experience with nuclear energy is reviewed: trends in the scale of use, the current status of nuclear energy as an option, and the social context for its acceptance problems. Third, conventional notions about the importance of scale in electricity generation are summarized. With these preliminaries out of the way, the paper then discusses apparent relationships between scale and the acceptance of nuclear energy and suggests some policy implications of these preliminary findings. Finally, some comments are offered about general relationships between scale and technology choice

  13. Processing of Irradiated Graphite to Meet Acceptance Criteria for Waste Disposal. Results of a Coordinated Research Project. Companion CD-ROM

    International Nuclear Information System (INIS)

    2016-05-01

    Graphite is widely used in the nuclear industry and in research facilities and this has led to increasing amounts of irradiated graphite residing in temporary storage facilities pending disposal. This publication arises from a coordinated research project (CRP) on the processing of irradiated graphite to meet acceptance criteria for waste disposal. It presents the findings of the CRP, the general conclusions and recommendations. The topics covered include, graphite management issues, characterization of irradiated graphite, processing and treatment, immobilization and disposal. Included on the attached CD-ROM are formal reports from the participants

  14. Electricity supply between acceptance, acceptability and social compatibility; Energieversorgung zwischen Akzeptanz, Akzeptabilitaet und Sozialvertraeglichkeit

    Energy Technology Data Exchange (ETDEWEB)

    Schubert, Katharina; Koch, Marco K. [Bochum Univ. (Germany). Lehrstuhl Energiesysteme und Energiewirtschaft (LEE)

    2012-11-01

    Acceptance promotion is supposed to be an indispensable premise for a successful realization of an energy concept. The contribution identifies deficiencies of the energy policy, including intransparency, complexity of decision procedures, for instance in case of the so called energy transmission line extension acceleration law, that has caused irritation and anger in the public. The justification of acceptance promotion is questioned in connection with the German nuclear policy reversal following the Fukushima accident. A research program ''public acceptance of large-scale power plants for electricity generation'' is presented. The issues criteria and limits of acceptability are of main importance for this discussion.

  15. Hanford Waste Vitrification Plant: Preliminary description of waste form and canister

    International Nuclear Information System (INIS)

    Mitchell, D.E.

    1986-01-01

    In July 1985, the US Department of Energy's Office of Civilian Radioactive Waste Management established the Waste Acceptance Process as the means by which defense high-level waste producers, such as the Hanford Waste Vitrification Plant, will develop waste acceptance requirements with the candidate geologic repositories. A complete description of the Waste Acceptance Process is contained in the Preliminary Hanford Waste Vitrification Plant Waste Form Qualification Plan. The Waste Acceptance Process defines three documents that high-level waste producers must prepare as a part of the process of assuming that a high-level waste product will be acceptable for disposal in a geologic repository. These documents are the Description of Waste Form and Canister, Waste Compliance Plan, and Waste Qualification Report. This document is the Hanford Waste Vitrification Plant Preliminary Description of Waste Form and Canister for disposal of Neutralized Current Acid Waste. The Waste Acceptance Specifications for the Hanford Waste Vitrification Plant have not yet been developed, therefore, this document has been structured to corresponds to the Waste Acceptance Preliminary Specifications for the Defense Waste Processing Facility High-Level Waste Form. Not all of the information required by these specifications is appropriate for inclusion in this Preliminary Description of Waste Form and Canister. Rather, this description is limited to information that describes the physical and chemical characteristics of the expected high-level waste form. The content of the document covers three major areas: waste form characteristics, canister characteristics, and canistered waste form characteristics. This information will be used by the candidate geologic repository projects as the basis for preliminary repository design activities and waste form testing. Periodic revisions are expected as the Waste Acceptance Process progresses

  16. From waste packages acceptance criteria to waste packages acceptance process at the Centre de l'Aube disposal facility

    International Nuclear Information System (INIS)

    Dutzer, M.

    2003-01-01

    The Centre de l'Aube disposal facility has now been operated for 10 years. At the end of 2001, about 124,000 m3 of low and intermediate level short lived waste packages, representing 180,000 packages, have been disposed, for a total capacity of 1,000,000 m3. The flow of waste packages is now between 12 and 15,000 m3 per year, that is one third of the flow that was taken into account for the design of the repository. It confirms the efforts by waste generators to minimise waste production. This flow represents 25 to 30,000 packages, 50% are conditioned into the compaction facility of the repository, so that 17,000 packages are disposed per year. 54 disposal vaults have been closed. In 1996-1999, the safety assessment of the repository have been reviewed, taking into account the experience of operation. This assessment was investigated by the regulatory body and, subsequently, a so-called 'definitive license' to operate was granted to ANDRA on September 2, 1999 with updated licensing requirements. Another review will be performed in 2004. To ensure a better consistency with the safety assessment of the facility, Andra issued new technical requirements for waste packages at the end of 2000. Discussions with waste generators also showed that the waste package acceptance process should be improved to provide a more precise definition of operational criteria to comply with in waste conditioning facilities. Consequently, a new approach has been implemented since 2000. (orig.)

  17. Safety criteria for nuclear chemical plants

    International Nuclear Information System (INIS)

    Ball, P.W.; Curtis, L.M.

    1983-01-01

    Safety measures have always been required to limit the hazards due to accidental release of radioactive substances from nuclear power plants and chemical plants. The risk associated with the discharge of radioactive substances during normal operation has also to be kept acceptably low. BNFL (British Nuclear Fuels Ltd.) are developing risk criteria as targets for safe plant design and operation. The numerical values derived are compared with these criteria to see if plants are 'acceptably safe'. However, the criteria are not mandatory and may be exceeded if this can be justified. The risk assessments are subject to independent review and audit. The Nuclear Installations Inspectorate also has to pass the plants as safe. The assessment principles it uses are stated. The development of risk criteria for a multiplant site (nuclear chemical plants tend to be sited with many others which are related functionally) is discussed. This covers individual members of the general public, societal risks, risks to the workforce and external hazards. (U.K.)

  18. Acceptance test procedure for Project W-280

    International Nuclear Information System (INIS)

    Stites, C.G.

    1994-01-01

    This Document is the Acceptance Test Procedure for 200 Area C and SY Tank Farm Lighting Upgrade. This Acceptance Test Procedure has been prepared to demonstrate that the Tank Farm Lighting Systems function correctly as required by project criteria and as intended by design

  19. Simplified probabilistic approach to determine safety factors in deterministic flaw acceptance criteria

    International Nuclear Information System (INIS)

    Barthelet, B.; Ardillon, E.

    1997-01-01

    The flaw acceptance rules in nuclear components rely on deterministic criteria supposed to ensure the safe operating of plants. The interest of having a reliable method of evaluating the safety margins and the integrity of components led Electricite de France to launch a study to link safety factors with requested reliability. A simplified analytical probabilistic approach is developed to analyse the failure risk in Fracture Mechanics. Assuming lognormal distributions of the main random variables, it is possible considering a simple Linear Elastic Fracture Mechanics model, to determine the failure probability as a function of mean values and logarithmic standard deviations. The 'design' failure point can be analytically calculated. Partial safety factors on the main variables (stress, crack size, material toughness) are obtained in relation with reliability target values. The approach is generalized to elastic plastic Fracture Mechanics (piping) by fitting J as a power law function of stress, crack size and yield strength. The simplified approach is validated by detailed probabilistic computations with PROBAN computer program. Assuming reasonable coefficients of variations (logarithmic standard deviations), the method helps to calibrate safety factors for different components taking into account reliability target values in normal, emergency and faulted conditions. Statistical data for the mechanical properties of the main basic materials complement the study. The work involves laboratory results and manufacture data. The results of this study are discussed within a working group of the French in service inspection code RSE-M. (authors)

  20. Proposed radiological protection criteria for waste disposal options

    International Nuclear Information System (INIS)

    Hill, M.D.

    1981-01-01

    Criteria which are based solely on the consequences of releases of radionuclides, that is doses to man, are inappropriate for decisions on the acceptability of many of the disposal options for solid wastes. The risks associated with disposal options in which the intention is to isolate wastes from the biosphere for any length of time have two major components: the probability that a release of radionuclides will occur and the probability that subsequent radiation doses will give rise to deleterious effects. It is therefore necessary to develop criteria which embody the basic radiological principle of keeping risks to acceptable levels and take account of both components of risk. In this paper proposed criteria are described and some of the implications of adopting these criteria are discussed. (author)

  1. The use of economic criteria in providing a basis for safe reactor operation

    International Nuclear Information System (INIS)

    Graham, J.

    1989-01-01

    Probabilistic criteria based upon an acceptance measure of protection for owner investment can complete the range of design probabilistic criteria between those set by acceptance public safety and those set by acceptable reliability in plant operation. Criteria which address the protection of owner investment have the benefit of lowering risk in adjacent risk regions by providing greater reliability in operation as well as less risk to the safety of the public and the environment. Such investment protection criteria are currently being used to extend plant life but they could also be used very beneficially as part of the initial design process. In this paper trial criteria are suggested which address the risk of extended plant shutdown with the resultant necessity to purchase replacement power, and the risk of replacement of expensive plant components. Additional financial assessment is required to ensure that there is a proper correlation between acceptable measures of owner-investment protection and the levels of probabilistic defence suggested, but the trial criteria proposed can be used as important practical design criteria

  2. NWTS program criteria for mined geologic disposal of nuclear waste: program objectives, functional requirements, and system performance criteria

    International Nuclear Information System (INIS)

    1981-04-01

    At the present time, final repository criteria have not been issued by the responsible agencies. This document describes general objectives, requirements, and criteria that the DOE intends to apply in the interim to the National Waste Terminal Storage (NWTS) Program. These objectives, requirements, and criteria have been developed on the basis of DOE's analysis of what is needed to achieve the National objective of safe waste disposal in an environmentally acceptable and economic manner and are expected to be consistent with anticipated regulatory standards. The qualitative statements in this document address the broad issues of public and occupational health and safety, institutional acceptability, engineering feasibility, and economic considerations. A comprehensive set of criteria, general and project specific, of which these are a part, will constitute a portion of the technical basis for preparation and submittal by the DOE of formal documents to support future license applications for nuclear waste repositories

  3. NWTS program criteria for mined geologic disposal of nuclear waste: program objectives, functional requirements, and system performance criteria

    Energy Technology Data Exchange (ETDEWEB)

    None

    1981-04-01

    At the present time, final repository criteria have not been issued by the responsible agencies. This document describes general objectives, requirements, and criteria that the DOE intends to apply in the interim to the National Waste Terminal Storage (NWTS) Program. These objectives, requirements, and criteria have been developed on the basis of DOE's analysis of what is needed to achieve the National objective of safe waste disposal in an environmentally acceptable and economic manner and are expected to be consistent with anticipated regulatory standards. The qualitative statements in this document address the broad issues of public and occupational health and safety, institutional acceptability, engineering feasibility, and economic considerations. A comprehensive set of criteria, general and project specific, of which these are a part, will constitute a portion of the technical basis for preparation and submittal by the DOE of formal documents to support future license applications for nuclear waste repositories.

  4. Top-level regulatory criteria for the standard MHTGR

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1986-10-15

    The Licensing Plan for the Standard MHTGR (Ref. 1) describes a program to support a U.S. Nuclear Regulatory Commission (NRC) design review and approval. The Plan calls for the submittal of Top-Level Regulatory Criteria to the NRC for concurrence with their completeness and acceptability for the MHTGR program. The Top-Level Regulatory Criteria are defined as the standards for judging licensability that directly specify acceptable limits for protection of the public health and safety and the environment. The criteria proposed herein are for normal plant operation and a broad spectrum of anticipated events, including accidents. The approach taken is to define a set of criteria which are general as opposed to being design specific. Specifically, it is recommended that criteria be met which: 1. Are less prescriptive than current regulation, thereby encouraging maximum flexibility in design approaches. 2. Are measurable. 3. Are not more strict than the criteria for current power plants.

  5. Present state of the design and realization of regional radioactive waste depositories and waste acceptance criteria for disposal

    International Nuclear Information System (INIS)

    Kortus, J.

    1988-01-01

    Surface type regional depositories for radioactive wastes from nuclear power plants are described in detail. The depository of the Mochovce nuclear power plant is located near the plant, that of the Dukovany nuclear power plant is directly on the premises of the plant. Particular attention is paid to the design of the monolithic reinforced concrete pits, draining of rainwater from their surface, draining of seeping rainwater from the pit environment by means of a double drainage system, and insulation of the pits against water. The construction of the Mochovce depository started in 1987; some experience gained from this activity is presented. The radioactive waste acceptance criteria for depositories of this kind, based on safety analysis, are given. (author). 2 figs

  6. Preliminary Results Of LOCA Problem For APR1400 Reactor

    International Nuclear Information System (INIS)

    Le Dai Dien; Hoang Minh Giang; Le Thi Thu; Vo Thi Huong; Le Van Hong

    2011-01-01

    Several features of NPP with APR1400 nuclear reactor during a loss of coolant accident (LOCA) are investigated in this study. The report describes some main design characteristics of an engineering safety systems of APR1400 and the thermal hydraulic calculation results for steady-state using MARS and RELAP/SCDAPSIM codes. Large Break LOCA accident has been analyzed and evaluated based on acceptable criteria for ECCS given by US NRC. The results from cold leg break LOCA with broken area of 0.0465 m 2 in case of high pressure safety injection system (HPSI) failed to operate or 2 and 4 HPSI pumps are activated. The preliminary results of this work is a part of collaboration between INST researchers and KAERI experts in using RELAP tool for safety analysis of NPPs. (author)

  7. Modeling Carbon Turnover in Five Terrestrial Ecosystems in the Boreal Zone Using Multiple Criteria of Acceptance

    International Nuclear Information System (INIS)

    Karlberg, Louise; Gustafsson, David; Jansson, Per-Erik

    2006-01-01

    Estimates of carbon fluxes and turnover in ecosystems are key elements in the understanding of climate change and in predicting the accumulation of trace elements in the biosphere. In this paper we present estimates of carbon fluxes and turnover times for five terrestrial ecosystems using a modeling approach. Multiple criteria of acceptance were used to parameterize the model, thus incorporating large amounts of multi-faceted empirical data in the simulations in a standardized manner. Mean turnover times of carbon were found to be rather similar between systems with a few exceptions, even though the size of both the pools and the fluxes varied substantially. Depending on the route of the carbon through the ecosystem, turnover times varied from less than one year to more than one hundred, which may be of importance when considering trace element transport and retention. The parameterization method was useful both in the estimation of unknown parameters, and to identify variability in carbon turnover in the selected ecosystems

  8. Preliminary designs: passive solar manufactured housing. Technical status report

    Energy Technology Data Exchange (ETDEWEB)

    1980-05-12

    The criteria established to guide the development of the preliminary designs are listed. Three preliminary designs incorporating direct gain and/or sunspace are presented. Costs, drawings, and supporting calculations are included. (MHR)

  9. A Feasibility Trial of Mental Health First Aid First Nations: Acceptability, Cultural Adaptation, and Preliminary Outcomes.

    Science.gov (United States)

    Crooks, Claire V; Lapp, Andrea; Auger, Monique; van der Woerd, Kim; Snowshoe, Angela; Rogers, Billie Jo; Tsuruda, Samantha; Caron, Cassidy

    2018-03-25

    The Mental Health First Aid First Nations course was adapted from Mental Health First Aid Basic to create a community-based, culturally safe and relevant approach to promoting mental health literacy in First Nations contexts. Over 2.5 days, the course aims to build community capacity by teaching individuals to recognize and respond to mental health crises. This feasibility trial utilized mixed methods to evaluate the acceptability, cultural adaptation, and preliminary effectiveness of MHFAFN. Our approach was grounded in community-based participatory research principles, emphasizing relationship-driven procedures to collecting data and choice for how participants shared their voices. Data included participant interviews (n = 89), and surveys (n = 91) from 10 groups in four provinces. Surveys contained open-ended questions, retrospective pre-post ratings, and a scenario. We utilized data from nine facilitator interviews and 24 facilitator implementation surveys. The different lines of evidence converged to highlight strong acceptability, mixed reactions to the cultural adaptation, and gains in participants' knowledge, mental health first aid skill application, awareness, and self-efficacy, and reductions in stigma beliefs. Beyond promoting individual gains, the course served as a community-wide prevention approach by situating mental health in a colonial context and highlighting local resources and cultural strengths for promoting mental well-being. © 2018 The Authors American Journal of Community Psychology published by Wiley Periodicals, Inc. on behalf of Society for Community Research and Action.

  10. Preliminary Assessment of the Hanford Tank Waste Feed Acceptance and Product Qualification Programs

    Energy Technology Data Exchange (ETDEWEB)

    Herman, C. C.; Adamson, Duane J.; Herman, D. T.; Peeler, David K.; Poirier, Micheal R.; Reboul, S. H.; Stone, M. E.; Peterson, Reid A.; Chun, Jaehun; Fort, James A.; Vienna, John D.; Wells, Beric E.

    2013-04-01

    The U.S. Department of Energy Office of Environmental Management (EM) is engaging the national laboratories to provide the scientific and technological rigor to support EM program and project planning, technology development and deployment, project execution, and assessment of program outcomes. As an early demonstration of this new responsibility, Savannah River National Laboratory (SRNL) and Pacific Northwest National Laboratory (PNNL) have been chartered to implement a science and technology program addressing Hanford Tank waste feed acceptance and product qualification. As a first step, the laboratories examined the technical risks and uncertainties associated with the planned waste feed acceptance and qualification testing for Hanford tank wastes. Science and technology gaps were identified for work associated with 1) feed criteria development with emphasis on identifying the feed properties and the process requirements, 2) the Tank Waste Treatment and Immobilization Plant (WTP) process qualification program, and 3) the WTP HLW glass product qualification program. Opportunities for streamlining the accetpance and qualification programs were also considered in the gap assessment. Technical approaches to address the science and technology gaps and/or implement the opportunities were identified. These approaches will be further refined and developed as strong integrated teams of researchers from national laboratories, contractors, industry, and academia are brought together to provide the best science and technology solutions. Pursuing the identified approaches will have immediate and long-term benefits to DOE in reducing risks and uncertainties associated with tank waste removal and preparation, transfers from the tank farm to the WTP, processing within the WTP Pretreatment Facility, and in producing qualified HLW glass products. Additionally, implementation of the identified opportunities provides the potential for long-term cost savings given the anticipated

  11. Sediment quality criteria: A review with recommendations for developing criteria for the Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    Driver, C.J.

    1994-05-01

    Criteria for determining the quality of liver sediment are necessary to ensure that concentrations of contaminants in aquatic systems are within acceptable limits for the protection of aquatic and human life. Such criteria should facilitate decision-making about remediation, handling, and disposal of contaminants. Several approaches to the development of sediment quality criteria (SQC) have been described and include both descriptive and numerical methods. However, no single method measures all impacts at all times to all organisms (U.S. EPA 1992b). The U.S. EPA`s interest is primarily in establishing chemically based, numerical SQC that are applicable nation-wide (Shea 1988). Of the approaches proposed for SQC development, only three are being considered for numerical SQC on a national level. These approaches include an Equilibrium Partitioning Approach, a site-specific method using bioassays (the Apparent Effects Threshold Approach), and an approach similar to EPA`s water quality criteria (Pavlou and Weston 1984). Although national (or even regional) criteria address a number of political, litigative, and engineering needs, some researchers feel that protection of benthic communities require site-specific, biologically based criteria (Baudo et al. 1990). This is particularly true for areas where complex mixtures of contaminants are present in sediments. Other scientifically valid and accepted procedures for freshwater SQC include a background concentration approach, methods using field or spiked bioassays, a screening level concentration approach, the Apparent Effects Threshold Approach, the Sediment Quality Triad, the International Joint Commission Sediment Assessment Strategy, and the National Status and Trends Program Approach. The various sediment assessment approaches are evaluated for application to the Hanford Reach and recommendations for Hanford Site sediment quality criteria are discussed.

  12. Early Site Permit Demonstration Program: Regulatory criteria evaluation report

    International Nuclear Information System (INIS)

    1993-03-01

    The primary objective of the Early Site Plan Demonstration Program (ESPDP) is to demonstrate successfully the use of 10CFR52 to obtain ESPs for one or more US sites for one (or more) ALWR nuclear power plants. It is anticipated that preparation of the ESP application and interaction with NRC during the application review process will result not only in an ESP for the applicant(s) but also in the development of criteria and definition of processes, setting the precedent that facilitates ESPs for subsequent ESP applications. Because siting regulatory processes and acceptance criteria are contained in over 100 separate documents, comprehensive licensing and technical reviews were performed to establish whether the requirements and documentation are self-consistent, whether the acceptance criteria are sufficiently well-defined and clear, and whether the licensing process leading to the issuance of an ESP is unambiguously specified. This document provides appendices A and B of this report. Appendix A contains a list of regulations, regulatory guidance, and acceptance criteria; Appendix B contains a cross-reference index of siting-related documentation

  13. Crew Transportation Technical Standards and Design Evaluation Criteria

    Science.gov (United States)

    Lueders, Kathryn L.; Thomas, Rayelle E. (Compiler)

    2015-01-01

    Crew Transportation Technical Standards and Design Evaluation Criteria contains descriptions of technical, safety, and crew health medical processes and specifications, and the criteria which will be used to evaluate the acceptability of the Commercial Providers' proposed processes and specifications.

  14. An Examination of Acceptable Navigation Accuracy for LISA Orbits

    National Research Council Canada - National Science Library

    Smythe, Reid W

    2007-01-01

    .... Preliminary analysis indicated the values of each parameter varied sinusoidally, and increasing the initial error conditions tended to reduce the time each parameter fell within the acceptable tolerance values...

  15. Risk based seismic design criteria

    International Nuclear Information System (INIS)

    Kennedy, R.P.

    1999-01-01

    In order to develop a risk based seismic design criteria the following four issues must be addressed: (1) What target annual probability of seismic induced unacceptable performance is acceptable? (2) What minimum seismic margin is acceptable? (3) Given the decisions made under Issues 1 and 2, at what annual frequency of exceedance should the safe-shutdown-earthquake (SSE) ground motion be defined? (4) What seismic design criteria should be established to reasonably achieve the seismic margin defined under Issue 2? The first issue is purely a policy decision and is not addressed in this paper. Each of the other three issues are addressed. Issues 2 and 3 are integrally tied together so that a very large number of possible combinations of responses to these two issues can be used to achieve the target goal defined under Issue 1. Section 2 lays out a combined approach to these two issues and presents three potentially attractive combined resolutions of these two issues which reasonably achieves the target goal. The remainder of the paper discusses an approach which can be used to develop seismic design criteria aimed at achieving the desired seismic margin defined in resolution of Issue 2. Suggestions for revising existing seismic design criteria to more consistently achieve the desired seismic margin are presented. (orig.)

  16. Development of the EU Ecolabel Criteria and Revision of the EU Green Public Procurement Criteria for Cleaning Services

    OpenAIRE

    DE ALMEIDA FERREIRA NETO BELMIRA; WOLF Oliver; FIELD Bethany; JENKIN Nicola; TAM Max; BENJAMIN Oscar

    2016-01-01

    The objective of this project is to develop a new EU Ecolabel and revise the existing EU Green Public Procurement (GPP) criteria for professional cleaning services (hereafter referred to as cleaning services). This preliminary report investigates the market, operational and sustainability aspects of cleaning services, with a goal to develop a robust evidence base and prioritise key environmental and social issues to support the development of EU Ecolabel criteria and the revision of the EU GP...

  17. Experimental activity on the definition of acceptance criteria for the ITER divertor plasma facing components

    International Nuclear Information System (INIS)

    Escourbiac, F.; Constans, S.; Vignal, N.; Cantone, V.; Richou, M.; Durocher, A.; Riccardi, B.; Bobin, I.; Jouvelot, J.L.; Merola, M.

    2009-01-01

    Tens of thousands of armor/heat sink joints will be produced by the industry during the manufacturing of ITER divertor PFC, statistically, there is a probability that joints with defects be delivered. The purpose of this paper is to study the detection and evolution during operation of calibrated defects artificially implemented on samples, as an experimental basis for the definition of acceptance criteria for the bond armor/heat sink in the frame of industrial manufacturing conditions.It was found that current CFC monoblock design option was compatible with the heat loads specified at the lower part of the vertical target (up to 20 MW/m 2 ), including the presence of armor/heat sink defects (up to 50 deg. extension for a location at 0 deg. or 45 deg.) detectable with NDE techniques developed in Europe (US, SATIR). The current W monoblock design appeared suitable for the upper part of the vertical target with defects extension up to 50 deg. but is not adapted for heat flux of 20 MW/m 2 . The studied W flat tile design proved to be compatible with fluxes of 5 MW/m 2 but unable to sustain cycling fluxes of 10 MW/m 2 .

  18. At-reactor storage concepts criteria for preliminary assessment

    International Nuclear Information System (INIS)

    Boydston, L.A.

    1981-12-01

    The licensing, safety, and environmental considerations of four wet and four dry at-reactor storage concepts are presented. Physical criteria for each concept are examined to determine the minimum site and facility requirements which must be met by a utility which desires to expand its at-reactor spent fuel storage capability

  19. Probabilistic relationships in acceptable risk studies

    International Nuclear Information System (INIS)

    Benjamin, J.R.

    1977-01-01

    Acceptable risk studies involve uncertainties in future events; consequences and associated values, the acceptability levels, and the future decision environment. Probabilistic procedures afford the basic analytical tool to study the influence of each of these parameters on the acceptable risk decision, including their interrelationships, and combinations. A series of examples are presented in the paper in increasing complexity to illustrate the principles involved and to quantify the relationships to the acceptable risk decision. The basic objective of such studies is to broaden the scientific basis of acceptable risk decision making. It is shown that rationality and consistency in decision making is facilitated by such studies and that rather simple relationships exist in many situations of interest. The variation in criteria associated with an increase in the state of knowledge or change in the level of acceptability is also discussed. (Auth.)

  20. Probabilistic relationships in acceptable risk studies

    International Nuclear Information System (INIS)

    Benjamin, J.R.

    1977-01-01

    Acceptable risk studies involve uncertainties in future events: consequences and associated values, the acceptability levels, and the future decision environment. Probabilistic procedures afford the basic analytical tool to study the influence of each of these parameters on the acceptable risk decision, including their interrelationships, and combinations. A series of examples are presented in the paper in increasing complexity to illustrate the principles involved and to quantify the relationships to the acceptable risk decision. The basic objective of such studies is to broaden the scientific basis of acceptable risk decision making. It is shown that rationality and consistency in decision making is facilitated by such studies and that rather simple relationships exist in many situations of interest. The variation in criteria associated with an increase in the state of knowledge or change in the level of acceptability is also discussed

  1. Spent fuel acceptance scenarios devoted to shutdown reactors: A preliminary analysis

    International Nuclear Information System (INIS)

    Wood, T.W.; Plummer, A.M.; Dippold, D.G.; Short, S.M.

    1989-10-01

    Spent fuel acceptance schedules and the allocation of federal acceptance capacity among commercial nuclear power reactors have important operational and cost consequences for reactor operators. Alternative allocation schemes were investigated to some extent in DOE's MRS Systems Study. The current study supplements these analyses for a class of acceptance schemes in which the acceptance capacity of the federal radioactive waste management system is allocated principally to shutdown commercial power reactors, and extends the scope of analysis to include considerations of at-reactor cask loading rates. The operational consequences of these schemes for power reactors, as measured in terms of quantity of spent fuel storage requirement above storage pool capacities and number of years of pool operations after last discharge, are estimated, as are the associated utility costs. This study does not attempt to examine the inter-utility equity considerations involved in departures from the current oldest-fuel-first (OFF) allocation rule as specified in the ''Standard Contract for Disposal of Spent Nuclear Fuel and/or High-Level Radioactive Waste.'' In the sense that the alternative allocations are more economically efficient than OFF, however, they approximate the allocations that could result from free exchange of acceptance rights among utilities. Such a process would result in the preservation of inter-utility equity. 13 refs., 9 figs., 9 tabs

  2. Feasibility and acceptability of electronic symptom surveillance with clinician feedback using the Patient-Reported Outcomes version of Common Terminology Criteria for Adverse Events (PRO-CTCAE) in Danish prostate cancer patients

    DEFF Research Database (Denmark)

    Baeksted, Christina; Pappot, Helle; Nissen, Aase

    2017-01-01

    Background: The aim was to examine the feasibility, acceptability and clinical utility of electronic symptom surveillance with clinician feedback using a subset of items drawn from the Patient-Reported Outcomes version of Common Terminology Criteria for Adverse Events (PRO-CTCAE) in a cancer...

  3. Safety criteria from the public viewpoint

    International Nuclear Information System (INIS)

    Renn, O.

    1994-01-01

    The paper attempts to outline the scope and limits of a consensus for the evaluation of energy systems, particularly nuclear energy. It is divided into four sections. The first section deals with factual acceptance of technology, while the second inquires into the specific acceptance of nuclear energy, i.e., public perception and valuation of nuclear energy today. The third section discusses criteria of acceptability. In the fourth section, finally, the author deals with questions concerning an energy consensus and presents his own model for approaching this issue. (orig.) [de

  4. Technical considerations associated with spent fuel acceptance. Final report

    International Nuclear Information System (INIS)

    Supko, E.M.

    1996-06-01

    This study was initiated by the Electric Power Research Institute (EPRI) to identify technical considerations associated with spent fuel acceptance and implementation of a waste management system that includes the use of transportable storage systems, and to serve as an opening dialogue among Standard Contract Holders and the department of Energy's Office of Civilian Radioactive Waste management (OCRWM) prior to the development of waste acceptance criteria or issuance of a Notice of Proposed Rulemaking by OCRWM to amend the Standard Contract. The original purpose of the Notice of Proposed Rulemaking was to address changes to the Standard Contract to implement a multi-purpose canister based system and to address other issues that were not adequately addressed in the standard contract. Even if DOE does not develop a multi-purpose canister based system for waste acceptance, it will still be necessary to develop waste acceptance criteria in order to accept spent fuel in transportable storage systems that are being deployed for at-reactor storage. In this study, technical issues associated with spent fuel acceptance will be defined and potential options and alternatives for resolution of technical considerations will be explored

  5. Criteria for the development and use of the methodology for environmentally-acceptable fossil energy site evaluation and selection. Volume 2. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Eckstein, L.; Northrop, G.; Scott, R.

    1980-02-01

    This report serves as a companion document to the report, Volume 1: Environmentally-Acceptable Fossil Energy Site Evaluation and Selection: Methodology and Users Guide, in which a methodology was developed which allows the siting of fossil fuel conversion facilities in areas with the least environmental impact. The methodology, known as SELECS (Site Evaluation for Energy Conversion Systems) does not replace a site specific environmental assessment, or an environmental impact statement (EIS), but does enhance the value of an EIS by thinning down the number of options to a manageable level, by doing this in an objective, open and selective manner, and by providing preliminary assessment and procedures which can be utilized during the research and writing of the actual impact statement.

  6. The mediating role of pain acceptance during mindfulness-based cognitive therapy for headache.

    Science.gov (United States)

    Day, Melissa A; Thorn, Beverly E

    2016-04-01

    This study aimed to determine if mindfulness-based cognitive therapy (MBCT) engenders improvement in headache outcomes via the mechanisms specified by theory: (1) change in psychological process, (i.e., pain acceptance); and concurrently (2) change in cognitive content, (i.e., pain catastrophizing; headache management self-efficacy). A secondary analysis of a randomized controlled trial comparing MBCT to a medical treatment as usual, delayed treatment (DT) control was conducted. Participants were individuals with headache pain who completed MBCT or DT (N=24) at the Kilgo Headache Clinic or psychology clinic. Standardized measures of the primary outcome (pain interference) and proposed mediators were administered at pre- and post-treatment; change scores were calculated. Bootstrap mediation models were conducted. Pain acceptance emerged as a significant mediator of the group-interference relation (pMediation models examining acceptance subscales showed nuances in this effect, with activity engagement emerging as a significant mediator (pmediation due to a non-significant pathway from the mediator to outcome. Criteria for mediation was also not met for the catastrophizing or self-efficacy models as neither of these variables significantly predicted pain interference. Pain acceptance, and specifically engagement in valued activities despite pain, may be a key mechanism underlying improvement in pain outcome during a MBCT for headache pain intervention. The theorized mediating role of cognitive content factors was not supported in this preliminary study. A large, definitive trial is warranted to replicate and extend the findings in order to streamline and optimize MBCT for headache. Copyright © 2016 Elsevier Ltd. All rights reserved.

  7. Acceptance and commitment therapy in youth with neurofibromatosis type 1 (NF1) and chronic pain and their parents: A pilot study of feasibility and preliminary efficacy.

    Science.gov (United States)

    Martin, Staci; Wolters, Pamela L; Toledo-Tamula, Mary Anne; Schmitt, Shawn Nelson; Baldwin, Andrea; Starosta, Amy; Gillespie, Andrea; Widemann, Brigitte

    2016-06-01

    Neurofibromatosis type 1 (NF1) is an autosomal dominant genetic disorder affecting about 1 in 3,500 individuals. Chronic pain is commonly reported among individuals with NF1 and plexiform neurofibroma tumors (PNs). Acceptance and Commitment Therapy (ACT), an empirically supported method for addressing chronic pain, helps individuals re-focus on valued relationships and activities. This pilot study investigated the feasibility and preliminary efficacy of a brief ACT workshop in the NF1 population. Eligible participants included adolescents and young adults (AYA; 12-21 years) with NF1 and chronic pain that interfered with daily functioning and their parents. Patients and parents completed baseline measures of pain interference, pain intensity, functional disability, pain acceptance, depression, and anxiety. Then, AYA and parents participated separately in a 2-day small-group ACT workshop. A telephone booster session occurred 1 month post-intervention. Three-month post-treatment measures were completed by mail. Ten adolescents (4 males; M age = 16.9 years) and seven parents provided baseline and 3-month data. Mean satisfaction with the study was moderate to high (3.9 for patients and 4.6 for parents on a 1-5 scales). Patients and parents reported significant declines in patients' pain interference at 3 months post-treatment. Patient-reported pain intensity significantly declined from baseline to 3 months. Parents reported marginally greater acceptance of their child's pain. No changes emerged in functional ability or mood. Preliminary findings suggest that a brief ACT group intervention is feasible and may help AYA with NF1 and PNs cope with their chronic pain, although larger randomized studies are needed to confirm treatment efficacy. © 2016 Wiley Periodicals, Inc. © 2016 Wiley Periodicals, Inc.

  8. The Japanese version of the modified ACR preliminary diagnostic criteria for fibromyalgia and the fibromyalgia symptom scale: reliability and validity.

    Science.gov (United States)

    Usui, Chie; Hatta, Kotaro; Aratani, Satoko; Yagishita, Naoko; Nishioka, Kenya; Kanazawa, Teruhisa; Itoh, Kenji; Yamano, Yoshihisa; Nakamura, Hiroyuki; Nakajima, Toshihiro; Nishioka, Kusuki

    2013-09-01

    The aim of this study is to investigate the reliability and validity of the Japanese version of the modified American College of Rheumatology (ACR) Preliminary Diagnostic Criteria for Fibromyalgia (mACR 2010-J) and the Fibromyalgia Symptom Scale (mFS-J). According to the ACR 1990 classification criteria, patients with chronic pain were divided into the fibromyalgia group and nonfibromyalgia group (rheumatoid arthritis and osteoarthritis). Patients in both groups were assessed using mACR 2010-J and mFS-J. 294 of 462 (64 %) patients in the fibromyalgia group met mACR 2010-J, whereas 4 % (9/231) of the nonfibromyalgia group did, with sensitivity of 64 %, specificity of 96 %, positive predictive value of 97 %, negative predictive value of 56 %, and positive likelihood ratio of 16.3. Mean total scores on mFS-J significantly differentiated the fibromyalgia from the nonfibromyalgia group. According to the value of the Youden index, the best cutoff score for the mFS-J was 9/10. Our findings indicate that mACR 2010-J as a positive test and mFS-J as a quantification scale might be suitable for assessing fibromyalgia among Japanese chronic pain populations.

  9. Cone penetrometer moisture probe acceptance test report

    International Nuclear Information System (INIS)

    Barnes, G.A.

    1996-01-01

    This Acceptance Test Report (ATR) documents the results of WHC-SD-WM-ATP-146 (Prototype Cone Penetrometer Moisture Probe Acceptance Test Procedure) and WHC-SD-WM-ATP-145 (Cone Penetrometer Moisture Probe Acceptance Test Procedure). The master copy of WHC-SD-WM-ATP-145 can be found in Appendix A and the master copy of WHC-SD-WM-ATP-146 can be found in Appendix B. Also included with this report is a matrix showing design criteria of the cone penetrometer moisture probe and the verification method used (Appendix C)

  10. Heat exchanger, head and shell acceptance criteria

    International Nuclear Information System (INIS)

    Lam, P.S.; Sindelar, R.L.

    1992-09-01

    Instability of postulated flaws in the head component of the heat exchanger could not produce a large break, equivalent to a DEGB in the PWS piping, due to the configuration of the head and restraint provided by the staybolts. Rather, leakage from throughwall flaws in the head would increase with flaw length with finite leakage areas that are bounded by a post-instability flaw configuration. Postulated flaws at instability in the shell of the heat exchanger or in the cooling water nozzles could produce a large break in the Cooling Water System (CWS) pressure boundary. An initial analysis of flaw stability for postulated flaws in the heat exchanger head was performed in January 1992. This present report updates that analysis and, additionally, provides acceptable flaw configurations to maintain defined structural or safety margins against flaw instability of the external pressure boundary components of the heat exchanger, namely the head, shell, and cooling water nozzles. Structural and flaw stability analyses of the heat exchanger tubes, the internal pressure boundary of the heat exchangers or interface boundary between the PWS and CWS, were previously completed in February 1992 as part of the heat exchanger restart evaluation and are not covered in this report

  11. Safety and reliability criteria

    International Nuclear Information System (INIS)

    O'Neil, R.

    1978-01-01

    Nuclear power plants and, in particular, reactor pressure boundary components have unique reliability requirements, in that usually no significant redundancy is possible, and a single failure can give rise to possible widespread core damage and fission product release. Reliability may be required for availability or safety reasons, but in the case of the pressure boundary and certain other systems safety may dominate. Possible Safety and Reliability (S and R) criteria are proposed which would produce acceptable reactor design. Without some S and R requirement the designer has no way of knowing how far he must go in analysing his system or component, or whether his proposed solution is likely to gain acceptance. The paper shows how reliability targets for given components and systems can be individually considered against the derived S and R criteria at the design and construction stage. Since in the case of nuclear pressure boundary components there is often very little direct experience on which to base reliability studies, relevant non-nuclear experience is examined. (author)

  12. Preliminary results of testing bioassay analytical performance standards

    International Nuclear Information System (INIS)

    Fisher, D.R.; Robinson, A.V.; Hadley, R.T.

    1983-08-01

    The analytical performance of both in vivo and in vitro bioassay laboratories is being studied to determine the capability of these laboratories to meet the minimum criteria for accuracy and precision specified in the draft ANSI Standard N13.30, Performance Criteria for Radiobioassay. This paper presents preliminary results of the first round of testing

  13. A systematic review of patient acceptance of consumer health information technology.

    Science.gov (United States)

    Or, Calvin K L; Karsh, Ben-Tzion

    2009-01-01

    A systematic literature review was performed to identify variables promoting consumer health information technology (CHIT) acceptance among patients. The electronic bibliographic databases Web of Science, Business Source Elite, CINAHL, Communication and Mass Media Complete, MEDLINE, PsycArticles, and PsycInfo were searched. A cited reference search of articles meeting the inclusion criteria was also conducted to reduce misses. Fifty-two articles met the selection criteria. Among them, 94 different variables were tested for associations with acceptance. Most of those tested (71%) were patient factors, including sociodemographic characteristics, health- and treatment-related variables, and prior experience or exposure to computer/health technology. Only ten variables were related to human-technology interaction; 16 were organizational factors; and one was related to the environment. In total, 62 (66%) were found to predict acceptance in at least one study. Existing literature focused largely on patient-related factors. No studies examined the impact of social and task factors on acceptance, and few tested the effects of organizational or environmental factors on acceptance. Future research guided by technology acceptance theories should fill those gaps to improve our understanding of patient CHIT acceptance, which in turn could lead to better CHIT design and implementation.

  14. American College of Rheumatology provisional criteria for defining clinical inactive disease in select categories of juvenile idiopathic arthritis.

    Science.gov (United States)

    Wallace, Carol A; Giannini, Edward H; Huang, Bin; Itert, Lukasz; Ruperto, Nicolino

    2011-07-01

    To prospectively validate the preliminary criteria for clinical inactive disease (CID) in patients with select categories of juvenile idiopathic arthritis (JIA). We used the process for development of classification and response criteria recommended by the American College of Rheumatology Quality of Care Committee. Patient-visit profiles were extracted from the phase III randomized controlled trial of infliximab in polyarticular-course JIA (i.e., patients considered to resemble those with select categories of JIA) and sent to an international group of expert physician raters. Using the physician ratings as the gold standard, the sensitivity and specificity were calculated using the preliminary criteria. Modifications to the criteria were made, and these were sent to a larger group of pediatric rheumatologists to determine quantitative, face, and content validity. Variables weighted heaviest by physicians when making their judgment were the number of joints with active arthritis, erythrocyte sedimentation rate (ESR), physician's global assessment, and duration of morning stiffness. Three modifications were made: the definition of uveitis, the definition of abnormal ESR, and the addition of morning stiffness. These changes did not alter the accuracy of the preliminary set. The modified criteria, termed the "criteria for CID in select categories of JIA," have excellent feasibility and face, content, criterion, and discriminant validity to detect CID in select categories of JIA. The small changes made to the preliminary criteria set did not alter the area under the receiver operating characteristic curve (0.954) or accuracy (91%), but have increased face and content validity. Copyright © 2011 by the American College of Rheumatology.

  15. A comparison between criteria for diagnosing atopic eczema in infants

    DEFF Research Database (Denmark)

    Jøhnke, H; Vach, W; Norberg, L A

    2005-01-01

    Research Centre (DARC) criteria developed for this study and doctor-diagnosed visible eczema with typical morphology and atopic distribution. Additionally, the U.K. diagnostic criteria based on a questionnaire were used at 1 year of age. Agreement between the four criteria was analysed at each time point...... the four criteria demonstrated that cumulative incidences showed better agreement than point prevalence values. CONCLUSIONS: Agreement between different criteria for diagnosing AE was acceptable, but the mild cases constituted a diagnostic problem, although they were in the minority. Repeated examinations...

  16. W-087 Acceptance test procedure. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Joshi, A.W.

    1997-06-10

    This Acceptance Test Procedure/Operational Test Procedure (ATP/OTP) has been prepared to demonstrate that the Electrical/Instrumentation and Mechanical systems function as required by project criteria and to verify proper operation of the integrated system including the interlocks.

  17. W-087 Acceptance test procedure. Revision 1

    International Nuclear Information System (INIS)

    Joshi, A.W.

    1997-01-01

    This Acceptance Test Procedure/Operational Test Procedure (ATP/OTP) has been prepared to demonstrate that the Electrical/Instrumentation and Mechanical systems function as required by project criteria and to verify proper operation of the integrated system including the interlocks

  18. An evaluation and acceptance of COTS software for FPGA-based controllers in NPPS

    International Nuclear Information System (INIS)

    Jung, Sejin; Kim, Eui-Sub; Yoo, Junbeom; Kim, Jang-Yeol; Choi, Jong Gyun

    2016-01-01

    Highlights: • All direct/indirect COTS SW should be dedicated. • FPGA synthesis tools are important for the safety of new digital I&Cs. • No standards/reports are yet available to deal with the indirect SW – FPGA synthesis tools. • This paper proposes a new evaluation/acceptance process and criteria for indirect SW. - Abstract: FPGA (Field-Programmable Gate Array) has received much attention from nuclear industry as an alternative platform of PLC (Programmable Logic Controller)-based digital I&C (Instrumentation & Control). Software aspect of FPGA development encompasses several commercial tools such as logic synthesis and P&R (Place & Route), which should be first dedicated in accordance with domestic standards based on EPRI NP-5652. Even if a state-of-the-art supplementary EPRI TR-1025243 makes an effort, the dedication of indirect COTS (Commercial Off-The-Shelf) SW such as FPGA logic synthesis tools has still caused a dispute. This paper proposes an acceptance process and evaluation criteria, specific to COTS SW, not commercial-grade direct items. It specifically incorporates indirect COTS SW and also provides categorized evaluation criteria for acceptance. It provides an explicit linkage between acceptance methods (Verification and Validation techniques) and evaluation criteria, too. We tried to perform the evaluation and acceptance process upon a commercial FPGA logic synthesis tool being used to develop a new FPGA-based digital I&C in Korea, and could confirm its applicability.

  19. Manufacturing and testing of reference samples for the definition of acceptance criteria for the ITER divertor

    International Nuclear Information System (INIS)

    Visca, Eliseo; Cacciotti, E.; Libera, S.; Mancini, A.; Pizzuto, A.; Roccella, S.; Riccardi, B.; Escourbiac, F.; Sanguinetti, G.P.

    2010-01-01

    The most critical part of a high heat flux (HHF) plasma facing component (PFC) is the armour to heat sink joint. An experimental study was launched by EFDA in order to define the acceptance criteria to be used for the procurements of the ITER Divertor PFCs. ENEA is involved in the European International Thermonuclear Experimental Reactor (ITER) R and D activities and together with Ansaldo Ricerche S.p.A. has manufactured several PFCs mock-ups using the Hot Radial Pressing and Pre-Brazed Casting technologies. According to the technical specifications issued by EFDA, ENEA and Ansaldo have collaborated to manufacture half of the samples with calibrated artificial defects required for this experimental study. After manufacturing, the samples were examined by ultrasonic and SATIR non-destructive examination (NDE) methods in order to confirm the size and position of the artificial defects. In particular, it was concluded that defects are detectable with these NDE techniques and they finally gave indication about the threshold of propagation during high heat flux experiments relevant with heat fluxes expected in ITER Divertor. This paper reports the manufacturing procedure used to obtain the required calibrated artificial defects in the CFC and W armoured samples as well as the NDE results and the thermal high heat flux results.

  20. Manufacturing and testing of reference samples for the definition of acceptance criteria for the ITER divertor

    Energy Technology Data Exchange (ETDEWEB)

    Visca, Eliseo, E-mail: visca@frascati.enea.i [Associazione EURATOM-ENEA sulla Fusione, Frascati (Italy); Cacciotti, E.; Libera, S.; Mancini, A.; Pizzuto, A.; Roccella, S. [Associazione EURATOM-ENEA sulla Fusione, Frascati (Italy); Riccardi, B., E-mail: Bruno.Riccardi@f4e.europa.e [Fusion For Energy, Barcelona (Spain); Escourbiac, F., E-mail: frederic.escourbiac@iter.or [ITER Organization, Cadarache (France); Sanguinetti, G.P., E-mail: gianpaolo.sanguinetti@aen.ansaldo.i [Ansaldo Energia S.p.A., Genova (Italy)

    2010-12-15

    The most critical part of a high heat flux (HHF) plasma facing component (PFC) is the armour to heat sink joint. An experimental study was launched by EFDA in order to define the acceptance criteria to be used for the procurements of the ITER Divertor PFCs. ENEA is involved in the European International Thermonuclear Experimental Reactor (ITER) R and D activities and together with Ansaldo Ricerche S.p.A. has manufactured several PFCs mock-ups using the Hot Radial Pressing and Pre-Brazed Casting technologies. According to the technical specifications issued by EFDA, ENEA and Ansaldo have collaborated to manufacture half of the samples with calibrated artificial defects required for this experimental study. After manufacturing, the samples were examined by ultrasonic and SATIR non-destructive examination (NDE) methods in order to confirm the size and position of the artificial defects. In particular, it was concluded that defects are detectable with these NDE techniques and they finally gave indication about the threshold of propagation during high heat flux experiments relevant with heat fluxes expected in ITER Divertor. This paper reports the manufacturing procedure used to obtain the required calibrated artificial defects in the CFC and W armoured samples as well as the NDE results and the thermal high heat flux results.

  1. The development of criteria for radioactive waste disposal

    International Nuclear Information System (INIS)

    Wagstaff, K.P.

    1985-02-01

    Radiation protection criteria are needed in Canada for judging the acceptability of radioactive waste disposal options for which there are potential long-term radiological impacts. This paper discusses the difficulties encountered in applying the ICRP system of dose limitation to the long term and the alternative approaches to criteria being developed and adopted by various other international and national bodies. Finally, the present situation in Canada is reviewed and conclusions are drawn on the general direction in which national criteria are being formulated and expressed

  2. Space reactor preliminary mechanical design

    International Nuclear Information System (INIS)

    Meier, K.L.

    1983-01-01

    An analysis was performed on the SABRE reactor space power system to determine the effect of the number and size of heat pipes on the design parameters of the nuclear subsystem. Small numbers of thin walled heat pipes were found to give a lower subsystem mass, but excessive fuel swelling resulted. The SP-100 preliminary design uses 120 heat pipes because of acceptable fuel swelling and a minimum nuclear subsystem mass of 1875 kg. Salient features of the reactor preliminary design are: individual fuel modules, ZrO 2 block core mounts, bolted collar fuel module restraints, and a BeO central plug

  3. Laboratory-performance criteria for in situ waste-stabilization materials

    International Nuclear Information System (INIS)

    Shaw, P.; Weidner, J.

    1996-01-01

    The Department of Energy (DOE) Landfill Stabilization Focus Area is investigating a variety of in situ placement methods, grout materials, and characterization techniques for the stabilization of buried low-level transuranic-contaminated waste at Department of Energy sites. In situ stabilization involves underground injection or placement of substances to isolate, treat, or contain buried contaminants. Performance criteria were developed to evaluate various candidate stabilization materials for both long-term stabilization and interim stabilization or retrieval. The criteria are go/no-go, ready, and preliminary. The criterion go/no-go eliminates technologies that are not applicable for in situ treatment of buried waste. The criterion ready indicates that the technology is sufficiently developed and proven to be field demonstrated full-scale. The criterion preliminary indicates the prospective technologies to be potentially applicable to in situ buried waste stabilization, but further development is needed before the technology is ready for field-scale demonstration

  4. Scientific opinion on the evaluation of substances as acceptable previous cargoes for edible fats and oils

    DEFF Research Database (Denmark)

    Petersen, Annette

    Shipping of edible fats and oils into Europe is permitted in bulk tanks, provided that the previous cargo is included in a positive list. The European Commission requested EFSA to evaluate the acceptability as previous cargoes for fats and oils the substances calcium lignosulphonate, methyl acetate...... the criteria for acceptability as previous cargoes. Due to uncertainties, mainly with regard to the composition and toxicity of the low molecular mass fraction, and the fact that the toxicological database is limited to the 40–65 grade and does not cover all grades of calcium lignosulphonate shipped...... as previous cargoes, the EFSA Panel on Contaminants in the Food Chain (CONTAM Panel) concluded that calcium lignosulphonate does not meet the criteria for acceptability as a previous cargo. Only food-grade ammonium sulphate meets the criteria for acceptability as a previous cargo due to uncertainties about...

  5. A STATISTICAL APPROACH FOR DERIVING KEY NFC EVALUATION CRITERIA

    Directory of Open Access Journals (Sweden)

    S.K. KIM

    2014-02-01

    As a result of analyzing the weight of evaluation criteria with the sample of nuclear power experts and the general public, both sides recognized safety as the most important evaluation criterion, and the social factors such as public acceptance appeared to be ranked as more important evaluation criteria by the nuclear energy experts than the general public.

  6. Defining criteria for good environmental journalism and testing their applicability: An environmental news review as a first step to more evidence based environmental science reporting.

    Science.gov (United States)

    Rögener, Wiebke; Wormer, Holger

    2017-05-01

    While the quality of environmental science journalism has been the subject of much debate, a widely accepted benchmark to assess the quality of coverage of environmental topics is missing so far. Therefore, we have developed a set of defined criteria of environmental reporting. This instrument and its applicability are tested in a newly established monitoring project for the assessment of pieces on environmental issues, which refer to scientific sources and therefore can be regarded as a special field of science journalism. The quality is assessed in a kind of journalistic peer review. We describe the systematic development of criteria, which might also be a model procedure for other fields of science reporting. Furthermore, we present results from the monitoring of 50 environmental reports in German media. According to these preliminary data, the lack of context and the deficient elucidation of the evidence pose major problems in environmental reporting.

  7. Acceptance-based behavior therapy to promote HIV medication adherence.

    Science.gov (United States)

    Moitra, Ethan; Herbert, James D; Forman, Evan M

    2011-12-01

    A significant number of adults with HIV in the USA do not maintain adherence to highly active antiretroviral therapy (HAART) at adequate levels. Although traditional cognitive behavioral interventions have shown promise in promoting HAART adherence, acceptance-based behavior therapy (ABBT) may be particularly useful in this population. ABBT has the potential to overcome common avoidance-based barriers associated with poor adherence, including denial of various illness-related factors and avoidance of stigmatization. We describe the rationale for promoting psychological and behavioral acceptance in HIV-positive populations; outline an ABBT to promote HAART adherence targeting primary care patients from urban, minority, low socioeconomic backgrounds; and report preliminary qualitative observations of treatment feasibility and acceptability.

  8. Extended BRS algebra and color confinement criteria

    International Nuclear Information System (INIS)

    Shintani, Meiun.

    1983-09-01

    We examine the color-confinement criteria proposed by Kugo and Ojima. With the use of the extended BRS symmetry and the Nakanishi's theorem, we look for the representations of the BRS algebra compatible with the first condition of their criteria (the K-O condition) and then ask whether or not they are physically acceptable. As a result, the quartet mechanism does not work, and the K-O condition is not regarded as a confinement condition. (author)

  9. Study of Validity Criteria for Radionuclide-Analysis of Low- and Intermediate-Level Radioactive Waste

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Ji Uk; Baek, Hyun Suk; Jeong, Sung Yeop [Sungwoo E and T Co., Hanam (Korea, Republic of); Shin, Seung Kyu [Korea Radioactive waste Management Corporation, Gyeongju (Korea, Republic of)

    2013-05-15

    Literature survey on the deviation of the measuring equipment and statistical analysis on the measured data of domestic LILW were performed in order to set evaluation criteria quantitatively when comparing the result of each test and inspections. This study provided opportunity to increase credibility and re-assure validity of Waste Acceptance Criteria (WAC). Through the statistical analysis for deviation of measurement by comparing repository inspection with generator self-test, the quantitative acceptance criteria were set depending on specific activity of Co-60 and Cs-137. The acceptance criteria is a relative bias of KRMC result to generator result and set from low 50 % to high 150 % for Co-60, from low 30 % to 250 % for Cs-137. In this study, because the statistical analysis results of the waste drum assay are not enough representing whole range specified at WAC, an additional research that include characteristic analysis of LILW generated other birthplace should be done.

  10. Review of the scientific and technical criteria for the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    1984-01-01

    The panel has evaluated the scientific and technical adequacy of work being done on the Waste Isolation Pilot Plant (WIPP) project to satisfy the charge to the panel set out in Chapter 1. The panel concluded that the scientific work has been carried out with a high degree of professional competence. The panel notes that the geology revealed by shaft sinking and excavation of drifts and the preliminary measurements generally confirm the geologic expectations derived from surface explorations and boreholes. The purity and volume of the salt, the absence of brine pockets at the repository horizon in the areas excavated, the absence of breccia pipes and of toxic gases, and the nearly horizontal bedding of the salt indicate that a repository can be constructed that will meet the geologic criteria for site selection. Thus, the important issues about the geology at the site have been resolved, but there remain some issues about the hydrology and design of the facility that should be resolved before large-scale transuranic (TRU) waste emplacement begins. The panel's conclusions and recommendations regarding the following studies are presented: site selection and characterization; in-situ tests and experiments; waste acceptance criteria; design and construction of underground facilities; and performance assessment. 65 references, 17 figures, 3 tables

  11. Criteria for decommissioning

    International Nuclear Information System (INIS)

    Ricci, P.F.

    1988-01-01

    In this paper the authors describe three risk acceptability criteria as parts of a strategy to clean up decommissioned facilities, related to both the status quo and to a variety of alternative technical clean-up options. The acceptability of risk is a consideration that must enter into any decision to establish when a site is properly decommissioned. To do so, both the corporate and public aspects of the acceptability issue must be considered. The reasons for discussion the acceptability of risk are to: Legitimize the process for making cleanup decisions; Determine who is at risk, who benefits, and who bears the costs of site cleanup, for each specific cleanup option, including the do nothing option; Establish those factors that, taken as a whole, determine measures of acceptability; Determine chemical-specific aggregate and individual risk levels; and Establish levels for cleanup. The choice of these reasons is pragmatic. The method consistent with these factors is risk-risk-effectiveness: the level of cleanup must be consistent with the foreseeable use of the site and budget constraints. Natural background contamination is the level below which further cleanup is generally inefficient. Case-by-case departures from natural background are to be considered depending on demonstrated risk. For example, a hot spot is obviously a prima facie exception, but should be rebuttable. Rebuttability means that, through consensus, the ''hot spot'' is shown not to be associated with exposure

  12. Development of very low-level radioactive waste sequestration process criteria

    Energy Technology Data Exchange (ETDEWEB)

    Chan, N.; Wong, P., E-mail: nicholas.chan@cnl.ca [Canadian Nuclear Laboratories, Chalk River, Ontario (Canada)

    2015-12-15

    Segregating radioactive waste at the source and reclassifying radioactive waste to lower waste classes are the key activities to reduce the environmental footprint and long-term liability. In the Canadian Standards Association's radioactive waste classification system, there are 2 sub-classes within low-level radioactive waste: very short-lived radioactive waste and very low-level radioactive waste (VLLW). VLLW has a low hazard potential but is above the Canadian unconditional clearance criteria as set out in Schedule 2 of Nuclear Substances and Devices Regulations. Long-term waste management facilities for VLLW do not require a high degree of containment and isolation. In general, a relatively low-cost near-surface facility with limited regulatory control is suitable for VLLW. At Canadian Nuclear Laboratories' Chalk River Laboratories site an initiative, VLLW Sequestration, was implemented in 2013 to set aside potential VLLW for temporary storage and to be later dispositioned in the planned VLLW facility. As of May 2015, a total of 236m{sup 3} resulting in approximately $1.1 million in total savings have been sequestered. One of the main hurdles in implementing VLLW Sequestration is the development of process criteria. Waste Acceptance Criteria (WAC) are used as a guide or as requirements for determining whether waste is accepted by the waste management facility. Establishment of the process criteria ensures that segregated waste materials have a high likelihood to meet the VLLW WAC and be accepted into the planned VLLW facility. This paper outlines the challenges and various factors which were considered in the development of interim process criteria. (author)

  13. Environmental risk assessment: its contribution to criteria development for HLW disposal

    International Nuclear Information System (INIS)

    Smith, G.M.; Little, R.H.; Watkins, B.M.

    1999-01-01

    Principles for radioactive waste management have been provided by the International Atomic Energy Agency in Safety Series No.111-F, which was published in 1995. This has been a major step forward in the process of achieving acceptance for proposals for disposal of radioactive waste, for example, for High Level Waste disposal in deep repositories. However, these principles have still to be interpreted and developed into practical radiation protection criteria. Without prejudicing final judgements on the acceptability of waste proposals, an important aspect is that practical demonstration of compliance (or the opposite) with these criteria must be possible. One of the IAEA principles requires that radioactive waste shall be managed in such a way as to provide an acceptable level of protection of the environment. There has been and continues to be considerable debate as to how to demonstrate compliance with such a principle. This paper briefly reviews the current status and considers how experience in other areas of environmental protection could contribute to criteria development for HLW disposal

  14. Plugging criteria for WWER SG tubes

    Energy Technology Data Exchange (ETDEWEB)

    Papp, L.; Wilam, M. [Vitkovice NPP Services (Switzerland); Herman, M. [Vuje, Trnava (Slovakia)

    1997-12-31

    At operated Czech and Slovak nuclear power plants the 80 % criteria for crack or other bulk defect depth is used for steam generator heat exchanging tubes plugging. This criteria was accepted as the recommendation of designer of WWER steam generators. Verification of this criteria was the objective of experimental program performed by Vitkovice, J.S.C., UJV Rez, J.S.C. and Vuje Trnava, J.S.C .. Within this program the following factors were studied: (1) Influence of secondary water chemistry on defects initiation and propagation, (2) Statistical evaluation of corrosion defects progression at operated SG, and (3) Determination of critical pressure for tube rupture as a function of eddy current indications. In this presentation items (2) and (3) are considered.

  15. Plugging criteria for WWER SG tubes

    Energy Technology Data Exchange (ETDEWEB)

    Papp, L; Wilam, M [Vitkovice NPP Services (Switzerland); Herman, M [Vuje, Trnava (Slovakia)

    1998-12-31

    At operated Czech and Slovak nuclear power plants the 80 % criteria for crack or other bulk defect depth is used for steam generator heat exchanging tubes plugging. This criteria was accepted as the recommendation of designer of WWER steam generators. Verification of this criteria was the objective of experimental program performed by Vitkovice, J.S.C., UJV Rez, J.S.C. and Vuje Trnava, J.S.C .. Within this program the following factors were studied: (1) Influence of secondary water chemistry on defects initiation and propagation, (2) Statistical evaluation of corrosion defects progression at operated SG, and (3) Determination of critical pressure for tube rupture as a function of eddy current indications. In this presentation items (2) and (3) are considered.

  16. A new type of headache, headache associated with airplane travel: preliminary diagnostic criteria and possible mechanisms of aetiopathogenesis.

    Science.gov (United States)

    Berilgen, M Said; Müngen, Bulent

    2011-09-01

    In recent years, there has been an increase in the reports indicating a form of headache that occurs during commercial aircraft travel. This headache, called airplane headache by some authors, is believed to be a new type of headache. The headache has very specific characteristics and all of the cases exhibited very stereotypical symptoms. The headache starts suddenly during the ascent and/or descent of the commercial aircraft. It has a mean duration of 20 minutes, which is usually unilateral and commonly localized to periorbital region. The headache is described to be severe, and has a stabbing or jabbing nature, and generally subsides in a short time. In some cases, an organic cause can be identified whereas in others no organic pathology could be found. We described the clinical features of 22 cases who suffered from a headache that occurred during airplane travel. We examined other cases with similar features reported in the literature and proposed preliminary diagnostic criteria for this new form of headache. We also discussed the possible patholophysiological mechanisms that may cause this headache.

  17. Acceptability and feasibility of self-help Cognitive Remediation Therapy for anorexia nervosa delivered in collaboration with carers: a qualitative preliminary evaluation study.

    Science.gov (United States)

    Lang, Katie; Treasure, Janet; Tchanturia, Kate

    2015-02-28

    Anorexia nervosa (AN) is an eating disorder without a recommended first-line treatment. Cognitive Remediation Therapy (CRT) is showing great promise in helping patients reduce cognitive inflexibility and excessive detail focus, thinking styles that could make engaging in psychological therapies difficult. CRT has shown to be effective, feasible and acceptable in both individual and group formats, and positive qualitative data has been gathered from both service users and clinicians. The aim of the current study was to assess the use of CRT as a self-help treatment for individuals with AN delivered in collaboration with carers. Six families underwent a six-week self-help CRT intervention. Feedback was gathered from qualitative interviews and analysed using thematic analysis. Neuropsychological outcomes were also collected. Participant feedback regarding the intervention was generally positive, with participants describing a number of benefits such as it creating a space for families to spend time together outside of the eating disorder, acting as a 'gateway' for more emotional work and helping participants to gain insight into their cognitive profiles. These preliminary findings suggest that self-help CRT delivered in collaboration with carers is an acceptable form of treatment, and adds to the growing literature supporting CRT for AN. Copyright © 2014 Elsevier Ireland Ltd. All rights reserved.

  18. [Organization of socially acceptable working hours in nursing].

    Science.gov (United States)

    Büssing, A; Glaser, J

    1994-05-01

    Three dimensions in the structure of the working hour system of nurses, rendering them socially acceptable, are becoming important: duration of the working day, the time of day which is being worked and the distribution of working hours. The latter two are of particular importance because flexible shift is becoming the dominant pattern in nursing. Six indicators are discussed as criteria for social acceptability: security of employment which includes access to the labour-market, level of income, health, opportunity for social relationships, social participation, and autonomy. Responses of 297 nurses in one General Hospital taking part in a study, were analysed to examine empirically the concept of 'socially acceptable structure of the working hours'. Ideal and factual patterns are considered first. Secondly aspects of autonomy are considered and the way this depends on time, thirdly the criteria used to define 'social acceptability' are examined for validity. Results show firstly the cross contrast between the hospital's expectation and the nurses' wishes with regard to working hours. Furthermore, inspite of the demand for flexibility, staff have very little choice and there is little sign of joint decision making. Thirdly results show that health, interpersonal and social aspects are of special importance and that, correspondingly, in the view of nurses, financial and practical problems are of lesser importance in their every day life.

  19. Criteria for the prioritization of public health interventions for climate-sensitive vector-borne diseases in Quebec.

    Directory of Open Access Journals (Sweden)

    Valerie Hongoh

    Full Text Available Prioritizing resources for optimal responses to an ever growing list of existing and emerging infectious diseases represents an important challenge to public health. In the context of climate change, there is increasing anticipated variability in the occurrence of infectious diseases, notably climate-sensitive vector-borne diseases. An essential step in prioritizing efforts is to identify what considerations and concerns to take into account to guide decisions and thus set disease priorities. This study was designed to perform a comprehensive review of criteria for vector-borne disease prioritization, assess their applicability in a context of climate change with a diverse cross-section of stakeholders in order to produce a baseline list of considerations to use in this decision-making context. Differences in stakeholder choices were examined with regards to prioritization of these criteria for research, surveillance and disease prevention and control objectives. A preliminary list of criteria was identified following a review of the literature. Discussions with stakeholders were held to consolidate and validate this list of criteria and examine their effects on disease prioritization. After this validation phase, a total of 21 criteria were retained. A pilot vector-borne disease prioritization exercise was conducted using PROMETHEE to examine the effects of the retained criteria on prioritization in different intervention domains. Overall, concerns expressed by stakeholders for prioritization were well aligned with categories of criteria identified in previous prioritization studies. Weighting by category was consistent between stakeholders overall, though some significant differences were found between public health and non-public health stakeholders. From this exercise, a general model for climate-sensitive vector-borne disease prioritization has been developed that can be used as a starting point for further public health prioritization

  20. Criteria for the prioritization of public health interventions for climate-sensitive vector-borne diseases in Quebec.

    Science.gov (United States)

    Hongoh, Valerie; Gosselin, Pierre; Michel, Pascal; Ravel, André; Waaub, Jean-Philippe; Campagna, Céline; Samoura, Karim

    2017-01-01

    Prioritizing resources for optimal responses to an ever growing list of existing and emerging infectious diseases represents an important challenge to public health. In the context of climate change, there is increasing anticipated variability in the occurrence of infectious diseases, notably climate-sensitive vector-borne diseases. An essential step in prioritizing efforts is to identify what considerations and concerns to take into account to guide decisions and thus set disease priorities. This study was designed to perform a comprehensive review of criteria for vector-borne disease prioritization, assess their applicability in a context of climate change with a diverse cross-section of stakeholders in order to produce a baseline list of considerations to use in this decision-making context. Differences in stakeholder choices were examined with regards to prioritization of these criteria for research, surveillance and disease prevention and control objectives. A preliminary list of criteria was identified following a review of the literature. Discussions with stakeholders were held to consolidate and validate this list of criteria and examine their effects on disease prioritization. After this validation phase, a total of 21 criteria were retained. A pilot vector-borne disease prioritization exercise was conducted using PROMETHEE to examine the effects of the retained criteria on prioritization in different intervention domains. Overall, concerns expressed by stakeholders for prioritization were well aligned with categories of criteria identified in previous prioritization studies. Weighting by category was consistent between stakeholders overall, though some significant differences were found between public health and non-public health stakeholders. From this exercise, a general model for climate-sensitive vector-borne disease prioritization has been developed that can be used as a starting point for further public health prioritization exercises relating to

  1. Selection criteria of residents for residency programs in Kuwait.

    Science.gov (United States)

    Marwan, Yousef; Ayed, Adel

    2013-01-19

    In Kuwait, 21 residency training programs were offered in the year 2011; however, no data is available regarding the criteria of selecting residents for these programs. This study aims to provide information about the importance of these criteria. A self-administered questionnaire was used to collect data from members (e.g. chairmen, directors, assistants …etc.) of residency programs in Kuwait. A total of 108 members were invited to participate. They were asked to rate the importance level (scale from 1 to 5) of criteria that may affect the acceptance of an applicant to their residency programs. Average scores were calculated for each criterion. Of the 108 members invited to participate, only 12 (11.1%) declined to participate. Interview performance was ranked as the most important criteria for selecting residents (average score: 4.63/5.00), followed by grade point average (average score: 3.78/5.00) and honors during medical school (average score: 3.67/5.00). On the other hand, receiving disciplinary action during medical school and failure in a required clerkship were considered as the most concerning among other criteria used to reject applicants (average scores: 3.83/5.00 and 3.54/5.00 respectively). Minor differences regarding the importance level of each criterion were noted across different programs. This study provided general information about the criteria that are used to accept/reject applicants to residency programs in Kuwait. Future studies should be conducted to investigate each criterion individually, and to assess if these criteria are related to residents' success during their training.

  2. Waste acceptance product specifications for vitrified high-level waste forms

    International Nuclear Information System (INIS)

    Applewhite-Ramsey, A.; Sproull, J.F.

    1993-01-01

    The Nuclear Waste Policy Act of 1982 mandated that all high-level waste (HLW) be sent to a federal geologic repository for permanent disposal. DOE published the Environmental Assessment in 1982 which identified borosilicate glass as the chosen HLW form. 1 In 1985 the Department of Energy instituted a Waste Acceptance Process to assure that DWPF glass waste forms would be acceptable to such a repository. This assurance was important since production of waste forms will precede repository construction and licensing. As part of this Waste Acceptance Process, the DOE Office of Civilian Radioactive Waste Management (RW) formed the Waste Acceptance Committee (WAC). The WAC included representatives from the candidate repository sites, the waste producing sites and DOE. The WAC was responsible for developing the Waste Acceptance Preliminary Specifications (WAPS) which defined the requirements the waste forms must meet to be compatible with the candidate repository geologies

  3. Project W-049H Collection System Acceptance Test

    International Nuclear Information System (INIS)

    Buckles, D.I.

    1994-01-01

    The Acceptance Test Procedure (ATP) Program for Project W-049H covers the following activities: Disposal system, Collection system, Instrumentation and control system. Each activity has its own ATP. The purpose of the ATPs is to verify that the systems have been constructed in accordance with the construction documents and to demonstrate that the systems function as required by the Project criteria. This ATP has been prepared to demonstrate that the Collection System Instrumentation functions as required by project criteria

  4. Preliminary market assessment of fluidized-bed waste-heat recovery technology

    Energy Technology Data Exchange (ETDEWEB)

    Campos, F.T.; Fey, C.L.; Grogan, P.J.; Klein, N.P.

    1980-06-01

    A preliminary assessment of fluidized-bed waste-heat recovery (FBWHR) system market potential is presented with emphasis on the factors influencing industrial acceptability. Preliminary market potential areas are identified based on the availability of waste heat. Trends in energy use are examined to see the effect they might have on these market potential areas in the future. Focus groups interviews are used to explore important factors in the industrial decision-making process. These important factors are explored quantitatively in a survey of industrial plant engineers. The survey deals with the waste-heat boiler configuration of the FBWHR system. Results indicate market acceptance of the fluidized-bed waste-heat boiler could be quite low.

  5. Measurement methodology for fulfilling of waste acceptance criteria for low and intermediate level radioactive waste in storages - 59016

    International Nuclear Information System (INIS)

    Sokcic-Kostic, M.; Langer, F.; Schultheis, R.

    2012-01-01

    Low and intermediate level radioactive waste must be sorted and treated before it can be sent to radioactive waste storage. The waste must fulfil an extensive amount of acceptance criteria (WAC) to guarantee a safe storage period. NUKEM Technologies has a broad experience with the building and management of radioactive waste treatment facilities and has developed methods and equipment to produce the waste packages and to gather all the required information. In this article we consider low and intermediate level radioactive waste excluding nuclear fuel material, even fresh fuel with low radiation. Only solid radioactive waste (RAW) will be considered. (Liquid RAW is usually processed and solidified before storage. Exception is the reprocessing of nuclear fuel.) Low and intermediate level radioactive waste has to be kept in storage facilities until isotopes are decayed sufficiently and the waste can be released. The storage has to fulfil certain conditions regarding the possible radiological impact and the possible chemical impact on the environment. With the inventory of nuclear waste characterised, the radiological impact can be estimated. RAW mainly originates from the operation of nuclear power plants. A small amount comes from reprocessing installations or from research entities. Chemical safety aspects are of qualitative nature, excluding substances in whole but not compared to limit values. Therefore they have minor influence on the storage conditions. Hereby corrosion and immobilisation of the waste play important roles. The storage concept assumes that the waste will be released if the radioactivity has decreased to an acceptable level. NUKEM Technologies has been specialised on collecting all data needed for the fulfilling of waste acceptance criteria (WAC). The classification as low or intermediate level waste is made on base of surface dose rate of the waste package as well as on the mass specific beta activity. Low level waste must not include isotopes

  6. Multi criteria analysis in the renewable energy industry

    CERN Document Server

    San Cristóbal Mateo, José Ramón

    2012-01-01

    Decision makers in the Renewable Energy sector face an increasingly complex social, economic, technological, and environmental scenario in their decision process. Different groups of decision-makers become involved in the process, each group bringing along different criteria therefore, policy formulation for fossil fuel substitution by Renewable Energies must be addressed in a multi-criteria context. Multi Criteria Analysis in the Renewable Energy Industry is a direct response to the increasing interest in the Renewable Energy industry which can be seen as an important remedy to many environmental problems that the world faces today. The multiplicity of criteria and the increasingly complex social, economic, technological, and environmental scenario makes multi-criteria analysis a valuable tool in the decision-making process for fossil fuel substitution. The detailed chapters explore the use of the Multi-criteria decision-making methods and how they provide valuable assistance in reaching equitable and accept...

  7. Criteria for safety-related operator actions

    International Nuclear Information System (INIS)

    Gray, L.H.; Haas, P.M.

    1983-01-01

    The Safety-Related Operator Actions (SROA) Program was designed to provide information and data for use by NRC in assessing the performance of nuclear power plant (NPP) control room operators in responding to abnormal/emergency events. The primary effort involved collection and assessment of data from simulator training exercises and from historical records of abnormal/emergency events that have occurred in operating plants (field data). These data can be used to develop criteria for acceptability of the use of manual operator action for safety-related functions. Development of criteria for safety-related operator actions are considered

  8. Preliminary Study Intended for the Application of the INPRO Methodology in the area of Infrastructure (Public Acceptance) for the Case of Mexico

    International Nuclear Information System (INIS)

    Heredia, R.; Puente Espel, F.

    2016-01-01

    The pronounced concern about climate change as seen in the past COP21 Conference, the increasing energy demand worldwide, and the importance of energy security are among the main issues within the pursuit of a sustainable development. In a sustainable and diverse energy portfolio, the goals focus on providing clean, carbon free, reliable and affordable electricity. Nuclear energy is one of the most efficient energy sources; considering the energy produced per amount of fuel, one of the least climate dependent sources and a clean energy source. Nuclear energy is a sustainable energy source. But the sustainability of nuclear energy systems is questioned by the public, as well as by some decision makers, mainly due to concerns related to safety, nuclear waste disposal, and the proliferation of nuclear weapons. The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO), from the International Atomic Energy Agency (IAEA), was established to assist and guarantee that in order to meet the energy needs of the 21st century through a sustainable approach, nuclear energy is available. In this line, INPRO in close cooperation with Member States work to understand the future development of nuclear energy systems from a national, regional and global perspective, as well as to comprehend the role of innovation in technologies and institutional arrangements in support of this development. Through one of INPRO's main areas, Sustainability Assessment and Strategies, INPRO supports Member States in developing national long-range sustainable nuclear energy strategies and related deployment decision-making throughout the application of the INPRO Methodology. This paper presents a preliminary study intended for the application of the INPRO Methodology in the area of Infrastructure, Public Acceptance, for the case of Mexico. Mexico's current nuclear power programme is small; integrated by a nuclear power plant (NPP) with two reactors. In the scenario of a

  9. 77 FR 5506 - ORPC Maine, LLC; Notice of Preliminary Permit Application Accepted for Filing and Soliciting...

    Science.gov (United States)

    2012-02-03

    ... preliminary permit, pursuant to section 4(f) of the Federal Power Act (FPA), proposing to study the feasibility of the Treat Island Tidal Energy Project to be located in Passamaquoddy Bay, between the Town of Eastport and Treat Island, Washington County, Maine. The sole purpose of a preliminary permit, if issued...

  10. The leak before break criteria, requirements and implications

    International Nuclear Information System (INIS)

    Martinez M, E.

    1992-05-01

    Inside this work a general balance is made on the Leak before break approach (LBB), like they are the history and licensing, those limitations, the acceptance criteria of the LBB, the current state of the regulatory development and the current state of it application in countries like E.U.A, Germany, Canada, Italy and France. Everything it with the purpose of evaluating the opportunities that offers the LBB criteria for it possible application in Mexico. (Author)

  11. Preliminary seismic design of dynamically coupled structural systems

    International Nuclear Information System (INIS)

    Pal, N.; Dalcher, A.W.; Gluck, R.

    1977-01-01

    In this paper, the analysis criteria for coupling and decoupling, which are most commonly used in nuclear design practice, are briefly reviewed and a procedure outlined and demonstrated with examples. Next, a criterion judged to be practical for preliminary seismic design purposes is defined. Subsequently, a technique compatible with this criterion is suggested. A few examples are presented to test the proposed procedure for preliminary seismic design purposes. Limitations of the procedure are also discussed and finally, the more important conclusions are summarized

  12. Technical evaluation of draft ANSI Standard N13.30, ''performance criteria for radiobioassay''

    International Nuclear Information System (INIS)

    MacLellan, J.A.; Traub, R.J.

    1986-03-01

    The Pacific Northwest Laboratory (PNL) is conducting a research program to evaluate the appropriateness of criteria in the ANSI draft Standard N13.30, ''Performance Criteria for Radiobioassay.'' The evaluation has progressed parallel with the preparation of the Standard by evaluating the performance of existing bioassay laboratories against the criteria specified. Recommendations for revision of the Standard and implementation of a testing/accreditation program have been formulated based on study results. The current performance testing program includes both in-vivo counting and in-vitro sample measurements. Test criteria specified in the Standard include relative bias, relative precision, and acceptable minimum detectable activity (AMDA). Results to date have indicated that the acceptance criteria in the Standard are appropriate for the existing state of the industry and are achievable by a majority of the participating laboratories. Specific conclusions are that the AMDA criteria are most difficult for the laboratories to achieve; the relative bias criterion is second in difficulty, and the precision criterion presents no problem for the laboratories; most of the participating laboratories can meet the Standard; and failure rates may decrease as the laboratories become more knowledgeable of the performance criteria. 3 refs., 11 figs., 6 tabs

  13. [Revision of McDonald's new diagnostic criteria for multiple sclerosis].

    Science.gov (United States)

    Wiendl, H; Kieseier, B C; Gold, R; Hohlfeld, R; Bendszus, M; Hartung, H-P

    2006-10-01

    In 2001, an international panel suggested new diagnostic criteria for multiple sclerosis (MS). These criteria integrate clinical, imaging (MRI), and paraclinical results in order to facilitate diagnosis. Since then, these so-called McDonald criteria have been broadly accepted and widely propagated. In the meantime a number of publications have dealt with the sensitivity and specificity for MS diagnosis and with implementing these new criteria in clinical practice. Based on these empirical values and newer data on MS, an international expert group recently proposed a revision of the criteria. Substantial changes affect (1) MRI criteria for the dissemination of lesions over time, (2) the role of spinal cord lesions in the MRI and (3) diagnosis of primary progressive MS. In this article we present recent experiences with the McDonald and revised criteria.

  14. Acceptance test procedure for High Pressure Water Jet System

    International Nuclear Information System (INIS)

    Crystal, J.B.

    1995-01-01

    The overall objective of the acceptance test is to demonstrate a combined system. This includes associated tools and equipment necessary to perform cleaning in the 105 K East Basin (KE) for achieving optimum reduction in the level of contamination/dose rate on canisters prior to removal from the KE Basin and subsequent packaging for disposal. Acceptance tests shall include necessary hardware to achieve acceptance of the cleaning phase of canisters. This acceptance test procedure will define the acceptance testing criteria of the high pressure water jet cleaning fixture. The focus of this procedure will be to provide guidelines and instructions to control, evaluate and document the acceptance testing for cleaning effectiveness and method(s) of removing the contaminated surface layer from the canister presently identified in KE Basin. Additionally, the desired result of the acceptance test will be to deliver to K Basins a thoroughly tested and proven system for underwater decontamination and dose reduction. This report discusses the acceptance test procedure for the High Pressure Water Jet

  15. Retrospective analysis of 'gamma distribution' based IMRT QA criteria

    International Nuclear Information System (INIS)

    Wen, C.; Chappell, R.A.

    2010-01-01

    Full text: IMRT has been implemented into clinical practice at Royal Hobart Hospital (RHH) since mid 2006 for treating patients with Head and Neck (H and N) or prostate tumours. A local quality assurance (QA) acceptance criteria based on 'gamma distribution' for approving IMRT plan was developed and implemented in early 2007. A retrospective analysis of such criteria over 194 clinical cases will be presented. The RHH IMRT criteria was established with assumption that gamma distribution obtained through inter-comparison of 2 D dose maps between planned and delivered was governed by a positive-hail' normal distribution. A commercial system-MapCheck was used for 2 D dose map comparison with a built-in gamma analysis tool. Gamma distribution histogram was generated and recorded for all cases. By retrospectively analysing those distributions using curve fitting technique, a statistical gamma distribution can be obtained and evaluated. This analytical result can be used for future IMRT planing and treatment delivery. The analyses indicate that gamma distribution obtained through MapCheckTM is well under the normal distribution, particularly for prostate cases. The applied pass/fail criteria is not overly sensitive to identify 'false fails' but can be further tighten-up for smaller field while for larger field found in both H and N and prostate cases, the criteria was correctly applied. Non-uniform distribution of detectors in MapCheck and experience level of planners are two major factors to variation in gamma distribution among clinical cases. This criteria derived from clinical statistics is superior and more accurate than single-valued criteria for lMRT QA acceptance procedure. (author)

  16. Acceptable Knowledge Summary Report for Waste Stream: SR-T001-221F-HET/Drums

    International Nuclear Information System (INIS)

    Lunsford, G.F.

    1999-01-01

    This report is fully responsive to the requirements of Section 4.0 ''Acceptable Knowledge'' from the WIPP Transuranic Waste Characterization Quality Assurance Plan, CAO-94-1010, and provides a sound, (and auditable) characterization that satisfies the WIPP criteria for Acceptable Knowledge

  17. Mark II containment lead plant program load evaluation and acceptance criteria

    International Nuclear Information System (INIS)

    1978-10-01

    The report, prepared by the Office of Nuclear Reactor Regulation, addresses the portion of the Mark II owner's program that provides a generic methodology for establishing design basis LOCA and safety relief valve loads for the lead Mark II facilities (Zimmer, Shoreham, and LaSalle), i.e., the lead plant program. The report includes an evaluation of the Mark II owner's load methodology, a description of load methodologies that we find acceptable for use in the individual plant unique assessments, and the basis for the stated conclusions

  18. A preliminary evaluation of Acceptance and Commitment Therapy (ACT) training in Sierra Leone

    OpenAIRE

    Stewart, Corinna; White, Ross G.; Ebert, Beate; Mays, Iain; Nardozzi, Jennifer; Bockarie, Hannah

    2016-01-01

    Concerted efforts are being made to scale up psychological interventions in low and middle-income countries (LMIC). Acceptance and Commitment Therapy (ACT) aims to reduce psychological inflexibility and has been shown to be effective for treating a range of mental health difficulties. ACT training workshops have been shown to reduce the psychological inflexibility of individuals receiving training. There is a dearth of research investigating the acceptability and potential efficacy of ACT in ...

  19. Early Site Permit Demonstration Program: Regulatory criteria evaluation report

    International Nuclear Information System (INIS)

    1993-03-01

    The primary objective of the Early Site Plan Demonstration Program (ESPDP) is to demonstrate successfully the use of 10CFR52 to obtain ESPs for one or more US sites for one (or more) ALWR nuclear power plants. It is anticipated that preparation of the ESP application and interaction with NRC during the application review process will result not only in an ESP for the applicant(s) but also in the development of criteria and definition of processes, setting the precedent that facilitates ESPs for subsequent ESP applications. Because siting regulatory processes and acceptance criteria are contained in over 100 separate documents, comprehensive licensing and technical reviews were performed to establish whether the requirements and documentation are self-consistent, whether the acceptance criteria are sufficiently well-defined and clear, and whether the licensing process leading to the issuance of an ESP is unambiguously specified. This document provides appendices C and D of this report. Appendix C contains data from the licensing and technical reviews; Appendix D contains technology toolkit data sheets

  20. 77 FR 66607 - Northern Wasco County People's Utility District; Notice of Preliminary Permit Application...

    Science.gov (United States)

    2012-11-06

    ... County People's Utility District; Notice of Preliminary Permit Application Accepted for Filing and... County People's Utility District (Northern Wasco) filed an application for a preliminary permit, pursuant...; (2) two five-foot by five-foot sluice gates connecting the new intake channel structure to the...

  1. Relationship between colorimetric (instrumental) evaluation and consumer-defined beef colour acceptability.

    Science.gov (United States)

    Holman, Benjamin W B; Mao, Yanwei; Coombs, Cassius E O; van de Ven, Remy J; Hopkins, David L

    2016-11-01

    The relationship between instrumental colorimetric values (L*, a*, b*, the ratio of reflectance at 630nm and 580nm) and consumer perception of acceptable beef colour was evaluated using a web-based survey and standardised photographs of beef m. longissimus lumborum with known colorimetrics. Only L* and b* were found to relate to average consumer opinions of beef colour acceptability. Respondent nationality was also identified as a source of variation in beef colour acceptability score. Although this is a preliminary study with the findings necessitating additional investigation, these results suggest L* and b* as candidates for developing instrumental thresholds for consumer beef colour expectations. Crown Copyright © 2016. Published by Elsevier Ltd. All rights reserved.

  2. Waste acceptance product specifications for vitrified high-level waste forms

    International Nuclear Information System (INIS)

    Applewhite-Ramsey, A.; Sproull, J.F.

    1994-01-01

    The Department of Energy (DOE) Office of Environmental Restoration and Waste Management (EM) has developed Waste Acceptance Product Specifications (EM-WAPS). The EM-WAPS will be the basis for defining product acceptance criteria compatible with the requirements of the Civilian Radioactive Waste Management System (CRWMS). The relationship between the EM-WAPS and the CRWMS Systems Requirements document (WA-SRD) will be discussed. The impact of the EM-WAPS on the Savannah River Sit (SRS) Defense Waste Processing Facility's (DWPF) Waste Acceptance Program, Waste Qualification Run planning, and startup schedule will also be reported. 14 refs., 2 tabs

  3. Considerations for developing seismic design criteria for nuclear waste storage repositories

    International Nuclear Information System (INIS)

    Owen, G.N.; Yanev, P.I.; Scholl, R.E.

    1980-04-01

    The function of seismic design criteria is to reduce the potential for hazards that may arise during various stages of the repository life. During the operational phase, the major concern is with the possible effects of earthquakes on surface facilities, underground facilities, and equipment. During the decommissioned phase, the major concern is with the potential effects of earthquakes on the geologic formation, which may result in a reduction in isolation capacity. Existing standards and guides or criteria used for the static and seismic design of licensed nuclear facilities were reviewed and evaluated for their applicability to repository design. This report is directed mainly toward the development of seismic design criteria for the underground structures of repositories. An initial step in the development of seismic design criteria for the underground structures of repositories is the development of performance criteria, or minimum standards of acceptable behavior. A number of possible damage modes are identified for the operating phase of the repository; however, no damage modes are foreseen that would perturb the long-term function of the repository, except for the possibility of increased permeability within the rock mass. Subsequent steps in formulating acceptable seismic design criteria for the underground structures involve the quantification of the design process. The report discusses the necessity of specifying the form of ground motion that would be needed for seismic analysis and the procedures that may be used for making ground motion predictions. Further discussions outline what is needed for analysis, including rock properties, failure criteria, modeling techniques, seismic hardening criteria for the host rock mass, and probabilistic considerations

  4. FFTBM and primary pressure acceptance criterion

    International Nuclear Information System (INIS)

    Prosek, A.

    2004-01-01

    When thermalhydraulic computer codes are used for simulation in the area of nuclear engineering the question is how to conduct an objective comparison between the code calculation and measured data. To answer this the fast Fourier transform based method (FFTBM) was developed. When the FFTBM method was developed the acceptance criteria for primary pressure and total accuracy were set. In the recent study the FFTBM method was used for accuracy quantification of RD-14M large LOCA test B9401 calculations. The blind accuracy analysis indicated good total accuracy while the primary pressure criterion was not fulfilled. The objective of the study was therefore to investigate the reasons for not fulfilling the primary pressure acceptance criterion and the applicability of the criterion to experimental facilities simulating heavy water reactor. The results of the open quantitative analysis showed that sensitivity analysis for influence parameters provide sufficient information to judge in which calculation the accuracy of primary pressure is acceptable. (author)

  5. Qualification criteria to certify a package for air transport of plutonium

    International Nuclear Information System (INIS)

    1977-12-01

    The document describes qualification criteria developed by the U.S. Nuclear Regulatory Commission to certify a package for air transport of plutonium. Included in the document is a discussion of aircraft accident conditions and a summary of the technical basis for the qualification criteria. The criteria require prototype packages to be subjected to various individual and sequential tests that simulate the conditions produced in severe aircraft accidents. Specific post-test acceptance standards are prescribed for each of the three safety functions of a package. The qualification criteria also prescribe certain operational controls to be exercised during transport

  6. Clinical audit: Development of the criteria of good practices

    International Nuclear Information System (INIS)

    Soimakallio, S.; Alanen, A.; Jaervinen, H.; Ahonen, A.; Ceder, K.; Lyyra-Laitinen, T.; Paunio, M.; Sinervo, T.; Wigren, T.

    2011-01-01

    Clinical audit is a systematic review of the procedures in order to improve the quality and the outcome of patient care, whereby the procedures are examined against agreed standards for good medical Radiological procedures. The criteria of good procedures (i.e. the good practice) are thus the cornerstones for development of clinical audits: these should be the basis of assessments regardless of the type of the audit-external, internal, comprehensive or partial. A lot of criteria for good practices are available through the recommendations and publications by international and national professional societies and other relevant organisations. For practical use in clinical audits, the criteria need to be compiled, sorted out and agreed on for the particular aims of an audit (comprehensive or partial, external or internal). The national professional and scientific societies can provide valuable contribution to this development. For examination-or treatment-specific criteria- preliminary consensus needs to be obtained with the help of clinical experts, while clinical audits can be useful as a benchmarking tool to improve the criteria. (authors)

  7. A Statistical Approach for Deriving Key NFC Evaluation Criteria

    Energy Technology Data Exchange (ETDEWEB)

    Kim, S. K; Kang, G. B.; Ko, W. I [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Young, S. R.; Gao, R. X. [Univ. of Science and Technology, Daejeon (Korea, Republic of)

    2014-02-15

    This study suggests 5 evaluation criteria (safety and technology, environmental impact, economic feasibility, social factors, and institutional factors) and 24 evaluation indicators for a NFC (nuclear fuel cycle) derived using factor analysis. To do so, a survey using 1 on 1 interview was given to nuclear energy experts and local residents who live near nuclear power plants. In addition, by conducting a factor analysis, homogeneous evaluation indicators were grouped with the same evaluation criteria, and unnecessary evaluation criteria and evaluation indicators were dropped out. As a result of analyzing the weight of evaluation criteria with the sample of nuclear power experts and the general public, both sides recognized safety as the most important evaluation criterion, and the social factors such as public acceptance appeared to be ranked as more important evaluation criteria by the nuclear energy experts than the general public.

  8. A Statistical Approach for Deriving Key NFC Evaluation Criteria

    International Nuclear Information System (INIS)

    Kim, S. K; Kang, G. B.; Ko, W. I; Young, S. R.; Gao, R. X.

    2014-01-01

    This study suggests 5 evaluation criteria (safety and technology, environmental impact, economic feasibility, social factors, and institutional factors) and 24 evaluation indicators for a NFC (nuclear fuel cycle) derived using factor analysis. To do so, a survey using 1 on 1 interview was given to nuclear energy experts and local residents who live near nuclear power plants. In addition, by conducting a factor analysis, homogeneous evaluation indicators were grouped with the same evaluation criteria, and unnecessary evaluation criteria and evaluation indicators were dropped out. As a result of analyzing the weight of evaluation criteria with the sample of nuclear power experts and the general public, both sides recognized safety as the most important evaluation criterion, and the social factors such as public acceptance appeared to be ranked as more important evaluation criteria by the nuclear energy experts than the general public

  9. A Systematic Review of Patient Acceptance of Consumer Health Information Technology

    OpenAIRE

    Karsh, BT; Or, CKL

    2009-01-01

    A systematic literature review was performed to identify variables promoting consumer health information technology (CHIT) acceptance among patients. The electronic bibliographic databases Web of Science, Business Source Elite, CINAHL, Communication and Mass Media Complete, MEDLINE, PsycArticles, and PsycInfo were searched. A cited reference search of articles meeting the inclusion criteria was also conducted to reduce misses. Fifty-two articles met the selection criteria. Among them, 94 diff...

  10. Early Site Permit Demonstration Program: Regulatory criteria evaluation report

    Energy Technology Data Exchange (ETDEWEB)

    1993-03-01

    The primary objective of the ESPDP is to demonstrate successfully the use of 10CFR52 to obtain ESPs for one or more US sites for one (or more) ALWR nuclear power plants. It is anticipated that preparation of the ESP application and interaction with NRC during the application review process will result not only in an ESP for the applicant(s) but also in the development of criteria and definition of processes, setting the precedent that facilitates ESPs for subsequent ESP applications. Because siting regulatory processes and acceptance criteria are contained in over 100 separate documents, comprehensive licensing and technical reviews were performed to establish whether the requirements and documentation are self-consistent, whether the acceptance criteria are sufficiently well-defined and clear, and whether the licensing process leading to the issuance of an ESP is unambiguously specified. The results of the technical and licensing evaluations are presented in this report. The purpose, background, and organization of the ESPDP is delineated in Section 1. Section 11 contains flowcharts defining siting application requirements, environmental report requirements, and emergency planning/preparedness requirements for ALWRS. The licensing and technical review results are presented in Section III.

  11. Early Site Permit Demonstration Program: Regulatory criteria evaluation report

    International Nuclear Information System (INIS)

    1993-03-01

    The primary objective of the ESPDP is to demonstrate successfully the use of 10CFR52 to obtain ESPs for one or more US sites for one (or more) ALWR nuclear power plants. It is anticipated that preparation of the ESP application and interaction with NRC during the application review process will result not only in an ESP for the applicant(s) but also in the development of criteria and definition of processes, setting the precedent that facilitates ESPs for subsequent ESP applications. Because siting regulatory processes and acceptance criteria are contained in over 100 separate documents, comprehensive licensing and technical reviews were performed to establish whether the requirements and documentation are self-consistent, whether the acceptance criteria are sufficiently well-defined and clear, and whether the licensing process leading to the issuance of an ESP is unambiguously specified. The results of the technical and licensing evaluations are presented in this report. The purpose, background, and organization of the ESPDP is delineated in Section 1. Section 11 contains flowcharts defining siting application requirements, environmental report requirements, and emergency planning/preparedness requirements for ALWRS. The licensing and technical review results are presented in Section III

  12. Preliminary design package for solar collector and solar pump

    Science.gov (United States)

    1978-01-01

    A solar-operated pump using an existing solar collector, for use on solar heating and cooling and hot water systems is described. Preliminary design criteria of the collector and solar-powered pump is given including: design drawings, verification plans, and hazard analysis.

  13. Acceptance test report for the Westinghouse 100 ton hydraulic trailer

    International Nuclear Information System (INIS)

    Barrett, R.A.

    1995-01-01

    The SY-101 Equipment Removal System 100 Ton Hydraulic Trailer was designed and built by KAMP Systems, Inc. Performance of the Acceptance Test Procedure at KAMP's facility in Ontario, California (termed Phase 1 in this report) was interrupted by discrepancies noted with the main hydraulic cylinder. The main cylinder was removed and sent to REMCO for repair while the trailer was sent to Lampson's facility in Pasco, Washington. The Acceptance Test Procedure was modified and performance resumed at Lampson (termed Phase 2 in this report) after receipt of the repaired cylinder. At the successful conclusion of Phase 2 testing the trailer was accepted as meeting all the performance criteria specified

  14. The role of natural analogues in safety assessment and acceptability

    International Nuclear Information System (INIS)

    Papp, Toenis

    1987-01-01

    The safety assessment must evaluate the level of safety for a repository, the confidence that can be placed on the assessment and how well the repository can meet the acceptance criteria of the society. Many of the processes and phenomena that govern the long term performance of a deep geologic repository for radioactive waste also take place in nature. To investigate these natural analogues and try to validate the models on which the safety assessment are based is a main task in the effort to build of confidence in the safety assessments. The assessment of the safety of a repository can, however, not only be based on good models. The possible role of natural analogues or natural evidence in other parts of the safety assessment is discussed. Specially with regard to - the need to demonstrate that all relevant processes have been taken into account, and that the important ones have been validated to an acceptable level for relevant parameters spans, -the definition and analysis of external scenarios for the safety assessment and for the claim that all reasonable scenarios have been addressed, - the public confidence in the long-term relevance of the acceptance criteria. (author)

  15. Uncanny valley: A preliminary study on the acceptance of Malaysian urban and rural population toward different types of robotic faces

    Science.gov (United States)

    Tay, T. T.; Low, Raymond; Loke, H. J.; Chua, Y. L.; Goh, Y. H.

    2018-04-01

    The proliferation of robotic technologies in recent years brings robots closer to humanities. There are many researches on going at various stages of development to bring robots into our homes, schools, nurseries, elderly care centres, offices, hospitals and factories. With recently developed robots having tendency to have appearance which increasingly displaying similarities to household animals and humans, there is a need to study the existence of uncanny valley phenomenon. Generally, the acceptance of people toward robots increases as the robots acquire increasing similarities to human features until a stage where people feel very uncomfortable, eerie, fear and disgust when the robot appearance become almost human like but not yet human. This phenomenon called uncanny valley was first reported by Masahiro Mori. There are numerous researches conducted to measure the existence of uncanny valley in Japan and European countries. However, there is limited research reported on uncanny valley phenomenon in Malaysia so far. In view of the different cultural background and exposure of Malaysian population to robotics technology compared to European or East Asian populations, it is worth to study this phenomenon in Malaysian context. The main aim of this work is to conduct a preliminary study to determine the existence of uncanny valley phenomenon in Malaysian urban and rural populations. It is interesting to find if there are any differences in the acceptance of the two set of populations despite of their differences. Among others the urban and rural populations differ in term of the rate of urbanization and exposure to latest technologies. A set of four interactive robotic faces and an ideal human model representing the fifth robot are used in this study. The robots have features resembling a cute animal, cartoon character, typical robot and human-like. Questionnaire surveys are conducted on respondents from urban and rural populations. Survey data collected are

  16. Seismic design criteria for the system 80+ advanced light water reactor

    International Nuclear Information System (INIS)

    Manrique, M.A.; Dermitzakis, S.N.; Gerdes, L.D.; Kennedy, R.P.; Idriss, I.M.; Cassidy, J.R.

    1991-01-01

    This paper presents the development of seismic design criteria in support of design certification by the Nuclear Regulatory Commission (NRC) of the ABB-Combustion Engineering's System 80+ Standard Design. The design certification effort is sponsored by the US Department of Energy (DOE). The development of the design criteria included: (a) development of the seismic control motion, (b) development of generic soil profiles for anticipated sites, (c) generation of in-structure response spectra and design loads for structures and equipment through soil-structure interaction (SSI) analyses, and (d) acceptance criteria for future construction sites

  17. Feasibility and acceptability of electronic symptom surveillance with clinician feedback using the Patient-Reported Outcomes version of Common Terminology Criteria for Adverse Events (PRO-CTCAE) in Danish prostate cancer patients

    DEFF Research Database (Denmark)

    Bæksted, Christina; Pappot, Helle; Nissen, Aase

    2017-01-01

    -CTCAE questionnaire on tablet computers using AmbuFlex software at each treatment visit in the outpatient clinic. In total, 22 symptomatic toxicities (41 PRO-CTCAE items), corresponding to the symptomatic adverse-events profile associated with the regimens commonly used for prostate cancer treatment (Docetaxel......Background: The aim was to examine the feasibility, acceptability and clinical utility of electronic symptom surveillance with clinician feedback using a subset of items drawn from the Patient-Reported Outcomes version of Common Terminology Criteria for Adverse Events (PRO-CTCAE) in a cancer...

  18. Variability amongst radiographers in the categorization of clinical acceptability for digital trauma radiography

    Science.gov (United States)

    Decoster, Robin; Toomey, Rachel; Smits, Dirk; Mol, Harrie; Verhelle, Filip; Butler, Marie-Louise

    2016-03-01

    Introduction: Radiographers evaluate anatomical structures to judge clinical acceptability of a radiograph. Whether a radiograph is deemed acceptable for diagnosis or not depends on the individual decision of the radiographer. Individual decisions cause variation in the accepted image quality. To minimise these variations definitions of acceptability, such as in RadLex, were developed. On which criteria radiographers attribute a RadLex categories to radiographs is unknown. Insight into these criteria helps to further optimise definitions and reduce variability in acceptance between radiographers. Therefore, this work aims the evaluation of the correlation between the RadLex classification and the evaluation of anatomical structures, using a Visual Grading Analysis (VGA) Methods: Four radiographers evaluated the visibility of five anatomical structures of 25 lateral cervical spine radiographs on a secondary class display with a VGA. They judged clinical acceptability of each radiograph using RadLex. Relations between VGAS and RadLex category were analysed with Kendall's Tau correlation and Nagelkerke pseudo-R². Results: The overall VGA score (VGAS) and the RadLex score correlate (rτ= 0.62, pscore. The reproduction of spinous processes (rτ=0.67, pscore. Conclusion: RadLex scores and VGAS correlate positively, strongly and significantly. The predictive value of bony structures may support the use of these in the judgement of clinical acceptability. Considerable inter-observer variations in the VGAS within a certain RadLex category, suggest that observers use of observer specific cut-off values.

  19. Acceptance criteria for reprocessed AcuNav catheters: comparison between functionality testing and clinical image assessment.

    Science.gov (United States)

    Bank, Alan J; Berry, James M; Wilson, Robert F; Lester, Bruce R

    2009-03-01

    The AcuNav-catheter is a vector-phased array ultrasound catheter that has shown great utility for both diagnosis and electrophysiological interventions. To test the feasibility of limited catheter reuse and to ensure that reprocessed catheters would produce acceptable clinical images, the present study compared the 2-D and Doppler image quality, as determined by clinical assessment, with the catheter's functional status as determined by the FirstCall 2000 transducer tester. Reprocessed catheters from four functional categories, two acceptable and two unacceptable, were used to collect images, 2-D and Doppler, from a porcine heart. The images were blinded and then rated by clinical evaluation. The study found that catheter images from all functional categories were found to be clinically acceptable except for those from the lowest unacceptable category. In addition, examination of tip deflection characteristics showed no significant difference between new and reprocessed catheters. We conclude that reprocessed AcuNav catheters that pass functional tests are able to produce clinical images, 2-D and Doppler, which are equivalent to their new counterparts.

  20. The Acceptability and Potential Utility of Cognitive Training to Improve Working Memory in Persons Living With HIV: A Preliminary Randomized Trial.

    Science.gov (United States)

    Towe, Sheri L; Patel, Puja; Meade, Christina S

    HIV-associated neurocognitive impairments that impact daily function persist in the era of effective antiretroviral therapy. Cognitive training, a promising low-cost intervention, has been shown to improve neurocognitive functioning in some clinical populations. We tested the feasibility, acceptability, and preliminary effects of computerized cognitive training to improve working memory in persons living with HIV infection (PLWH) and working memory impairment. In this randomized clinical trial, we assigned 21 adult PLWH to either an experimental cognitive training intervention or an attention-matched control training intervention. Participants completed 12 training sessions across 10 weeks with assessments at baseline and post-training. Session attendance was excellent and participants rated the program positively. Participants in the experimental arm demonstrated improved working memory function over time; participants in the control arm showed no change. Our results suggest that cognitive training may be a promising intervention for working memory impairment in PLWH and should be evaluated further. Copyright © 2017 Association of Nurses in AIDS Care. Published by Elsevier Inc. All rights reserved.

  1. 75 FR 77862 - FFP Missouri 16, LLC, Solia 9 Hydroelectric, LLC; Notice of Competing Preliminary Permit...

    Science.gov (United States)

    2010-12-14

    ... Missouri 16, LLC, Solia 9 Hydroelectric, LLC; Notice of Competing Preliminary Permit Applications Accepted.... On August 6, 2010, FFP Missouri 16, LLC (FFP) and Solia 9 Hydroelectric, LLC filed preliminary permit...-2822. Solia 9 Hydroelectric's proposed Lock and Dam 15 Hydropower Project (Project No. 13827-000) would...

  2. Dysplastic naevus: histological criteria and their inter-observer reproducibility.

    Science.gov (United States)

    Hastrup, N; Clemmensen, O J; Spaun, E; Søndergaard, K

    1994-06-01

    Forty melanocytic lesions were examined in a pilot study, which was followed by a final series of 100 consecutive melanocytic lesions, in order to evaluate the inter-observer reproducibility of the histological criteria proposed for the dysplastic naevus. The specimens were examined in a blind fashion by four observers. Analysis by kappa statistics showed poor reproducibility of nuclear features, while reproducibility of architectural features was acceptable, improving in the final series. Consequently, we cannot apply the combined criteria of cytological and architectural features with any confidence in the diagnosis of dysplastic naevus, and, until further studies have documented that architectural criteria alone will suffice in the diagnosis of dysplastic naevus, we, as pathologists, shall avoid this term.

  3. Spent nuclear fuel project-criteria document Cold Vacuum Drying Facility phase 2 safety analysis report

    International Nuclear Information System (INIS)

    Garvin, L.J.

    1998-01-01

    The criteria document provides the criteria and guidance for developing the SNF CVDF Phase 2 SAR. This SAR will support the US Department of Energy, Richland Operations Office decision to authorize the procurement, installation, and installation acceptance testing of the CVDF systems

  4. Acceptance test report, plutonium finishing plant life safety upgrade

    International Nuclear Information System (INIS)

    Hodge, S.G.

    1994-01-01

    This acceptance Test Procedure (ATP) has been prepared to demonstrate that modifications to the Fir Protection systems function as required by project criteria. The ATP will test the Fire Alarm Control Panels, Flow Alarm Pressure Switch, Heat Detectors, Smoke Detectors, Flow Switches, Manual Pull Stations, and Gong/Door By Pass Switches

  5. Social Competence in Childhood Brain Tumor Survivors: Feasibility and Preliminary Outcomes of a Peer-Mediated Intervention

    Science.gov (United States)

    Devine, Katie A.; Bukowski, William M.; Sahler, Olle Jane Z.; Ohman-Strickland, Pamela; Smith, Tristram H.; Lown, E. Anne; Patenaude, Andrea Farkas; Korones, David N.; Noll, Robert B.

    2016-01-01

    Objective Evaluate the acceptability, feasibility, and preliminary outcomes of a peer-mediated intervention to improve social competence of brain tumor survivors and classmates. Methods Twelve childhood brain tumor survivors and 217 classroom peers in intervention (n = 8) or comparison (n = 4) classrooms completed measures of social acceptance and reputation at two time points in the year. The intervention (5–8 sessions over 4–6 weeks) taught peer leaders skills for engaging classmates. Individual and classroom outcomes were analyzed with ANCOVA. Results Recruitment rates of families of brain tumor survivors (81%) and schools (100%) were adequate. Peer leaders reported satisfaction with the intervention. Preliminary outcome data trended toward some benefit in increasing the number of friend nominations for survivors of brain tumors but no changes in other peer-reported metrics. Preliminary results also suggested some positive effects on classroom levels of victimization and rejection. Conclusions A peer-mediated intervention was acceptable to families of brain tumor survivors and feasible to implement in schools. Findings warrant a larger trial to evaluate improvements for children with brain tumors and their peers. PMID:27355881

  6. A technical basis for meeting waste form stability requirements of 10 CFR 61

    International Nuclear Information System (INIS)

    Chang, W.Y.; Skoski, L.; Eng, R.; Tuite, P.T.

    1988-01-01

    To assure that solidified low level waste forms meet the stability requirements of 10 CFR 61 regulations, the US Nuclear Regulatory Commission (NRC) has published Branch Technical Positions (BTPs) and draft Regulatory Guide on waste form stability. These guidance documents describe the test procedures and acceptance criteria for six stability parameters: leachability, compressive strength, immersion effect, radiation effect, thermal stability and biodegradability. The most recent set of recommended tests and acceptance criteria are presented in the November 1986 Preliminary Draft Regulatory Guide Low Level Waste Form Stability. The objective of this study was to: (1) investigate the regulatory and technical bases for the required stability tests, (2) evaluate the relevance of these tests and acceptance criteria based on actual test results, and (3) recommended alternatives to the testing and acceptance criteria. The latter two objectives are discussed in this paper

  7. Acceptance test report for the Westinghouse 100 ton hydraulic trailer

    Energy Technology Data Exchange (ETDEWEB)

    Barrett, R.A.

    1995-03-06

    The SY-101 Equipment Removal System 100 Ton Hydraulic Trailer was designed and built by KAMP Systems, Inc. Performance of the Acceptance Test Procedure at KAMP`s facility in Ontario, California (termed Phase 1 in this report) was interrupted by discrepancies noted with the main hydraulic cylinder. The main cylinder was removed and sent to REMCO for repair while the trailer was sent to Lampson`s facility in Pasco, Washington. The Acceptance Test Procedure was modified and performance resumed at Lampson (termed Phase 2 in this report) after receipt of the repaired cylinder. At the successful conclusion of Phase 2 testing the trailer was accepted as meeting all the performance criteria specified.

  8. Reliability criteria selection for integrated resource planning

    International Nuclear Information System (INIS)

    Ruiu, D.; Ye, C.; Billinton, R.; Lakhanpal, D.

    1993-01-01

    A study was conducted on the selection of a generating system reliability criterion that ensures a reasonable continuity of supply while minimizing the total costs to utility customers. The study was conducted using the Institute for Electronic and Electrical Engineers (IEEE) reliability test system as the study system. The study inputs and results for conditions and load forecast data, new supply resources data, demand-side management resource data, resource planning criterion, criterion value selection, supply side development, integrated resource development, and best criterion values, are tabulated and discussed. Preliminary conclusions are drawn as follows. In the case of integrated resource planning, the selection of the best value for a given type of reliability criterion can be done using methods similar to those used for supply side planning. The reliability criteria values previously used for supply side planning may not be economically justified when integrated resource planning is used. Utilities may have to revise and adopt new, and perhaps lower supply reliability criteria for integrated resource planning. More complex reliability criteria, such as energy related indices, which take into account the magnitude, frequency and duration of the expected interruptions are better adapted than the simpler capacity-based reliability criteria such as loss of load expectation. 7 refs., 5 figs., 10 tabs

  9. Development of flaw evaluation and acceptance procedures for flaw indications in the cooling water system at the Savannah River site K reactor

    International Nuclear Information System (INIS)

    Tandon, S.; Bamford, W.H.; Cowfer, C.D.; Ostrowski, R.

    1993-01-01

    This paper describes the methodology used in determining the criteria for acceptance of inspection indications in the K-Reactor Cooling Water System at the Savannah River Plant. These criteria have been developed in a manner consistent with the development of similar criteria in the ASME Code Section XI for commercial light water reactors, but with a realistic treatment of the operating conditions in the cooling water system. The technical basis for the development of these criteria called ''Acceptance Standards'' is contained in this paper. A second portion of this paper contains the methodology used in the construction of flaw evaluation charts which have been developed for each specific line size in the cooling water system. The charts provide the results of detailed fracture mechanics calculations which have been completed to determine the largest flaw which can be accepted in the cooling water system without repair. These charts are designed for use in conjunction with in-service inspections of the cooling water system, and only require inspection results to determine acceptability

  10. 76 FR 73616 - Lock 12 Hydro Partners; FFP Project 107 LLC; Notice of Competing Preliminary Permit Applications...

    Science.gov (United States)

    2011-11-29

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project Nos. 13214-002; 14274-000] Lock 12 Hydro Partners; FFP Project 107 LLC; Notice of Competing Preliminary Permit Applications Accepted..., 2011, Lock 12 Hydro Partners (Lock 12), and FFP Project 107 LLC (FFP 107) filed preliminary permit...

  11. 76 FR 73614 - Lock 14 Hydro Partners; FFP Project 106 LLC; Notice of Competing Preliminary Permit Applications...

    Science.gov (United States)

    2011-11-29

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project Nos. 13213-002; 14271-000] Lock 14 Hydro Partners; FFP Project 106 LLC; Notice of Competing Preliminary Permit Applications Accepted..., 2011, Lock 14 Hydro Partners (Lock 14), and FFP Project 106 LLC (FFP 106) filed preliminary permit...

  12. A Preliminary Analysis of Reactor Performance Test (LOEP) for a Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hyeonil; Park, Su-Ki [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    The final phase of commissioning is reactor performance test, which is to prove the integrated performance and safety of the research reactor at full power with fuel loaded such as neutron power calibration, Control Absorber Rod/Second Shutdown Rod drop time, InC function test, Criticality, Rod worth, Core heat removal with natural mechanism, and so forth. The last test will be safety-related one to assure the result of the safety analysis of the research reactor is marginal enough to be sure about the nuclear safety by showing the reactor satisfies the acceptance criteria of the safety functions such as for reactivity control, maintenance of auxiliaries, reactor pool water inventory control, core heat removal, and confinement isolation. After all, the fuel integrity will be ensured by verifying there is no meaningful change in the radiation levels. To confirm the performance of safety equipment, loss of normal electric power (LOEP), possibly categorized as Anticipated Operational Occurrence (AOO), is selected as a key experiment to figure out how safe the research reactor is before turning over the research reactor to the owner. This paper presents a preliminary analysis of the reactor performance test (LOEP) for a research reactor. The results showed how different the transient between conservative estimate and best estimate will look. Preliminary analyses have shown all probable thermal-hydraulic transient behavior of importance as to opening of flap valve, minimum critical heat flux ratio, the change of flow direction, and important values of thermal-hydraulic parameters.

  13. Upgraded acceptance criteria from transient thermography control for the W7-X divertor target elements

    Energy Technology Data Exchange (ETDEWEB)

    Missirlian, M. [CEA, IRFM, F-13108 Saint-Paul-Lez-Durance (France)], E-mail: marc.missirlian@cea.fr; Boscary, J. [Max-Planck-Institut fuer Plasmaphysik, Euratom Association, Boltzmannstr. 2, D-85748 Garching (Germany); Guigon, R.; Schlosser, J.; Durocher, A. [CEA, IRFM, F-13108 Saint-Paul-Lez-Durance (France); Greuner, H. [Max-Planck-Institut fuer Plasmaphysik, Euratom Association, Boltzmannstr. 2, D-85748 Garching (Germany)

    2009-06-15

    The commissioning of plasma-facing component fields needs advanced non-destructive methods to detect in a reliable way the defects, which can impair the component performances and/or integrity during operation. Within this framework, CEA developed a dedicated non-destructive examination method based on active infrared thermography (SATIR facility) to inspect the bonding between armour material and metallic heat sink. Used with successful in the commissioning of the toroidal pump limiter of Tore Supra, this technique was applied in the frame of the pre-series activities of the Wendelstein 7-X high heat flux divertor elements to assess the bonding quality of the delivered components. This paper presents the methodology adopted to define an acceptance criterion based on SATIR test bed possibly applied for a serial inspection of the Wendelstein 7-X elements. Using the well-tried acceptance test based on the DTref{sub m}ax parameter, the new method includes advanced data post-processing techniques from thermo-signal SATIR and a data merging method to help the decision-making and to optimise the reliability of the binary response expected for a final decision in terms of acceptance test.

  14. Upgraded acceptance criteria from transient thermography control for the W7-X divertor target elements

    International Nuclear Information System (INIS)

    Missirlian, M.; Boscary, J.; Guigon, R.; Schlosser, J.; Durocher, A.; Greuner, H.

    2009-01-01

    The commissioning of plasma-facing component fields needs advanced non-destructive methods to detect in a reliable way the defects, which can impair the component performances and/or integrity during operation. Within this framework, CEA developed a dedicated non-destructive examination method based on active infrared thermography (SATIR facility) to inspect the bonding between armour material and metallic heat sink. Used with successful in the commissioning of the toroidal pump limiter of Tore Supra, this technique was applied in the frame of the pre-series activities of the Wendelstein 7-X high heat flux divertor elements to assess the bonding quality of the delivered components. This paper presents the methodology adopted to define an acceptance criterion based on SATIR test bed possibly applied for a serial inspection of the Wendelstein 7-X elements. Using the well-tried acceptance test based on the DTref m ax parameter, the new method includes advanced data post-processing techniques from thermo-signal SATIR and a data merging method to help the decision-making and to optimise the reliability of the binary response expected for a final decision in terms of acceptance test.

  15. Workshop material for state review of USNRC site suitability criteria for high-level radioactive waste repositories

    International Nuclear Information System (INIS)

    1977-08-01

    The Nuclear Regulatory Commission (NRC) is developing criteria on which to judge whether a proposed site for a geologic repository is suitable for disposal of high-level nuclear wastes. To aid in its analysis and assessment, NRC is planning three early independent reviews of the site suitability criteria development effort: a peer review by experts outside of NRC; a review by the National Academy of Sciences; and a review by State officials. This document has been prepared to aid workshop participants in understanding the Preliminary Site Suitability Criteria and to prepare them to contribute to an evaluation of those criteria

  16. Selection criteria for water disinfection techniques in agricultural practices.

    Science.gov (United States)

    Haute, Sam van; Sampers, Imca; Jacxsens, Liesbeth; Uyttendaele, Mieke

    2015-01-01

    This paper comprises a selection tool for water disinfection methods for fresh produce pre- and postharvest practices. A variety of water disinfection technologies is available on the market and no single technology is the best choice for all applications. It can be difficult for end users to choose the technology that is best fit for a specific application. Therefore, the different technologies were characterized in order to identify criteria that influence the suitability of a technology for pre- or postharvest applications. Introduced criteria were divided into three principal components: (i) criteria related to the technology and which relate to the disinfection efficiency, (ii) attention points for the management and proper operation, and (iii) necessities in order to sustain the operation with respect to the environment. The selection criteria may help the end user of the water disinfection technology to obtain a systematic insight into all relevant aspects to be considered for preliminary decision making on which technologies should be put to feasibility testing for water disinfection in pre- and postharvest practices of the fresh produce chain.

  17. Design Preliminaries for Direct Drive under Water Wind Turbine Generator

    DEFF Research Database (Denmark)

    Leban, Krisztina Monika; Ritchie, Ewen; Argeseanu, Alin

    2012-01-01

    This paper focuses on the preliminary design process of a 20 MW electric generator. The application calls for an offshore, vertical axis, direct drive wind turbine. Arguments for selecting the type of electric machine for the application are presented and discussed. Comparison criteria for deciding...... on a type of machine are listed. Additional constraints emerging from the direct drive, vertical axis concepts are considered. General rules and a preliminary algorithm are discussed for the machine selected to be most suitable for the imposed conditions....

  18. 78 FR 38313 - Kings River Conservation District; Notice of Preliminary Permit Application Accepted for Filing...

    Science.gov (United States)

    2013-06-26

    ...-hours utilizing one Kaplan-bulb turbine. A preliminary design of the facilities and selection of the turbine and generator would be performed during the feasibility study. Applicant Contact: Mr. David Orth...

  19. Acceptance criteria for interim dry storage of aluminum-clad fuels

    International Nuclear Information System (INIS)

    Sindelar, R.L.; Peacock, H.B. Jr.; Iyer, N.C.; Louthan, M.R. Jr.

    1994-01-01

    Direct repository disposal of foreign and domestic research reactor fuels owned by the United States Department of Energy is an alternative to reprocessing (together with vitrification of the high level waste and storage in an engineered barrier) for ultimate disposition. Neither the storage systems nor the requirements and specifications for acceptable forms for direct repository disposal have been developed; therefore, an interim storage strategy is needed to safely store these fuels. Dry storage (within identified limits) of the fuels received from wet-basin storage would avoid excessive degradation to assure post-storage handleability, a full range of ultimate disposal options, criticality safety, and provide for maintaining confinement by the fuel/clad system. Dry storage requirements and technologies for US commercial fuels, specifically zircaloy-clad fuels under inert cover gas, are well established. Dry storage requirements and technologies for a system with a design life of 40 years for dry storage of aluminum-clad foreign and domestic research reactor fuels are being developed by various groups within programs sponsored by the DOE

  20. Design criteria for the structural analysis of shipping cask containment vessels

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    10 CFR Part 71, Sections 71.35 and 71.36, require that packages used to transport radioactive materials meet specified normal and hypothetical accident conditions. Acceptable design criteria are presented for use in the structural analysis of the containment vessels of Type B packages used to transport irradiated nuclear fuel. Alternative design criteria meeting the structural requirements of 10 CFR Part 71, Section 71.35 and 71.36, may also be used

  1. Independent review of Oak Ridge HCTW test program and development of seismic evaluation criteria

    International Nuclear Information System (INIS)

    1995-05-01

    Many of the existing buildings at the Oak Ridge Y-12 Plant are steel frame construction with unreinforced hollow clay tile infill walls (HCTW). The HCTW infill provides some lateral seismic resistance to the design/evaluation basis earthquake; however acceptance criteria for this construction must be developed. The basis for the development of seismic criteria is the Oak Ridge HCTW testing and analysis program and the target performance goals of DOE 5480.28 and DOE-STD-1020-94. This report documents and independent review of the testing and analysis program and development of recommended acceptance criteria for Oak Ridge HCTW construction. The HCTW test program included ''macro'' wall in-plane and out-of-plane tests, full-scale wall in-plane and out-of-plane tests, in-situ out-of-plane test, shake table tests, and masonry component tests

  2. Acceptance criteria for the evaluation of Category 1 fuel cycle facility physical security plans

    Energy Technology Data Exchange (ETDEWEB)

    Dwyer, P.A.

    1991-10-01

    This NUREG document presents criteria developed from US Nuclear Regulatory Commission regulations for the evaluation of physical security plans submitted by Category 1 fuel facility licensees. Category 1 refers to those licensees who use or possess a formula quantity of strategic special nuclear material.

  3. Acceptance criteria for the evaluation of Category 1 fuel cycle facility physical security plans

    International Nuclear Information System (INIS)

    Dwyer, P.A.

    1991-10-01

    This NUREG document presents criteria developed from US Nuclear Regulatory Commission regulations for the evaluation of physical security plans submitted by Category 1 fuel facility licensees. Category 1 refers to those licensees who use or possess a formula quantity of strategic special nuclear material

  4. Analysis of existing work-zone devices with MASH safety performance criteria.

    Science.gov (United States)

    2009-02-01

    Crashworthy, work-zone, portable sign support systems accepted under NCHRP Report No. 350 were analyzed to : predict their safety peformance according to the TL-3 MASH evaluation criteria. An analysis was conducted to determine : which hardware param...

  5. International comparison of safety criteria applied to radwaste repositories. Safety aspects of the post-operational phase

    International Nuclear Information System (INIS)

    Baltes, B.

    1994-01-01

    There is a generally accepted system of framework safety conditions governing the construction, operation, and post-operational monitoring of radwaste repositories. Although the development of these framework conditions may vary from country to country, the resulting criteria are based on the commonly accepted system of priciples and purposes established for ultimate radioactive waste disposal. The experience accumulated by GRS in the course of the plan approval procedure for the Konrad mine site and the safety-relevant studies performed for the planned Morsleben repository clearly show demand for further development of the safety criteria. In Germany, it is especially the safety criteria and detailed requirements filling the framework safety conditions that need revision and in-depth definition, as well as comparison and harmonisation with internationally applied criteria. These activities will particularly consider the international convention on radioactive waste management currently in preparation under the auspieces of the IAEA. (orig.) [de

  6. Radiation shielding aspects for long manned mission to space - Criteria, survey study and preliminary model

    International Nuclear Information System (INIS)

    Sztejnberg, M.; Xiao, S.; Satvat, N.; Limon, F.; Hopkins, J.; Jevremovic, T.; T. Jevremovic)

    2006-01-01

    The prospect of manned space missions out side Earth's or bit is limited by the travel time and shielding against cosmic radiation. The chemical rockets currently used in the space program have no hope of propelling a manned vehicle to a far away location such as Mars due to the enormous mass of fuel that would be required. The specific energy available from nuclear fuel is a factor of 106 higher than chemical fuel; it is there fore obvious that nuclear power production in space is a must. On the other hand, recent considerations to send a man to the Moon for a long stay would require a stable, secured, and safe source of energy (there is hardly anything beyond nuclear power that would provide a useful and reliably safe sustainable supply of energy). National Aeronautics and Space Administration (NASA) anticipates that the mass of a shielding material required for long travel to Mars is the next major design driver. In 2006 NASA identified a need to assess and evaluate potential gaps in existing knowledge and understanding of the level and types of radiation critical to astronauts' health during the long travel to Mars and to start a comprehensive study related to the shielding design of a spacecraft finding the conditions for the mitigation of radiation components contributing to the doses beyond accepted limits. In order to reduce the overall space craft mass, NASA is looking for the novel, multi-purpose and multi-functional materials that will provide effective shielding of the crew and electronics on board. The Laboratory for Neutronics and Geometry Computation in the School of Nuclear Engineering at Purdue University led by Prof. Tatjana Jevremovic began in 2004 the analytical evaluations of different lightweight materials. The preliminary results of the design survey study are presented in this paper. (author)

  7. Radiation shielding aspects for long manned mission to space: Criteria, survey study, and preliminary model

    Directory of Open Access Journals (Sweden)

    Sztejnberg Manuel

    2006-01-01

    Full Text Available The prospect of manned space missions outside Earth's orbit is limited by the travel time and shielding against cosmic radiation. The chemical rockets currently used in the space program have no hope of propelling a manned vehicle to a far away location such as Mars due to the enormous mass of fuel that would be required. The specific energy available from nuclear fuel is a factor of 106 higher than chemical fuel; it is therefore obvious that nuclear power production in space is a must. On the other hand, recent considerations to send a man to the Moon for a long stay would require a stable, secured and safe source of energy (there is hardly anything beyond nuclear power that would provide a useful and reliably safe sustainable supply of energy. National Aeronautics and Space Administration (NASA anticipates that the mass of a shielding material required for long travel to Mars is the next major design driver. In 2006 NASA identified a need to assess and evaluate potential gaps in existing knowledge and understanding of the level and types of radiation critical to astronauts' health during the long travel to Mars and to start a comprehensive study related to the shielding design of a spacecraft finding the conditions for the mitigation of radiation components contributing to the doses beyond accepted limits. In order to reduce the overall space craft mass, NASA is looking for the novel, multi-purpose and multi-functional materials that will provide effective shielding of the crew and electronics on board. The Laboratory for Neutronics and Geometry Computation in the School of Nuclear Engineering at Purdue University led by Prof. Tatjana Jevremović began in 2004 the analytical evaluations of different lightweight materials. The preliminary results of the design survey study are presented in this paper.

  8. Development of small reactor safety criteria in Canada

    International Nuclear Information System (INIS)

    Ernst, P.C.; French, P.M.; Axford, D.J.; Snell, V.G.

    1990-01-01

    A number of new small reactor designs have been proposed in Canada over the last several years and some have reached the stage where licensing discussions have been initiated with the Atomic Energy Control Board (AECB). An inter-organizational Small Reactor Criteria (SRC) working group was formed in 1988 to propose safety and licensing criteria for these small reactors. Two levels of criteria are proposed. The first level forms a safety philosophy and the second is a set of criteria for specific reactor applications. The safety philosophy consists of three basic safety objectives together with evaluation criteria, and fourteen fundamental principles measured by specific criteria, which must be implemented to meet the safety objectives. Two of the fourteen principles are prime: defence in depth, and safety culture; the other twelve principles can be seen as deriving from them. A benefit of this approach is that the concepts of defence in depth and safety culture become well-defined. The objectives and principles are presented in the paper and their criteria are summarized. The second level of criteria, under development, will form a safety application set and will provide small reactor criteria in a number of general areas, such as regulatory process and safety assessment, as well as for specific reactor life-cycle activities, from siting through to decommissioning. The criteria are largely deterministic. However, the frequencies and consequences of postulated accidents are assessed against numerical criteria to assist in judging the acceptability of plant design, operation, and proposed siting. All criteria proposed are designed to be testable in some evidentiary fashion, readily enabling an assessment of compliance for a given proposal

  9. Criteria for candidate species for aquaculture

    Energy Technology Data Exchange (ETDEWEB)

    Webber, H H; Riordan, P F

    1976-01-01

    The nature of the animal taxa that are the most probable candidates for an intensive, commercial aquatic animal husbandry industry is considered. A characterization is presented of those biological criteria that lend the species the necessary physiological and genetic malleability to be adapted and molded into a domesticated race. The animal cultivated must be amenable to intensive management in high-density confinements such as those now being engineered for high-yield aquaculture. Attributes considered are discussed in the context of the various aquacultural ecosystems in which the specific biotype is expected to achieve satisfactory growth and survival. Correlative with bionomic criteria, economic requirements are posed and evaluated in an effort to define a socially and financially profitable agribusiness system. Investment requirements and operating costs are considered in terms of expected returns. However, since production alone is insufficient to sustain an enterprise - i.e., the product must be sold - production costs must be judged against market values. Therefore, ultimate use or consumer acceptance criteria are incorporated into the list of essential requirements for a candidate species for aquafarming.

  10. Determination of effective criteria on development of RTA Furniture Industry in Iran

    Directory of Open Access Journals (Sweden)

    hosein omidi

    2016-06-01

    Full Text Available Ready to assemble furniture industry in Iran has not been considered by practitioners and investors as it is known in the other countries. While, it is possible to achive the many competitive advantage, if this industry develop in Iran. With regard to this issue, the goal of this study is to introduce the potential market for ready to assemble furniture and determination and prioritize of the effective criteria on development of Iran ready to assemble furniture industry. For this purpose, after preliminary investigation and interview with some of the furniture producers and relevant experts, the identified criteria were divided into five major groups as Economic, Management, Marketing & Sales, Technical-Technological and Infrastructure and as well as 42 sub-criteria. The hierarchy of these criteria was designed and then the weighting values of criteria and sub-criteria were determined using Analytical Hierarchy Process (AHP by expert choice software. The results indicated that the management and marketing & sales criteria have the highest weighting values at the first level. In addition, among the effective sub-criteria, the criteria as marketing innovation, design innovation, operations management, logistics management, raw materials innovation and product promotion, have the highest priorities for development of ready to assemble furniture industry in Iran.

  11. Criteria for the evaluation of a dilute decontamination demonstration

    International Nuclear Information System (INIS)

    FitzPatrick, V.F.; Divine, J.R.; Hoenes, G.R.; Munson, L.F.; Card, C.J.

    1981-12-01

    This document provides the prerequisite technical information required to evaluate and/or develop a project to demonstrate the dilute chemical decontamination of the primary coolant system of light water reactors. The document focuses on five key areas: the basis for establishing programmatic prerequisites and the key decision points that are required for proposal evaluation and/or RFP (Request for Proposal) issuance; a technical review of the state-of-the-art to identify the potential impacts of a reactor's primary-system decontamination on typical BWR and PWR plants; a discussion of the licensing, recertification, fuel warranty, and institutional considerations and processes; a preliminary identification and development of the selection criteria for the reactor and the decontamination process; and a preliminary identification of further research and development that might be required

  12. Criteria for cesium capsules to be shipped as special form radioactive material

    International Nuclear Information System (INIS)

    Lundeen, J.E.

    1994-01-01

    The purpose of this report is to compile all the documentation which defines the criteria for Waste Encapsulation and Storage Facility (WESF) cesium capsules at the IOTECH facility and Applied Radiant Energy Corporation (ARECO) to be shipped as special form radioactive material in the Beneficial Uses Shipping System (BUSS) Cask. The capsules were originally approved as special form in 1975, but in 1988 the integrity of the capsules came into question. WHC developed the Pre-shipment Acceptance Test Criteria for capsules to meet in order to be shipped as special form material. The Department of Energy approved the criteria and directed WHC to ship the capsules at IOTECH and ARECO meeting this criteria to WHC as special form material

  13. The preliminary design and feasibility study of the spent fuel and high level waste repository in the Czech Republic

    International Nuclear Information System (INIS)

    Valvoda, Z.; Holub, J.; Kucerka, M.

    1996-01-01

    In the year 1993, began the Program of Development of the Spent Fuel and High Level Waste Repository in the Conditions of the Czech Republic. During the first phase, the basic concept and structure of the Program has been developed, and the basic design criteria and requirements were prepared. In the conditions of the Czech Republic, only an underground repository in deep geological formation is acceptable. Expected depth is between 500 to 1000 meters and as host rock will be granites. A preliminary variant design study was realized in 1994, that analyzed the radioactive waste and spent fuel flow from NPPs to the repository, various possibilities of transportation in accordance to the various concepts of spent fuel conditioning and transportation to the underground structures. Conditioning and encapsulation of spent fuel and/or radioactive waste is proposed on the repository site. Underground disposal structures are proposed at one underground floor. The repository will have reserve capacity for radioactive waste from NPPs decommissioning and for waste non acceptable to other repositories. Vertical disposal of unshielded canisters in boreholes and/or horizontal disposal of shielded canisters is studied. As the base term of the start up of the repository operation, the year 2035 has been established. From this date, a preliminary time schedule of the Project has been developed. A method of calculating leveled and discounted costs within the repository lifetime, for each of selected 5 variants, was used for economic calculations. Preliminary expected parametric costs of the repository are about 0,1 Kc ($0.004) per MWh, produced in the Czech NPPs. In 1995, the design and feasibility study has gone in more details to the technical concept of repository construction and proposed technologies, as well as to the operational phase of the repository. Paper will describe results of the 1995 design work and will present the program of the repository development in next period

  14. The acceptability of the female and male condom: a randomized crossover trial.

    Science.gov (United States)

    Kulczycki, Andrzej; Kim, Dhong-Jin; Duerr, Ann; Jamieson, Denise J; Macaluso, Maurizio

    2004-01-01

    Although studies have assessed the acceptability of male and female condoms, comparative trial data are lacking. A sample of 108 women in stable relationships recruited from an urban, reproductive health clinic were randomly assigned to use 10 male or female condoms, followed by use of 10 of the other type. A nurse provided instruction in correct method use. Demographic information was collected in a baseline questionnaire; acceptability data were collected in follow-up and exit questionnaires and coital logs. Nonparametric and chi-square statistics were used to analyze measures of the methods' relative acceptability. Bowker's test of symmetry was adapted to test the null hypothesis of no difference in acceptability between condom types. Participants used 678 female and 700 male condoms. Although neither method scored high on user satisfaction measures, the 63 women completing the study protocol preferred the male condom to the female condom for ease of application or insertion, ease of removal, general fit, feel of the condom during intercourse and ease of penetration. Participants reported that their partner also favored the male condom, although women generally appeared to like this method more than their partner did. In a direct comparison between the methods at the end of the study, women generally judged male condoms superior on specified preference criteria. Across a range of criteria, the female condom was less acceptable than the male condom to most women and their partners. Although both types had low acceptability, they are needed and valid methods of pregnancy and disease prevention. That neither rated high on user satisfaction measures underscores the need for more barrier methods that women and men can use.

  15. Reportable Nuclide Criteria for ORNL Radioactive Waste Management Activities - 13005

    International Nuclear Information System (INIS)

    McDowell, Kip; Forrester, Tim; Saunders, Mark

    2013-01-01

    The U.S. Department of Energy's Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee generates numerous radioactive waste streams. Many of those streams contain a large number of radionuclides with an extremely broad range of concentrations. To feasibly manage the radionuclide information, ORNL developed reportable nuclide criteria to distinguish between those nuclides in a waste stream that require waste tracking versus those nuclides of such minimal activity that do not require tracking. The criteria include tracking thresholds drawn from ORNL onsite management requirements, transportation requirements, and relevant treatment and disposal facility acceptance criteria. As a management practice, ORNL maintains waste tracking on a nuclide in a specific waste stream if it exceeds any of the reportable nuclide criteria. Nuclides in a specific waste stream that screen out as non-reportable under all these criteria may be dropped from ORNL waste tracking. The benefit of these criteria is to ensure that nuclides in a waste stream with activities which meaningfully affect safety and compliance are tracked, while documenting the basis for removing certain isotopes from further consideration. (authors)

  16. Conclusions regarding geotechnical acceptability of the WIPP site

    International Nuclear Information System (INIS)

    Weart, W.D.

    1983-01-01

    The Waste Isolation Pilot Plant (WIPP) was authorized by Congress in 1980 as an unlicensed research and development (R and D) facility to demonstrate the safe disposal of radioactive wastes arising from the defense activities and programs of the United States. WIPP is now being constructed in southeast New Mexico, using salt beds about 655 m below the surface of the ground. Construction of the full WIPP facility will not commence until a preliminary underground excavation phase, called Site and Preliminary Design Validation (SPDV), is satisfactorily concluded in the summer of 1983. This SPDV program permits confirmation of subsurface geology, in drifts at planned facility depth that extend for 1555 m in a north-south direction, and in the two vertical shafts that provide access to these drifts. The subsurface studies are nearing completion, and it is therefore appropriate to draw conclusions regarding the geotechnical acceptability of the WIPP site. Four geotechnical elements are discussed: dissolution, deformation, hydrologic regime, and natural resources

  17. General criteria for radioactive waste disposal

    International Nuclear Information System (INIS)

    Maxey, M.N.; Musgrave, B.C.; Watkins, G.B.

    1979-01-01

    Techniques are being developed for conversion of radioactive wastes to solids and their placement into repositories. Criteria for such disposal are needed to assure protection of the biosphere. The ALARA (as low as reasonably achievable) principle should be applicable at all times during the disposal period. Radioactive wastes can be categorized into three classes, depending on the activity. Three approaches were developed for judging the adequacy of disposal concepts: acceptable risk, ore body comparison, and three-stage ore body comparison

  18. Use of an Acceptance and Mindfulnessbased Stress Management Workshop Intervention with support staff caring for individuals with intellectual disabilities

    OpenAIRE

    McConachie, Douglas

    2012-01-01

    Introduction: Support staff working with individuals with intellectual disability (ID) and challenging behaviour experience high levels of work-related stress. Preliminary theoretical and experimental research has highlighted the potential suitability of acceptance and mindfulness approaches for addressing support staff stress. This study examines the effectiveness of an acceptance and mindfulness-based stress management workshop on the levels of psychological distress and well...

  19. Emotional and Spiritual Quotient Approach Improve Biology Education Students’ Acceptance of Evolution Theory

    Science.gov (United States)

    Darussyamsu, R.; Fadilah, M.; Putri, D. H.

    2018-04-01

    Emotional and spiritual aspect is one of main factors that influence students’ acceptance of a theory. This study aim to measure university students’ acceptance of evolution by learns evolution using emotional and spiritual quotient (ESQ) approach. This is a quasi-experimental research using one shot case study design with the subject 36 biology educational students at Biology Department, Faculty of Mathematics and Natural Science, Universitas Negeri Padang. Data collected using the MATE instrument by Rutledge and Warden (2000) after the students learn evolution for eight meetings since January until March 2017. The result showed that by learning evolution theory combine with ESQ aspects increase students acceptance from very low become moderate acceptance. It concluded that ESQ aspects can improve students’ acceptance of evolution. Any criteria depend on it are discussed.

  20. The use of fracture mechanics for the evaluation of NDE flaw acceptance standards

    Energy Technology Data Exchange (ETDEWEB)

    Alicino, A; Capurro, E; Ansaldo, Sp; Corvi, A [Ansaldo SpA, Genoa (Italy)

    1988-12-31

    This document deals with the use of fracture mechanics criteria to evaluate the Non Destructive Examination (NDE) flaw acceptance standards. The communication discusses the general schemes and the guidelines of the activity carried out. (TEC).

  1. AAPT Diagnostic Criteria for Chronic Cancer Pain Conditions

    OpenAIRE

    Paice, Judith A.; Mulvey, Matt; Bennett, Michael; Dougherty, Patrick M.; Farrar, John T.; Mantyh, Patrick W.; Miaskowski, Christine; Schmidt, Brian; Smith, Thomas J.

    2016-01-01

    Chronic cancer pain is a serious complication of malignancy or its treatment. Currently, no comprehensive, universally accepted cancer pain classification system exists. Clarity in classification of common cancer pain syndromes would improve clinical assessment and management. Moreover, an evidence-based taxonomy would enhance cancer pain research efforts by providing consistent diagnostic criteria, ensuring comparability across clinical trials. As part of a collaborative effort between the A...

  2. The feasibility, acceptability and preliminary efficacy of a low-cost, virtual-reality based, upper-limb stroke rehabilitation device: a mixed methods study.

    Science.gov (United States)

    Warland, Alyson; Paraskevopoulos, Ioannis; Tsekleves, Emmanuel; Ryan, Jennifer; Nowicky, Alexander; Griscti, Josephine; Levings, Hannah; Kilbride, Cherry

    2018-04-12

    To establish feasibility, acceptability, and preliminary efficacy of an adapted version of a commercially available, virtual-reality gaming system (the Personalised Stroke Therapy system) for upper-limb rehabilitation with community dwelling stroke-survivors. Twelve stroke-survivors (nine females, mean age 58 years, [standard deviation 7.1], median stroke chronicity 42 months [interquartile range 34.7], Motricity index 14-25 for shoulder and elbow) were asked to complete nine, 40-min intervention sessions using two activities on the system over 3 weeks. Feasibility and acceptability were assessed through a semi-structured interview, recording of adverse effects, adherence, enjoyment (using an 11-point Likert scale), and perceived exertion (using the BORG scale). Assessments of impairment (Fugl-Meyer Assessment Upper extremity), activity (ABILHAND, Action Research Arm Test, Motor Activity Log-28), and participation (Subjective Index of Physical and Social Outcome) were completed at baseline, following intervention, and at 4-week follow-up. Data were analysed using Thematic Analysis of interview and intervention field-notes and Wilcoxon Signed Ranks. Side-by-side displays were used to integrate findings. Participants received between 175 and 336 min of intervention. Thirteen non-serious adverse effects were reported by five participants. Participants reported a high level of enjoyment (8.1 and 6.8 out of 10) and rated exertion between 11.6 and 12.9 out of 20. Themes of improvements in impairments and increased spontaneous use in functional activities were identified and supported by improvements in all outcome measures between baseline and post-intervention (p technologies for use in upper-limb stroke rehabilitation should be personalised, dependent on individual need. Through the use of hands-free systems and personalisation, stroke survivors with moderate and moderately-severe levels of upper-limb impairment following stroke are able to use gaming technologies

  3. Bayesian predictive risk modeling of microbial criteria for Campylobacter in broilers

    DEFF Research Database (Denmark)

    Nauta, Maarten; Ranta, J.; Mikkelä, A.

    Microbial Criteria define the acceptability of food products, based on the presence or detected number of microorganisms in samples. The criteria are applied at the level of defined food lots. Generally, these are interpreted as statistical batches representing the production [1]. The batches...... be assessed by computing posterior distribution of the parameters - a Bayesian evidence synthesis. The outcome of a defined Microbial Criterion (MC) for a batch provides additional evidence concerning the batch. Posterior predictive consumer risk (probability of illness) was computed for such batch...

  4. SARDA HITL Preliminary Human Factors Measures and Analyses

    Science.gov (United States)

    Hyashi, Miwa; Dulchinos, Victoria

    2012-01-01

    Human factors data collected during the SARDA HITL Simulation Experiment include a variety of subjective measures, including the NASA TLX, questionnaire questions regarding situational awareness, advisory usefulness, UI usability, and controller trust. Preliminary analysis of the TLX data indicate that workload may not be adversely affected by use of the advisories, additionally, the controller's subjective ratings of the advisories may suggest acceptance of the tool.

  5. Quality criteria for landscape visualisation

    International Nuclear Information System (INIS)

    Waldi, H.-P.; Witt, U. de

    1996-01-01

    The rapid expansion of wind energy utilisation in Western Europe can strain the limits of social acceptance with citizens living in wind development areas. One of the problems wind farm engineers and local authorities face is the visual impact of wind turbines. To determine the influence on the landscape visualisations of wind farms photorealistic compositions are used. In many cases it is part of the planning procedure. The quality of this visualization can strongly influence the success of the permission procedure. We will give criteria which can give help to reduce the possibility of unwanted manipulations. (author)

  6. Frequency limitations on reactor release derived from radiological criteria

    International Nuclear Information System (INIS)

    Clarke, R.H.

    1976-05-01

    Acceptable frequencies are suggested with which a number of defined individual and collective dose criteria are met. This has enabled a relationship to be proposed between the frequency and any event leading to release of radioactive material and the dose commitment to the hypothetical individual at the site boundary. The philosphy developed is generally applicable, but in this instance it has been demonstrated for an SGHW Reactor located at Sizewell. The results are derived on the basis of an acceptable level of risk of fatality to the most exposed individual and the application of the methodology to other reactor types and sites is demonstrated. (author)

  7. Uncontrolled pilot study of an Acceptance and Commitment Therapy and Health at Every Size intervention for obese, depressed women: Accept Yourself!

    Science.gov (United States)

    Berman, Margit I; Morton, Stephanie N; Hegel, Mark T

    2016-12-01

    Depression and obesity frequently co-occur, but providing adequate treatment to depressed obese women is challenging because existing treatments for each problem in isolation are suboptimal, and treatments to address one problem may exacerbate the other. This study used an uncontrolled, pretreatment-to-posttreatment design, with 3-month follow-up, to evaluate the feasibility and outcome of a novel, self-acceptance-based treatment for obese women with depression, "Accept Yourself!" Accept Yourself! is an 11-week manualized, group-based intervention that integrates Health At Every Size (an evidence-based paradigm to enhance physical health) and Acceptance and Commitment Therapy (an evidence-based psychotherapy often used to treat depression and eating-related concerns) to improve the physical and mental health of obese, depressed women without encouraging weight loss. Twenty-one obese women with Major Depressive Disorder received the intervention; 18 completed at least seven sessions, a minimal dose of the intervention. Depressive symptoms, depression diagnosis, physical health outcomes (including physical activity and blood pressure), and obesity-related quality of life were assessed at baseline, posttreatment, and 3-month follow-up. Weight was also monitored. Depression, blood pressure, and obesity-related quality of life significantly improved from pretreatment to posttreatment, and improvements were sustained over a 3-month follow-up. Participants did not gain significant weight during the intervention or at follow-up. These data, although preliminary and nonexperimental, suggest that Accept Yourself! could be a promising treatment for obese, depressed women, and support the value of larger randomized controlled trials. (PsycINFO Database Record (c) 2016 APA, all rights reserved).

  8. Draft principles, policy, and acceptance criteria for decommissioning of U.S. Department of Energy contaminated surplus facilities and summary of international decommissioning programs

    International Nuclear Information System (INIS)

    Singh, B.K.

    1994-12-01

    Decommissioning activities enable the DOE to reuse all or part of a facility for future activities and reduce hazards to the general public and any future work force. The DOE Office of Environment, Health and Safety has prepared this document, which consists of decommissioning principles and acceptance criteria, in an attempt to establish a policy that is in agreement with the NRC policy. The purpose of this document is to assist individuals involved with decommissioning activities in determining their specific responsibilities as identified in Draft DOE Order 5820.DDD, ''Decommissioning of US Department of Energy Contaminated Surplus Facilities'' (Appendix A). This document is not intended to provide specific decommissioning methodology. The policies and principles of several international decommissioning programs are also summarized. These programs are from the IAEA, the NRC, and several foreign countries expecting to decommission nuclear facilities. They are included here to demonstrate the different policies that are to be followed throughout the world and to allow the reader to become familiar with the state of the art for environment, safety, and health (ES and H) aspects of nuclear decommissioning

  9. Risk analysis and risk acceptance criteria in the planning processes of hazardous facilities-A case of an LNG plant in an urban area

    International Nuclear Information System (INIS)

    Vinnem, Jan Erik

    2010-01-01

    Planning of hazardous facilities is usually carried out on the basis of a risk-informed decision-making and planning process making use of risk analysis. This practice is well established in Norway under petroleum legislation but less so for onshore facilities under non-petroleum legislation. The present paper focuses on the use of risk analysis studies for risk evaluation against risk acceptance criteria, risk communication and derivation of technical and operational requirements in these circumstances. This is demonstrated through reference to a case study involving an LNG plant currently under construction in an urban area in Norway. The main finding is that risk-informed legislation is a fragile legislative system which is dependent on conscientious and open-minded use by the industrial developer. In the opposite case, the authorities may well be unable to correct the situation and the legislation may fail to protect the neighbourhood from unreasonable exposure to risk. Reference is also made to the international perspective where authorities define what is deemed tolerable risk, which would appear to be a more robust and defensible approach.

  10. A proposal of criteria for the classification of systemic sclerosis.

    Science.gov (United States)

    Nadashkevich, Oleg; Davis, Paul; Fritzler, Marvin J

    2004-11-01

    Sensitive and specific criteria for the classification of systemic sclerosis are required by clinicians and investigators to achieve higher quality clinical studies and approaches to therapy. A clinical study of systemic sclerosis patients in Europe and Canada led to a set of criteria that achieve high sensitivity and specificity. Both clinical and laboratory investigations of patients with systemic sclerosis, related conditions and diseases with clinical features that can be mistaken as part of the systemic sclerosis spectrum were undertaken. Laboratory investigations included the detection of autoantibodies to centromere proteins, Scl-70 (topoisomerase I), and fibrillarin (U3-RNP). Based on the investigation of 269 systemic sclerosis patients and 720 patients presenting with related and confounding conditions, the following set of criteria for the classification of systemic sclerosis was proposed: 1) autoantibodies to: centromere proteins, Scl-70 (topo I), fibrillarin; 2) bibasilar pulmonary fibrosis; 3) contractures of the digital joints or prayer sign; 4) dermal thickening proximal to the wrists; 5) calcinosis cutis; 6) Raynaud's phenomenon; 7) esophageal distal hypomotility or reflux-esophagitis; 8) sclerodactyly or non-pitting digital edema; 9) teleangiectasias. The classification of definite SSc requires at least three of the above criteria. Criteria for the classification of systemic sclerosis have been proposed. Preliminary testing has defined the sensitivity and specificity of these criteria as high as 99% and 100%, respectively. Testing and validation of the proposed criteria by other clinical centers is required.

  11. Automatically generated acceptance test: A software reliability experiment

    Science.gov (United States)

    Protzel, Peter W.

    1988-01-01

    This study presents results of a software reliability experiment investigating the feasibility of a new error detection method. The method can be used as an acceptance test and is solely based on empirical data about the behavior of internal states of a program. The experimental design uses the existing environment of a multi-version experiment previously conducted at the NASA Langley Research Center, in which the launch interceptor problem is used as a model. This allows the controlled experimental investigation of versions with well-known single and multiple faults, and the availability of an oracle permits the determination of the error detection performance of the test. Fault interaction phenomena are observed that have an amplifying effect on the number of error occurrences. Preliminary results indicate that all faults examined so far are detected by the acceptance test. This shows promise for further investigations, and for the employment of this test method on other applications.

  12. Improving International-Level Chess Players' Performance with an Acceptance-Based Protocol: Preliminary Findings

    Science.gov (United States)

    Ruiz, Francisco J.; Luciano, Carmen

    2012-01-01

    This study compared an individual, 4-hr intervention based on acceptance and commitment therapy (ACT) versus a no-contact control condition in improving the performance of international-level chess players. Five participants received the brief ACT protocol, with each matched to another chess player with similar characteristics in the control…

  13. Screening Criteria and Considerations of Offshore Enhanced Oil Recovery

    Directory of Open Access Journals (Sweden)

    Pan-Sang Kang

    2016-01-01

    Full Text Available The application of enhanced oil recovery (EOR in offshore oil fields has received significant attention due to the potentially enormous amount of recoverable oil. However, EOR application offshore is in its very early stage due to conditions that are more complex than onshore oil fields, owing to the unique parameters present offshore. Therefore, successful EOR applications in offshore oil fields require different screening criteria than those for conventional onshore applications. A comprehensive database for onshore applications of EOR processes together with a limited offshore EOR application database are analyzed in this paper, and the important parameters for successful offshore application are incorporated into the new EOR screening criteria. In this paper, screening criteria to determine acceptable EOR processes for offshore fields, including hydrocarbon gas miscible, CO2 miscible, and polymer processes, are presented. Suggested screening criteria for these EOR processes comprise quantitative boundaries and qualitative considerations. Quantitative screening criteria are predominantly based on quantifiable data, such as oil and reservoir properties. Qualitative screening considerations mainly focus on the operational issues present offshore, including platform space constraints, limited disposal options, injectant availability, and flow assurance matters (including hydrate formation and difficulties in emulsion separation.

  14. Criteria impacting shipments of Rocky Flats Plant radioactive mixed wastes

    International Nuclear Information System (INIS)

    Clawson, R.L.; Eide, J.H.

    1992-05-01

    Westinghouse Hanford Company, Transportation and Packaging Division, under contract for the Los Alamos Technology Office-Rocky Flats Plant, has developed this synopsis report to be used as a reference in the development of the Rocky Flats Plant Comprehensive Treatment and Management Plan and the Rocky Flats Plant Residue Elimination Plan. This report represents the criteria for packaging, shipping, and transporting Rocky Flats Plant radioactive mixed wastes. It is a compilation of state and federal regulations, US Department of Energy orders, and acceptance criteria specific to US Department of Energy radioactive mixed waste treatment, storage and disposal facilities

  15. Seismic design and evaluation criteria based on target performance goals

    International Nuclear Information System (INIS)

    Murray, R.C.; Nelson, T.A.; Kennedy, R.P.; Short, S.A.

    1994-04-01

    The Department of Energy utilizes deterministic seismic design/evaluation criteria developed to achieve probabilistic performance goals. These seismic design and evaluation criteria are intended to apply equally to the design of new facilities and to the evaluation of existing facilities. In addition, the criteria are intended to cover design and evaluation of buildings, equipment, piping, and other structures. Four separate sets of seismic design/evaluation criteria have been presented each with a different performance goal. In all these criteria, earthquake loading is selected from seismic hazard curves on a probabilistic basis but seismic response evaluation methods and acceptable behavior limits are deterministic approaches with which design engineers are familiar. For analytical evaluations, conservatism has been introduced through the use of conservative inelastic demand-capacity ratios combined with ductile detailing requirements, through the use of minimum specified material strengths and conservative code capacity equations, and through the use of a seismic scale factor. For evaluation by testing or by experience data, conservatism has been introduced through the use of an increase scale factor which is applied to the prescribed design/evaluation input motion

  16. Some problems in the acceptability of implementing radiation protection programs

    International Nuclear Information System (INIS)

    Neill, R.H.

    1997-01-01

    The three fundamentals that radiation protection programs are based upon are; 1) establishing a quantitative correlation between radiation exposure and biological effects in people; 2) determining a level of acceptable risk of exposure; and 3) establishing systems to measure the radiation dose to insure compliance with the regulations or criteria. The paper discusses the interrelationship of these fundamentals, difficulties in obtaining a consensus of acceptable risk and gives some examples of problems in identifying the most critical population-at-risk and in measuring dose. Despite such problems, it is recommended that we proceed with the existing conservative structure of radiation protection programs based upon a linear no threshold model for low radiation doses to insure public acceptability of various potential radiation risks. Voluntary compliance as well as regulatory requirements should continue to be pursued to maintain minimal exposure to ionizing radiation. (author)

  17. Study on Influencing Factor Analysis and Application of Consumer Mobile Commerce Acceptance

    Science.gov (United States)

    Li, Gaoguang; Lv, Tingjie

    Mobile commerce (MC) refers to e-commerce activities carried out using a mobile device such as a phone or PDA. With new technology, MC will be rapidly growing in the near future. At the present time, what factors making consumer accept MC and what MC applications are acceptable by consumers are two of hot issues both for MC providers and f or MC researchers. This study presents a proposed MC acceptance model that integrates perceived playfulness, perceived risk and cost into the TAM to study which factors affect consumer MC acceptance. The proposed model includes five variables, namely perceived risk, cost, perceived usefulness, perceived playfulness, perceived ease of use, perceived playfulness. Then, using analytic hierarchy process (AHP) to calculate weight of criteria involved in proposed model. Finally, the study utilizes fuzzy comprehensive evaluation method to evaluate MC applications accepted possibility, and then a MC application is empirically tested using data collected from a survey of MC consumers.

  18. A proposed acceptance process for commercial off-the-shelf (COTS) software in reactor applications

    International Nuclear Information System (INIS)

    Preckshot, G.G.; Scott, J.A.

    1996-03-01

    This paper proposes a process for acceptance of commercial off-the-shelf (COTS) software products for use in reactor systems important to safety. An initial set of four criteria establishes COTS software product identification and its safety category. Based on safety category, three sets of additional criteria, graded in rigor, are applied to approve/disapprove the product. These criteria fall roughly into three areas: product assurance, verification of safety function and safety impact, and examination of usage experience of the COTS product in circumstances similar to the proposed application. A report addressing the testing of existing software is included as an appendix

  19. Seismic design and evaluation criteria for DOE facilities (DOE-STD-1020-XX)

    International Nuclear Information System (INIS)

    Short, S.A.; Kennedy, R.P.; Murray, R.C.

    1993-01-01

    Seismic design and evaluation criteria for DOE facilities are provided in DOE-STD-1020-XX. The criteria include selection of design/evaluation seismic input from probabilistic seismic hazard curves combined with commonly practiced deterministic response evaluation methods and acceptance criteria with controlled levels of conservatism. Conservatism is intentionally introduced in specification of material strengths and capacities, in the allowance of limited inelastic behavior and by a seismic load factor. These criteria are based on the performance or risk goals specified in DOE 5480.28. Criteria have been developed following a graded approach for several performance goals ranging from that appropriate for normal-use facilities to that appropriate for facilities involving hazardous or critical operations. Performance goals are comprised of desired behavior and of the probability of not achieving that behavior. Following the seismic design/evaluation criteria of DOE-STD-1020-XX is sufficient to demonstrate that the probabilistic performance or risk goals are achieved. The criteria are simple procedures but with a sound, rigorous basis for the achievement of goals

  20. The Predictive Value of Selection Criteria in an Urban Magnet School

    Science.gov (United States)

    Lohmeier, Jill Hendrickson; Raad, Jennifer

    2012-01-01

    The predictive value of selection criteria on outcome data from two cohorts of students (Total N = 525) accepted to an urban magnet high school were evaluated. Regression analyses of typical screening variables (suspensions, absences, metropolitan achievement tests, middle school grade point averages [GPAs], Matrix Analogies test scores, and…

  1. Idaho National Engineering Laboratory release criteria for decontamination and decommissioning

    International Nuclear Information System (INIS)

    Dolenc, M.R.; Case, M.J.

    1986-01-01

    Criteria have been developed for release of Idaho National Engineering Laboratory (INEL) facilities and land areas following decontamination and decommissioning (D and D). Decommissioning release criteria in the form of dose guidelines were proposed by the US Nuclear Regulatory Commission as early as 1980. These criteria were used on an interim basis for INEL D and D projects. However, dose guidelines alone do not adequately cover the criteria necessary to release sites for unrestricted use. In actual practice, other parameters such as pathways analyses, sampling and instrumentation techniques, and implementation procedures are required to develop the basis for unrestricted release of a site. Thus, a rigorous approach for evaluating these other parameters is needed to develop acceptable D and D release criteria. Because of the complex and sensitive nature of the dose and pathways analyses work, a thorough review by experts in those respective fields was desired. Input and support in preparing or reviewing each part of the criteria development task was solicited from several DOE field offices. Experts were identified and contracted to assist in preparing portions of the release criteria, or to serve on a peer-review committee. Thus, the entire release criteria development task was thoroughly reviewed by recognized experts from each DOE field office, to validate technical content of the INEL site-specific document

  2. A preliminary analysis of the reactor-based plutonium disposition alternative deployment schedules

    International Nuclear Information System (INIS)

    Zurn, R.M.

    1997-09-01

    This paper discusses the preliminary analysis of the implementation schedules of the reactor-based plutonium disposition alternatives. These schedule analyses are a part of a larger process to examine the nine decision criteria used to determine the most appropriate method of disposing of U.S. surplus weapons plutonium. The preliminary analysis indicates that the mission durations for the reactor-based alternatives range from eleven years to eighteen years and the initial mission fuel assemblies containing surplus weapons-usable plutonium could be loaded into the reactors between nine and fourteen years after the Record of Decision

  3. Preliminary safety assessment and preliminary safety report for the treated radwaste store, Winfrith

    International Nuclear Information System (INIS)

    Staples, A.T.

    1992-06-01

    It is the purpose of this assessment to define the categorisation of the Treated Radwaste Store, TRS, B55 at the Winfrith Technology Centre. Its further purpose is to cover all relevant sections required for a Preliminary Safety Report (PSR) encompassing the TRS and the integral Quality Assessment Unit (QUA). The TRS is designed for the interim storage of intermediate level radioactive wastes. All waste material stored in the TRS will be contained within 500 litre stainless steel drums acceptable to NIREX. It is proposed that the TRS will receive 500 litre stainless steel NIREX drums containing either irradiated DRAGON fuel or encapsulated sludge waste. (author)

  4. Extending the foreign spent fuel acceptance program: Policy and implementation issues

    International Nuclear Information System (INIS)

    Lyman, Edwin S.

    2005-01-01

    The May 2006 expiration date of the Foreign Research Reactor Spent Nuclear Fuel (FRR SNF) Acceptance Program is fast approaching. In April 2004, Energy Secretary Spencer Abraham instructed the Energy Department to 'initiate actions necessary to extend .... the fuel acceptance deadline'. However, extending the deadline may not be a simple task. The limits on the original program resulted from a delicate negotiation among many stakeholders. Any proposal to increase the duration and scope of the program will have to be considered in the context of DOE's failure since 1996 to develop viable treatment, packaging and long-term disposal options for FRR SNF. It is also unclear whether accepting additional low-enriched uranium FRR SNF can be justified on security grounds. This paper will propose criteria for acceptance of spent fuel under an extension that are intended to minimize controversy and ensure consistency with a threat-based prioritization of homeland security expenditures. (author)

  5. Establishing endangered species recovery criteria using predictive simulation modeling

    Science.gov (United States)

    McGowan, Conor P.; Catlin, Daniel H.; Shaffer, Terry L.; Gratto-Trevor, Cheri L.; Aron, Carol

    2014-01-01

    Listing a species under the Endangered Species Act (ESA) and developing a recovery plan requires U.S. Fish and Wildlife Service to establish specific and measurable criteria for delisting. Generally, species are listed because they face (or are perceived to face) elevated risk of extinction due to issues such as habitat loss, invasive species, or other factors. Recovery plans identify recovery criteria that reduce extinction risk to an acceptable level. It logically follows that the recovery criteria, the defined conditions for removing a species from ESA protections, need to be closely related to extinction risk. Extinction probability is a population parameter estimated with a model that uses current demographic information to project the population into the future over a number of replicates, calculating the proportion of replicated populations that go extinct. We simulated extinction probabilities of piping plovers in the Great Plains and estimated the relationship between extinction probability and various demographic parameters. We tested the fit of regression models linking initial abundance, productivity, or population growth rate to extinction risk, and then, using the regression parameter estimates, determined the conditions required to reduce extinction probability to some pre-defined acceptable threshold. Binomial regression models with mean population growth rate and the natural log of initial abundance were the best predictors of extinction probability 50 years into the future. For example, based on our regression models, an initial abundance of approximately 2400 females with an expected mean population growth rate of 1.0 will limit extinction risk for piping plovers in the Great Plains to less than 0.048. Our method provides a straightforward way of developing specific and measurable recovery criteria linked directly to the core issue of extinction risk. Published by Elsevier Ltd.

  6. International Political Actorness of the European Union: Evaluation Criteria

    Directory of Open Access Journals (Sweden)

    GNATYUK N.N.

    2014-06-01

    Full Text Available The European Union is a completely new international entity which is hard to evaluate using traditional criteria of political actorness. Its active international presence stimulates the modeling of international actor features beyond the scope of “state-international organization” scheme. The concept of international actorness serves as a starting point for the development of appropriate analytical model. Unlike the traditional state-centered approaches which define an international actor through its affiliation witch the international system, this concept operates at the internal level of international entity and at the international structure level. Furthermore, both of these levels are treated as ontologically neutral and mutually constitutive. This basic theoretical scheme is used for elaboration of evaluation criteria of political actorness. The proposed system of criteria is based on drawing, synthesizing and developing the main writings on “new international actors” since the times of classic work by Carol A. Cosgrove and Kenneth J. Twitchett. The key elements of actorness assessed in this article include defining of capacity to act on the global scene as well as the acceptance by other actors and by international system as a whole. At the internal level, the EU’s actor capacity is measured by assessing its core elements ranging from core aspects, such as autonomy, authority, actor capability, coherence and cohesion to identity aspects. On the external level, the decisive criteria are recognition and acceptance by others which reflect expectations and perceptions of the EU. The proposed approach of evaluating the international actorness enables us to consider the political activity of the EU on the basis of coordinated system of interaction between the variables of international and domestic levels of the analysis. Furthermore, this contributes to the development of cumulative, coherent, and comprehensive theory of international

  7. MULTIPLE CRITERIA DECISION MAKING IN STRATEGIC PLANNING OF TABLE EGG PRODUCTION

    Directory of Open Access Journals (Sweden)

    Ana Crnčan

    2016-06-01

    Full Text Available The main research objective was to analyze and evaluate different systems of table egg production by using the multiple criteria analysis, the method of Analytic Hierarchy Process (AHP in decision making within strategic planning of production. The survey involved 79 producers of table eggs registered in the Records on laying hens’ farms in the Republic of Croatia. In the first stage, the research defined the criteria and sub-criteria for system evaluation which were compared in pairs in order to determine the weight or importance for each of them. Alternatives were evaluation based on definition of priorities of examinees and the extent to which they meet each of the defined criteria and sub-criteria. Intensity of examinees’ preferences were entered into the Expert Choice software in order to evaluate ranking results of egg production systems. Defined model consisted of a quantitative criterion of economic indicators, and the other two referred to qualitative criteria, market indicators and technical-technological factors. Each criterion had its corresponding sub-criteria that were evenly distributed in numerical order. Based on individual assessments of the examinees, overall cumulative evaluation was obtained for the table egg production systems. Accordingly, the most acceptable alternative to egg production is the indoor keeping system (priority 0.301. It is followed by the free-range system of keeping laying hens (priority 0.253. The third-ranked alternative is egg production by hens kept in conventional cages (priority 0.226, while the fourth-ranked least acceptable alternative, as of the total evaluation, is the ecological system of egg production (priority 0.220. Taking into account the obtained results of multiple criteria evaluation as well as EU and world trends in changing consumers’ habits including food safety and quality as well as customers’ preferences towards local market and local products, it is recommended that eggs

  8. Advances in seismic criteria to qualify structures, systems and components in operating reactors

    International Nuclear Information System (INIS)

    Manrique, M.A.; Bak, W.R.

    1989-01-01

    This paper describes improved seismic evaluation criteria and analysis methodologies used as part of the seismic reevaluation of San Onofre Nuclear Generating Station, Unit 1. The plant had originally been designed for 0.25 g ground acceleration and was required to be upgraded to a 0.67 g ground acceleration as part of the plant's Long Term Service Seismic Reevaluation Program. The application of the criteria and methods described in this paper to demonstrate the seismic capability of the plant resulted in efficient plant modifications with considerable cost savings to the plant owner. The NRC accepted these criteria and methods based on favorable results of reviews, audits and independent verification of the theories, bases and implementation procedures of the proposed criteria and analysis methods

  9. Nuclear reactor philosophy and criteria

    International Nuclear Information System (INIS)

    Atchison, R.J.

    1979-07-01

    Nuclear power plant safety criteria and principles developed in Canada are directed towards minimizing the chance of failure of the fuel and preventing or reducing to an acceptably low level the escape of fission products should fuel failure occur. Safety criteria and practices are set forth in the Reactor Siting Guide, which is based upon the concept of defence in depth. The Guide specifies that design and construction shall follow the best applicable code, standard or practice; the total of all serious process system failures shall not exceed one in three years; special safety systems are to be physically and functionally separate from process systems and each other; and safety systems shall be testable, with unavailability less than 10 - 3 . Doses to the most exposed member of the public due to normal operation, serious process failures, and dual failures are specified. Licensees are also required to consider the effects of extreme conditions due to airplane crashes, explosions, turbine disintegration, pipe burst, and natural disasters. Safety requirements are changing as nuclear power plant designs evolve and in response to social and economic pressures

  10. Development of Preliminary Remission Criteria for Gout Using Delphi and 1000Minds® Consensus Exercises

    DEFF Research Database (Denmark)

    de Lautour, Hugh; Taylor, William J; Adebajo, Ade

    2016-01-01

    OBJECTIVES: The aim of this study was to establish consensus for potential remission criteria for use in clinical trials of gout. METHODS: Experts (n=88) in gout from multiple countries were invited to participate in a web-based questionnaire study. Three rounds of Delphi consensus exercises were...... months (51%) and one year (49%). In the discrete choice experiment, there was a preference towards 12 months as a timeframe for remission. CONCLUSION: These consensus exercises have identified domains and provisional definitions for gout remission criteria. Based on the results of these exercises...

  11. Acceptability and preliminary feasibility of an internet/CD-ROM-based education and decision program for early-stage prostate cancer patients: randomized pilot study.

    Science.gov (United States)

    Diefenbach, Michael A; Mohamed, Nihal E; Butz, Brian P; Bar-Chama, Natan; Stock, Richard; Cesaretti, Jamie; Hassan, Waleed; Samadi, David; Hall, Simon J

    2012-01-13

    Prostate cancer is the most common cancer affecting men in the United States. Management options for localized disease exist, yet an evidence-based criterion standard for treatment still has to emerge. Although 5-year survival rates approach 98%, all treatment options carry the possibility for significant side effects, such as erectile dysfunction and urinary incontinence. It is therefore recommended that patients be actively involved in the treatment decision process. We have developed an Internet/CD-ROM-based multimedia Prostate Interactive Educational System (PIES) to enhance patients' treatment decision making. PIES virtually mirrors a health center to provide patients with information about prostate cancer and its treatment through an intuitive interface, using videos, animations, graphics, and texts. (1) To examine the acceptability and feasibility of the PIES intervention and to report preliminary outcomes of the program in a pilot trial among patients with a new prostate cancer diagnosis, and (2) to explore the potential impact of tailoring PIES treatment information to participants' information-seeking styles on study outcomes. Participants (n = 72) were patients with newly diagnosed localized prostate cancer who had not made a treatment decision. Patients were randomly assigned to 3 experimental conditions: (1) control condition (providing information through standard National Cancer Institute brochures; 26%), and PIES (2) with tailoring (43%) and (3) without tailoring to a patient's information-seeking style (31%). Questionnaires were administrated before (t1) and immediately after the intervention (t2). Measurements include evaluation and acceptability of the PIES intervention, monitoring/blunting information-seeking style, psychological distress, and decision-related variables (eg, decisional confidence, feeling informed about prostate cancer and treatment, and treatment preference). The PIES program was well accepted by patients and did not interfere

  12. Self-perceived competence and social acceptance of young children who stutter: Initial findings.

    Science.gov (United States)

    Hertsberg, Naomi; Zebrowski, Patricia M

    The goals of this study were to determine whether young children who stutter (CWS) perceive their own competence and social acceptance differently than young children who do not stutter (CWNS), and to identify the predictors of perceived competence and social acceptance in young speakers. We administered the Pictorial Scale of Perceived Competence and Social Acceptance for Young Children (PSPCSA; Harter & Pike, 1984) to 13 CWS and 14 CWNS and examined group differences. We also collected information on the children's genders, temperaments, stuttering frequencies, language abilities, and phonological skills to identify which of these factors predicted PSPCSA scores. CWS, as a group, did not differ from CWNS in their perceived general competence or social acceptance. Gender predicted scores of perceived general competence, and stuttering frequency predicted perceived social acceptance. Temperament, language abilities, and phonological skills were not significant predictors of perceived competence or social acceptance in our sample. While CWS did not significantly differ from CWNS in terms of perceived competence and social acceptance, when both talker groups were considered together, girls self-reported greater perceived competence than boys. Further, lower stuttering frequency was associated with greater perceived social acceptance. These preliminary findings provide motivation for further empirical study of the psychosocial components of childhood stuttering. Readers will be able to describe the constructs of perceived competence and social acceptance in young children, and whether early stuttering plays a role in the development of these constructs. Copyright © 2016 Elsevier Inc. All rights reserved.

  13. Most Scottish neurologists do not apply the 2010 McDonald criteria when diagnosing multiple sclerosis.

    Science.gov (United States)

    Lumley, R; Davenport, R; Williams, A

    2015-03-01

    The diagnostic criteria for multiple sclerosis have evolved over time and currently the 2010 McDonald criteria are the most widely accepted. These criteria allow the diagnosis of multiple sclerosis to be made at the clinically isolated syndrome stage provided certain criteria are met on a single magnetic resonance brain scan. Our hypothesis was that neurologists in Scotland did not use these criteria routinely. We sent a SurveyMonkey questionnaire to all Scottish neurologists (consultants and trainees) regarding the diagnosis of multiple sclerosis. Our questionnaire response rate was 65/99 (66%). Most Scottish neurologists were aware of the criteria and 31/58 (53%) felt that they were using these routinely. However, in a clinical vignette designed to test the application of these criteria, only 5/57 (9%) of neurologists appeared to use them. Scottish neurologists' use of the 2010 McDonald criteria for diagnosis of multiple sclerosis varies from practitioners' perception of their use of these criteria.

  14. Acceptance-criteria for the bedrock for deep geologic disposal of spent nuclear fuel. Proceedings from a seminar at Gothenburg University

    International Nuclear Information System (INIS)

    1995-11-01

    The seminar was directed to Nordic participants, and discussed disposal in the Nordic crystalline bedrock. Criteria for the bedrock should include: It should give durable mechanical protection for the engineered barriers; give a stable and favorable chemical environment for these barriers; have a low turnover of ground water in the near field; be easy to characterize; give favorable recipient-conditions; not have valuable minerals in workable quantities. These general criteria raise several questions coupled to the safety analysis: e.g. the need for geological, hydrological and geochemical parameters. Which data are missing, which are most difficult to find? What should the site characterization program look like to focus on factors that are of the highest importance according to the safety analysis. The demands on the conditions at a site need to be translated into quantitative criteria, which should be expressed as values that can be measured at the site or deduced from such measurements. These questions were discussed at the seminar, and 21 contributions from Finnish, Norwegian and Swedish participants are reported in these proceedings under the chapters: Coupling to the safety analysis; Methodology and criteria for site selection in a regional geoscientific perspective; Rock as a building material - prognosis and result; Geoscientific criteria for the bedrock at the repository - Mechanical protection; Geoscientific criteria for the bedrock at the repository - Low ground water turnover, chemically favorable and stable environment in the near field; Geoscientific criteria for the bedrock at the repository - Demands on the bedrock concerning the migration of radionuclides

  15. Proposed approach to derivation of acceptance criteria for disposal of disused sealed sources mixed with other accepted wastes in near-surface repository

    International Nuclear Information System (INIS)

    Salzer, P.; Stefula, V.; Homola, J.

    2003-01-01

    The Mochovce repository is described in the report. It is vault type near surface repository with 80 concrete vaults (2x2x20), 90 FRC containers (3.1 m 3 ) in one vault (3x10x3), compacted clay bath-tub around double row. 300 years of institutional control are envisioned.The following scenarios are examined: Normal evolution scenario; Alternative evolution scenarios (perforated clay barrier; well in close proximity); Intruder scenarios (construction of simple dwelling; construction of multi-storey building; construction of road; residence scenario). It is being proposed that the DSSs are disposed of in the containers together with normal operational waste. Long-lived alpha emitters - excluded a priori (e.g. 226 Ra); Short-lived (T 1/2 = 10 2 days) radionuclides - interim stored until decayed down to clearance level 60 Co - no activity limit, with due consideration of operational safety. The DSSs disposal issue is thus reduced to the disposal of 137 Cs. No limit has been imposed on total activity. Existing limits for operational waste: 3.13.10 13 Bq / container in the upper layer; 3.41.10 13 Bq / container in the bottom or intermediate layer. The acceptance criteria are assessed according to the risk. Two are models set up in MicroShield ver. 5.0. Homogenous source of 137 Cs in cubic concrete container and point source (hot spot) of the same activity. The result is - dose from the point source is 16.6 times higher than the one from the cube. As a result the following new restrictions arise for disposal of the 137 Cs spent industrial sources: disposal of DSSs is forbidden in the upper layer of the containers; maximum activity of the 137 Cs disused industrial source emplaced into the FRC container is 3.41x10 13 / 16.6 = 2.05x10 12 Bq in case of FRC filling by non-radioactive cement mortar; if the cemented radioactive waste is to be used for filling of FRC, decrease of the limit for the disused sealed source is equivalent to the radioactivity of the cement mixture

  16. Development and Preliminary Validation of the Time Management for Exercise Scale

    Science.gov (United States)

    Hellsten, Laurie-ann M.; Rogers, W. Todd

    2009-01-01

    The purpose of this study was to collect preliminary validity evidence for a time management scale for exercise. An initial pool of 91 items was developed from existing literature. Ten exercise/health psychologists evaluated each of the items in terms of relevance and representativeness. Forty-nine items met all criteria. Exploratory factor…

  17. 75 FR 11153 - Main Mill Street Investments, LLC; Notice of Preliminary Permit Application Accepted for Filing...

    Science.gov (United States)

    2010-03-10

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 13631-000] Main Mill Street..., Motions To Intervene, and Competing Applications March 1, 2010. On November 16, Main Mill Street Investments, LLC (Main Mill Street Investments) filed an application for a preliminary permit, pursuant to...

  18. Delivering Acceptance and Commitment Therapy for Weight Self-Stigma through Guided Self-Help: Results from an Open Pilot Trial

    OpenAIRE

    Levin, Michael E.; Potts, Sarah; Haeger, Jack; Lillis, Jason

    2017-01-01

    Weight self-stigma is a promising target for innovative interventions seeking to improve outcomes among overweight/obese individuals. Preliminary research suggests acceptance and commitment therapy (ACT) may be an effective approach for reducing weight self-stigma, but a guided self-help version of this intervention may improve broad dissemination. This pilot open trial sought to evaluate the potential acceptability and efficacy of a guided self-help ACT intervention, included coaching and a ...

  19. Containment design, performance criteria and research needs for advanced reactor designs

    International Nuclear Information System (INIS)

    Bagdi, G.; Ali, S.; Costello, J

    2004-01-01

    This paper points out some important shifts in the basic expectations in the performance requirements for containment structures and discusses the areas where the containment structure design requirements and acceptance criteria can be integrated with ultimate test based insights. Although there has not been any new reactor construction in the United States for over thirty years, several designs of evolutionary and advanced reactors have already been certified. Performance requirements for containment structures under design basis and severe accident conditions and explicit consideration of seismic margins have been used in the design certification process. In the United States, the containment structure design code is the American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section III, Division 1, Subsection NE-Class MC for the steel containment and Section III, Division 2 for reinforced and prestressed concrete reactor vessels and containments. This containment design code was based on the early concept of applying design basis internal pressure and associated load combinations that included the operating basis and safe shutdown earthquake ground motion. These early design criteria served the nuclear industry and the regulatory authorities in maintaining public health and safety. However, these early design criteria do not incorporate the performance criteria related to containment function in an integrated fashion. Research in large scale model testing of containment structures to failure from over pressurization and shake table testing using simulated ground motion, have produced insights related to failure modes and material behavior at failure. The results of this research provide the opportunity to integrate these observations into design and acceptance criteria. This integration process would identify 'gaps' in the present knowledge and future research needs. This knowledge base is important for gleaning risk-informed insights into

  20. Predicting nurses' use of healthcare technology using the technology acceptance model: an integrative review.

    Science.gov (United States)

    Strudwick, Gillian

    2015-05-01

    The benefits of healthcare technologies can only be attained if nurses accept and intend to fully use them. One of the most common models utilized to understand user acceptance of technology is the Technology Acceptance Model. This model and modified versions of it have only recently been applied in the healthcare literature among nurse participants. An integrative literature review was conducted on this topic. Ovid/MEDLINE, PubMed, Google Scholar, and CINAHL were searched yielding a total of 982 references. Upon eliminating duplicates and applying the inclusion and exclusion criteria, the review included a total of four dissertations, three symposium proceedings, and 13 peer-reviewed journal articles. These documents were appraised and reviewed. The results show that a modified Technology Acceptance Model with added variables could provide a better explanation of nurses' acceptance of healthcare technology. These added variables to modified versions of the Technology Acceptance Model are discussed, and the studies' methodologies are critiqued. Limitations of the studies included in the integrative review are also examined.

  1. Ecological criteria for evaluating candidate sites for marine reserves

    Science.gov (United States)

    Roberts, Callum M.; Andelman, Sandy; Branch, George; Bustamante, Rodrigo H.; Castilla, Juan Carlos; Dugan, Jenifer; Halpern, Benjamin S.; Lafferty, Kevin D.; Leslie, Heather; Lubchenco, Jane; McArdle, Deborah; Possingham, Hugh P.; Ruckelshaus, Mary; Warner, Robert R.

    2003-01-01

    Several schemes have been developed to help select the locations of marine reserves. All of them combine social, economic, and biological criteria, and few offer any guidance as to how to prioritize among the criteria identified. This can imply that the relative weights given to different criteria are unimportant. Where two sites are of equal value ecologically, then socioeconomic criteria should dominate the choice of which should be protected. However, in many cases, socioeconomic criteria are given equal or greater weight than ecological considerations in the choice of sites. This can lead to selection of reserves with little biological value that fail to meet many of the desired objectives. To avoid such a possibility, we develop a series of criteria that allow preliminary evaluation of candidate sites according to their relative biological values in advance of the application of socioeconomic criteria. We include criteria that, while not strictly biological, have a strong influence on the species present or ecological processes. Our scheme enables sites to be assessed according to their biodiversity, the processes which underpin that diversity, and the processes that support fisheries and provide a spectrum of other services important to people. Criteria that capture biodiversity values include biogeographic representation, habitat representation and heterogeneity, and presence of species or populations of special interest (e.g., threatened species). Criteria that capture sustainability of biodiversity and fishery values include the size of reserves necessary to protect viable habitats, presence of exploitable species, vulnerable life stages, connectivity among reserves, links among ecosystems, and provision of ecosystem services to people. Criteria measuring human and natural threats enable candidate sites to be eliminated from consideration if risks are too great, but also help prioritize among sites where threats can be mitigated by protection. While our

  2. 105 K East isolation barrier acceptance analysis report

    International Nuclear Information System (INIS)

    McCracken, K.J.; Irwin, J.J.

    1995-01-01

    The objective of this document is to report and interpret the findings of the isolation barrier acceptance tests performed in 105KE/100K. The tests were performed in accordance with the test plan (McCracken 1995c) and acceptance test procedure (McCracken 1995a). The test report (McCracken 1995b) contains the test data. This document compares the test data (McCracken 1995b) against the criteria (McCracken 1995a, c). A discussion of the leak rate analytical characterization (Irwin 1995) describes how the flow characteristics and the flow rate will be determined using the test data from the test report (McCracken 1995b). The barriers must adequately control the leakage from the main basin to the discharge chute to less than the 1,500 gph (5,680 lph) Safety Analysis Report (SAR 1994) limit

  3. Design requirements, criteria and methods for seismic qualification of CANDU power plants

    International Nuclear Information System (INIS)

    Singh, N.; Duff, C.G.

    1979-10-01

    This report describes the requirements and criteria for the seismic design and qualification of systems and equipment in CANDU nuclear power plants. Acceptable methods and techniques for seismic qualification of CANDU nuclear power plants to mitigate the effects or the consequences of earthquakes are also described. (auth)

  4. The Swedish Radiation Protection Institute's protection criteria for disposal of spent nuclear fuel

    International Nuclear Information System (INIS)

    1995-12-01

    In this document the Swedish Radiation Protection Institute reports the preliminary protection criteria for personnel and public concerned with, or in other ways affected by, the disposal of high level radioactive waste. The document will be submitted for consideration by the parties concerned and also serve as a basis for preparing a Swedish viewpoint which can be asserted in future international discussions

  5. A Multi-Criteria Approach to Dry Port Location in Developing Economies with Application to Vietnam

    Directory of Open Access Journals (Sweden)

    Lam Canh Nguyen

    2016-03-01

    Full Text Available This paper presents a conceptual framework for the inclusion of multiple criteria in the evaluation of dry port location in developing countries from a multiple stakeholder perspective. We present the framework in four steps. The first step encompasses preliminary research to filter the alternative locations for dry port development. In the second step, the stakeholders are clustered in three groups: dry port users, dry port service providers and the wider community. Then, we present the sub-criteria related to dry port location including the associated measuring methods. The third step includes an explanation on the methods used for weighing these criteria and sub-criteria. A multi-criteria analysis is carried out in the final step. We apply the methodological framework to Vietnam. The location of a new dry port project in Vinh Phuc province will be evaluated against two existing inland clearance depots (ICD in Lao Cai and Phu Tho province.

  6. Criteria and principles for environmental assessment of disposal of radioactive wastes

    International Nuclear Information System (INIS)

    Hill, M.D.

    1989-01-01

    This paper describes the criteria which are used in judging whether methods for the disposal of radioactive wastes are acceptable, from a radiological protection point of view, and the principles used in assessing the radiological impact of waste disposal methods. Gaseous, liquid and solid wastes are considered, and the discussion is relevant to wastes arising from the nuclear power industry, and from medical practices, general industry and research. Throughout the paper, emphasis is given to the general criteria and principles recommended by international organizations rather than to the detailed legislative and regulatory requirements in particular countries

  7. Protection criteria from the non-ionizing radiations

    International Nuclear Information System (INIS)

    Touzet, Rodolfo E.

    2004-01-01

    The first objective of the protection philosophy is to determinate the relation reason-effect in order to establish the exposition thresholds to acceptable values. To establish the radioprotection criteria is important to considerate the following: a-) The damage and effects of the non-ionizing radiation; b-) The physical aspects of the fields exposition; and c-) The dosimetry of the involucrate tissues. The non-ionizing radiation includes the optics radiations (ultraviolet, visible, infrared and laser), and the electromagnetic radiations (microwave, radars, magnetic and electrostatics fields)

  8. Feasibility and Acceptability of Screening and Brief Interventions to Address Alcohol and Other Drug Use among Patients Presenting for Emergency Services in Cape Town, South Africa

    Directory of Open Access Journals (Sweden)

    Bronwyn Myers

    2012-01-01

    Full Text Available Despite evidence from high income countries, it is not known whether screening and brief interventions (SBI for alcohol and other drug (AOD use are feasible to implement in low and middle income countries. This paper describes the feasibility and acceptability of a peer-led SBI for AOD-using patients presenting with injuries at emergency services in Cape Town, South Africa. Data were extracted from program records on the number of eligible patients screened and the number of program refusals. A questionnaire examined preliminary responses to the intervention for 30 patients who had completed the program and 10 emergency personnel. Peer counselors were also interviewed to identify barriers to implementation. Of the 1458 patients screened, 21% (305 met inclusion criteria, of which 74% (225 were enrolled in the intervention. Of the 30 patients interviewed, most (83% found the program useful. Emergency personnel were supportive of the program but felt that visibility and reach could improve. Peer counselors identified the need for better integration of the program into emergency services and for additional training and support. In conclusion, with limited additional resources, peer-led SBIs for AOD use are feasible to conduct in South African emergency services and are acceptable to patients and emergency personnel.

  9. Ecological radiation protection criteria for nuclear power

    International Nuclear Information System (INIS)

    Kryshev, I.I.

    1993-01-01

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

  10. Determining criteria for the disposal of iodine-129

    International Nuclear Information System (INIS)

    Burger, L.L.

    1980-10-01

    The basic consideration in the disposal of the 129 I produced by the nuclear power industry is that humans must be protected from unacceptable radiation risks. Existing standards prescribe maximum concentrations in air and water and, more recently, a maximum release per unit of electrical power production. The global quantity, distribution, and rate of movement of 127 I (natural iodine), naturally produced 129 I, and anthropogenic 129 I are examined. The 129 I released earlier as a result of nuclear activities over the past few decades is not uniformly dispersed. But the possibility of much greater dispersion exists and, therefore, of much greater dilution than was previously attempted. The potential for dilution with respect to either the 129 I concentration or the 129 I/ 127 I ratio far exceeds the minimum required for acceptable exposure to mankind. For utilizing the dilution principle, it is preferable to package and dispose of 129 I separately from other fission products. The deep ocean is seen to be the logical location for ultimate disposal. A set of 14 basic items is described that can be used to set criteria for storage and disposal of 129 I. It is suggested that preliminary standards be developed on these and perhaps other items to apply to (1) temporary storage and transportation, (2) disposal to a dry environment with a time limitation on calculated behavior, and (3) disposal to the deep ocean with complete release permitted in 10 3 yr. Early quantification of some of these items will permit better decisions on further research and development needed for iodine removal or control, fixation, and disposal

  11. Preliminary classification criteria for the antiphospholipid syndrome within systemic lupus erythematosus.

    Science.gov (United States)

    Alarcón-Segovia, D; Pérez-Vázquez, M E; Villa, A R; Drenkard, C; Cabiedes, J

    1992-04-01

    Ten percent of 667 consecutive systemic lupus erythematosus (SLE) patients were considered to have definite antiphospholipid syndrome (aPLS) because they had two or more antiphospholipid (aPL)-related clinical manifestations and aPL titers more than 5 SD above the mean of normal controls. Another 14% had either one aPL-related manifestation but high titers of the antibody or two manifestations and low aPL titers (probable aPLS). One fourth of the patients had no manifestations but high titers, one manifestation and low titers, or two or more manifestations and negative aPL titers ("doubtful" aPLS); the other half were considered negative for aPLS. In patients with high-titer aPL, the number of aPL-related manifestations was influenced by disease duration and number of pregnancies, indicating potential mobility of category with time or with risk of recurrent pregnancy loss. Patients with two or more manifestations but variable aPL levels differed in immunosuppressive treatment and in the number of times they had been tested, indicating potential mobility of category with lower treatment and/or further aPL testing. Patients with definite aPLS had increased risk of cutaneous vasculitis, peripheral neuropathy, seizures, psychosis, transient ischemic attacks, and leukopenia. In 11 of 52 SLE patients with definite aPLS the initial manifestation was related to aPL, and in 16 it concurred with an unrelated one. Only two patients fulfilled criteria for aPLS before having other evidence of SLE. The authors conclude that aPLS occurring within SLE is part of the disease rather than an associated condition and propose the use of definite and probable classification categories. These criteria, with appropriate follow-up and clinical and serological exclusion clauses for potential primary conditions, could also be applied to primary aPLS.

  12. Protocol for the verification of minimum criteria

    International Nuclear Information System (INIS)

    Gaggiano, M.; Spiccia, P.; Gaetano Arnetta, P.

    2014-01-01

    This Protocol has been prepared with reference to the provisions of article 8 of the Legislative Decree of May 26, 2000 No. 187. Quality controls of radiological equipment fit within the larger 'quality assurance Program' and are intended to ensure the correct operation of the same and the maintenance of that State. The pursuit of this objective guarantees that the radiological equipment subjected to those controls also meets the minimum criteria of acceptability set out in annex V of the aforementioned legislative decree establishing the conditions necessary to allow the functions to which each radiological equipment was designed, built and for which it is used. The Protocol is established for the purpose of quality control of radiological equipment of Cone Beam Computer Tomography type and reference document, in the sense that compliance with stated tolerances also ensures the subsistence minimum acceptability requirements, where applicable.

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

    Science.gov (United States)

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

    2013-11-01

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

  14. Engineering study of generic site criteria for selected DOE plutonium facilities

    International Nuclear Information System (INIS)

    Kingsbury, R.J.; Greenwood, J.M.; Sandoval, M.D.

    1980-09-01

    The objectives of this study were to identify criteria that would be applied to selection of a site for plutonium facilities such as those at the Rocky Flats Plant, to establish the relative importance of these criteria, and to identify suitable areas within the United States for location of plutonium facilities with respect to these criteria. Sources of the site criteria identified include federal laws, federal agency regulations, state laws and regulations, and requirements associated with operations to be performed at the site. The criteria identified during the study were organized into 14 major categories. The relative importnace of each category and each criterion within the categories were established using group decision-making techniques. The major criteria categories, their assigned weight on a scale of 1 to 10, and their relative priority ranks are as follows: geology/seismicity; public safety; environmental impact; meteorology; hydrology; topography; transportation; utilities; personnel; safeguards/security; land area and availability; land use compatibility; and, public acceptance. A suitability analysis of the continental United States was performed using only those criteria that could be mapped at a national scale. Suitability was assessed with respect to each of these criteria, and individual suitability maps were prepared. A composite suitability map was generated using computerized overlay techniques. This map provides a starting point for identifying specific candidate sites if an actual site selection were to be conducted

  15. Generalized Safety and Efficacy of Simplified Intravenous Thrombolysis Treatment (SMART) Criteria in Acute Ischemic Stroke

    DEFF Research Database (Denmark)

    Sørensen, Sigrid B; Barazangi, Nobl; Chen, Charlene

    2016-01-01

    BACKGROUND: Common intravenous recombinant tissue plasminogen activator (IV rt-PA) exclusion criteria may substantially limit the use of thrombolysis. Preliminary data have shown that the SMART (Simplified Management of Acute stroke using Revised Treatment) criteria greatly expand patient...... eligibility by reducing thrombolysis exclusions, but they have not been assessed on a large scale. We evaluated the safety and efficacy of general adoption of SMART thrombolysis criteria to a large regional stroke network. METHODS: Retrospective analysis of consecutive patients who received IV thrombolysis...... within a regional stroke network was performed. Patients were divided into those receiving thrombolysis locally versus at an outside hospital. The primary outcome was modified Rankin Scale score (≤1) at discharge and the main safety outcome was symptomatic intracranial hemorrhage (sICH) rate. RESULTS...

  16. Suggested non-proliferation criteria for commercial nuclear fuel cycles

    International Nuclear Information System (INIS)

    Laney, R.V.; Heubotter, P.R.

    1978-01-01

    Based on the Administration's policy to prevent nuclear weapons proliferation through diversion of fuel from commercial reactor fuel cycles, a ''benchmark'' set of nonproliferation criteria was prepared for the commercial nuclear fuel cycle. These criteria should eliminate incremental risks of proliferation beyond those inherent in the present generation of low-enriched-uranium-fueled reactors operating in a once-through mode, with internationally safeguarded storage of spent fuel. They focus on the balanced application of technical constraints consistent with the state of the technology, with minimal requirements for institutional constraints, to provide a basis for assessing the proliferation resistance of proposed fission power systems. The paper contains: (1) our perception of the nuclear energy policy and of the baseline proliferation risk accepted under this policy; (2) objectives for a reactor and fuel cycle strategy which address the technical, political, and institutional aspects of diversion and proliferation and, at the same time, satisfy the Nation's needs for efficient, timely, and economical utilization of nuclear fuel resources; (3) criteria which are responsive to these objectives and can therefore be used to screen proposed reactor and fuel cycle strategies; and (4) a rationale for these criteria

  17. Multi-criteria multi-stakeholder decision analysis using a fuzzy-stochastic approach for hydrosystem management

    Science.gov (United States)

    Subagadis, Y. H.; Schütze, N.; Grundmann, J.

    2014-09-01

    The conventional methods used to solve multi-criteria multi-stakeholder problems are less strongly formulated, as they normally incorporate only homogeneous information at a time and suggest aggregating objectives of different decision-makers avoiding water-society interactions. In this contribution, Multi-Criteria Group Decision Analysis (MCGDA) using a fuzzy-stochastic approach has been proposed to rank a set of alternatives in water management decisions incorporating heterogeneous information under uncertainty. The decision making framework takes hydrologically, environmentally, and socio-economically motivated conflicting objectives into consideration. The criteria related to the performance of the physical system are optimized using multi-criteria simulation-based optimization, and fuzzy linguistic quantifiers have been used to evaluate subjective criteria and to assess stakeholders' degree of optimism. The proposed methodology is applied to find effective and robust intervention strategies for the management of a coastal hydrosystem affected by saltwater intrusion due to excessive groundwater extraction for irrigated agriculture and municipal use. Preliminary results show that the MCGDA based on a fuzzy-stochastic approach gives useful support for robust decision-making and is sensitive to the decision makers' degree of optimism.

  18. Preliminary proposed seismic design and evaluation criteria for new and existing underground hazardous materials storage tanks

    International Nuclear Information System (INIS)

    Kennedy, R.P.

    1991-01-01

    The document provides a recommended set of deterministic seismic design and evaluation criteria for either new or existing underground hazardous materials storage tanks placed in either the high hazard or moderate hazard usage catagories of UCRL-15910. The criteria given herein are consistent with and follow the same philosophy as those given in UCRL-15910 for the US Department of Energy facilities. This document is intended to supplement and amplify upon Reference 1 for underground hazardous materials storage tanks

  19. 105K West Isolation Barrier Acceptance Test results

    International Nuclear Information System (INIS)

    McCracken, K.J.; Irwin, J.J.

    1995-01-01

    The objective of this document is to report and interpret the findings of the isolation barrier acceptance tests performed in 105KW/100K. The tests were performed in accordance with the test plan and acceptance test procedure. The test report contains the test data. This document compares the test data against the criteria. A discussion of the leak rate analytical characterization describes how the flow characteristics flow rate will be determined using the test data from the test report. Two modes of water loss were considered; basin and/or discharge chute leakage, and evaporation. An initial test established baseline leakage data and instrumentation performance. Test 2 evaluated the sealing performance of the isolation barrier by inducing an 11 in. (27.9 cm) level differential across the barrier. The leak rate at this 11 in. (27.9 cm) level is extrapolated to the 16 ft. (4.9 m) level differential postulated in the DBE post seismic event. If the leak rate, adjusted for evaporation and basin leakage (determined from Test 1), is less than the SAR limit of 1,500 gph (5,680 lph) at a 16 ft (4.9 m) level differential, the barriers pass the acceptance test

  20. Quality of laboratory studies assessing effects of Bt-proteins on non-target organisms: minimal criteria for acceptability.

    Science.gov (United States)

    De Schrijver, Adinda; Devos, Yann; De Clercq, Patrick; Gathmann, Achim; Romeis, Jörg

    2016-08-01

    The potential risks that genetically modified plants may pose to non-target organisms and the ecosystem services they contribute to are assessed as part of pre-market risk assessments. This paper reviews the early tier studies testing the hypothesis whether exposure to plant-produced Cry34/35Ab1 proteins as a result of cultivation of maize 59122 is harmful to valued non-target organisms, in particular Arthropoda and Annelida. The available studies were assessed for their scientific quality by considering a set of criteria determining their relevance and reliability. As a case-study, this exercise revealed that when not all quality criteria are met, weighing the robustness of the study and its relevance for risk assessment is not obvious. Applying a worst-case expected environmental concentration of bioactive toxins equivalent to that present in the transgenic crop, confirming exposure of the test species to the test substance, and the use of a negative control were identified as minimum criteria to be met to guarantee sufficiently reliable data. This exercise stresses the importance of conducting studies meeting certain quality standards as this minimises the probability of erroneous or inconclusive results and increases confidence in the results and adds certainty to the conclusions drawn.

  1. IMPORTANCE OF MULTIPLE CRITERIA FOR PRIORITY SETTING OF HIV/AIDS INTERVENTIONS.

    Science.gov (United States)

    Tromp, Noor; Prawiranegara, Rozar; Siregar, Adiatma; Sunjaya, Deni; Baltussen, Rob

    2015-01-01

    This study describes the views of various stakeholders on the importance of different criteria for priority setting of HIV/AIDS interventions in Indonesia. Based on a general list of criteria and a focus group discussion with stakeholders (n = 6), a list was developed of thirty-two criteria that play a role in priority setting in HIV/AIDS control in West-Java province. Criteria were categorized according to the World Health Organization's health system goals and building block frameworks. People living with HIV/AIDS (n = 49), healthcare workers (HCW) (n = 41), the general population (n = 43), and policy makers (n = 22) rated the importance of thirty-two criteria on a 5-point Likert-scale. Thereafter, respondents ranked the highest rated criteria to express more detailed preferences. Stakeholders valued the following criteria as most important for the priority setting of HIV/AIDS interventions: an intervention's impact on the HIV/AIDS epidemic, reduction of stigma, quality of care, effectiveness on individual level, and feasibility in terms of current capacity of the health system (i.e., HCW, product, information, and service requirements), financial sustainability, and acceptance by donors. Overall, stakeholders' preferences for the importance of criteria are similar. Our study design outlines an approach for other settings to identify which criteria are important for priority setting of health interventions. For Indonesia, these study results may be used in priority setting processes for HIV/AIDS control and may contribute to more transparent and systematic allocation of resources.

  2. 40 CFR 80.584 - What are the precision and accuracy criteria for approval of test methods for determining the...

    Science.gov (United States)

    2010-07-01

    ... criteria for approval of test methods for determining the sulfur content of motor vehicle diesel fuel, NRLM....584 What are the precision and accuracy criteria for approval of test methods for determining the... available gravimetric sulfur standard in the range of 1-10 ppm sulfur shall not differ from the accepted...

  3. Initial Assessment of the Acceptability of a Push-Pull Aedes aegypti Control Strategy in Iquitos, Peru and Kanchanaburi, Thailand

    Science.gov (United States)

    Paz-Soldan, Valerie A.; Plasai, Valaikanya; Morrison, Amy C.; Rios-Lopez, Esther J.; Guedez-Gonzales, Shirly; Grieco, John P.; Mundal, Kirk; Chareonviriyaphap, Theeraphap; Achee, Nicole L.

    2011-01-01

    As part of a larger research program evaluating chemical threshold levels for a Push-Pull intervention to reduce man-vector (Aedes aegypti) contact, this qualitative study explored local perceptions and strategies associated with mosquito control within dengue-endemic communities in Peru and Thailand. Focus groups were used to provide preliminary information that would identify possible public acceptance issues to the Push-Pull strategy in each site. Nine focus group discussions (total of 102 individuals) conducted between September 2008 and March 2009 examined several themes: 1) current mosquito control practices; 2) perceptions of spatial repellency and contact irritancy versus killing mosquitoes; and 3) initial perceptions toward mosquito host-seeking traps. Results indicate participants use household-level strategies for insect control that reveal familiarity with the concept of spatial repellent and contact irritant actions of chemicals and that placing traps in the peridomestic environment to remove repelled mosquitoes was acceptable. Preliminary evidence suggests a Push-Pull strategy should be well accepted in these locations. These results will be beneficial for developing future large scale push-pull interventions and are currently being used to guide insecticide application strategies in (entomological) proof-of-concept studies using experimental huts. PMID:21292886

  4. Preliminary Analysis of a Loss of Condenser Vacuum Accident Using the MARS-KS Code

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jieun Kim; Bang, Young Seok; Oh, Deog Yeon; Kim, Kap; Woo, Sweng-Wong [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2015-05-15

    In accordance with revision of NUREG-0800 of USNRC, the area of review for loss of condenser vacuum(LOCV) accident has been expanded to analyze both peak pressures of primary and secondary system separately. Currently, the analysis of LOCV accident, which is caused by malfunction of condenser, has been focused to fuel cladding integrity and peak pressure in the primary system. In this paper, accident analysis for LOCV using MARS-KS code were conducted to support the licensing review on transient behavior of secondary system pressure of APR1400 plant. The accident analysis for the loss of condenser vacuum (LOCV) of APR1400 was conducted with the MARS-KS code to support the review on the pressure behavior of primary and secondary system. Total four cases which have different combination of availability of offsite power and the pressurizer spray are considered. The preliminary analysis results shows that the initial conditions or assumptions which concludes the severe consequence are different for each viewpoint, and in some cases, it could be confront with each viewpoint. Therefore, with regard to the each acceptance criteria, figuring out and sensitivity analysis of the initial conditions and assumptions for system pressure would be necessary.

  5. The acceptability, feasibility, and possible benefits of a neurobiologically-informed 5-day multifamily treatment for adults with anorexia nervosa.

    Science.gov (United States)

    Wierenga, Christina E; Hill, Laura; Knatz Peck, Stephanie; McCray, Jason; Greathouse, Laura; Peterson, Danika; Scott, Amber; Eisler, Ivan; Kaye, Walter H

    2018-05-02

    Novel treatments for adults with anorexia nervosa (AN) are lacking. Recent scientific advances have identified neurobiologically-driven temperament contributors to AN symptoms that may guide development of more effective treatments. This preliminary study evaluates the acceptability, feasibility and possible benefits of a multicenter open trial of an intensive 5-day neurobiologically-informed multifamily treatment for adults with AN and their supports (SU). The temperament-focused treatment combines psychoeducation of AN neurobiology and SU involvement to develop skills to manage traits contributing to disease chronicity. Fifty-four adults with AN and at least one SU (n = 73) received the 5-day treatment. Acceptability, feasibility, and attrition were measured post-treatment. Clinical outcome (BMI, eating disorder psychopathology, family function) was assessed post-treatment and at >3-month follow-up. The treatment had low attrition, with only one drop-out. Patients and SU rated the intervention as highly acceptable, and clinicians reported good feasibility. At post-treatment, patients demonstrated significantly increased BMI, reduced eating disorder psychopathology, and improved family function. Benefits were maintained in the 39 patients who completed follow-up assessment, with 62% reporting full or partial remission. Preliminary results are promising and suggest this novel treatment is feasible and acceptable. To establish treatment efficacy, fully-powered randomized controlled trials are necessary. © 2018 Wiley Periodicals, Inc.

  6. Working draft regulatory guide on release criteria for decommissioning: NRC staff's draft for comment

    International Nuclear Information System (INIS)

    Daily, M.C.; Huffert, A.; Cardile, F.; Malaro, J.C.

    1994-08-01

    The Nuclear Regulatory Commission's (NRC) regulations in 10 CFR 20 are being amended to include radiological criteria for decommissioning of lands and structures at nuclear facilities. 10 CFR Part 20, Subpart E establishes criteria for the remediation of contaminated sites or facilities that will allow their release for future use with or without restrictions. The criteria include a Total Effective Dose Equivalent (TEDE) limit of 15 mrem/year (0.15 mSv/y) that should not be exceeded by an average individual among those who could potentially receive the greatest exposure from any residual activity within a facility or on a site. The criteria also require a licensee to reduce any residual radioactivity to as-low-as-reasonably-achievable (ALARA) levels. This staff draft guide describes acceptable procedures for determining the predicted dose level (PDL) from any residual radioactivity at the site. It describes the basic features of the calculational models and the associated default assumptions and parameter values the NRC staff would find acceptable in calculating PDLs. Appendices A, B, and C provide numerical values that can be used to estimate the dose from residual radioactivity remaining at a site. Since 10 CFR Part 20, Subpart E introduces several new concepts, definitions and discussions are included in a regulatory position concepts section of the guide to assist licensees in understanding some of the philosophy underlying the rule

  7. Preliminary Performance Assessment for Disposal of APT and CLWR/TEF Wastes at SRS

    International Nuclear Information System (INIS)

    Wilhite, E.L.

    1998-01-01

    This section provides the descriptive information for understanding the analyses presented in this preliminary performance assessment. This section addresses the approach taken in the PA, provides a general description of the Savannah River Site E-Area low-level waste facility, and discusses the performance criteria used for evaluating performance

  8. 76 FR 52656 - Rhode Island Department of Environmental Management; Notice of Preliminary Permit Application...

    Science.gov (United States)

    2011-08-23

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 14211-000] Rhode Island Department of Environmental Management; Notice of Preliminary Permit Application Accepted for Filing and Soliciting Comments, Motions To Intervene, and Competing Applications On June 10, 2011, the Rhode Island Department of Environmental Management...

  9. The Swedish Radiation Protection Institute`s protection criteria for disposal of spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-01

    In this document the Swedish Radiation Protection Institute reports the preliminary protection criteria for personnel and public concerned with, or in other ways affected by, the disposal of high level radioactive waste. The document will be submitted for consideration by the parties concerned and also serve as a basis for preparing a Swedish viewpoint which can be asserted in future international discussions.

  10. Preliminary evaluation of 30 potential granitic rock sites for a radioactive waste storage facility in southern Nevada

    International Nuclear Information System (INIS)

    Boardman, C.R.; Knutson, C.F.

    1978-01-01

    Results of preliminary study are presented which was performed under subtask 2.7 of the NTS Terminal Waste Storage Program Plan for 1978. Subtask 2.7 examines the feasibility of locating a nuclear waste repository in a granitic stock or pluton in southern Nevada near the Nevada Test Site (NTS). It is assumed for the purposes of this study that such a repository cannot be located at NTS. This assumption may or may not be correct. This preliminary report does not identify a particular site as being a suitable location for a repository. Nor does it absolutely eliminate a particular site from further consideration. It does, however, answer the basic question of probable suitability of some of the sites and present a systematic method for site evaluation. Since the findings of this initial study have been favorable, it will be followed by more exhaustive and detailed studies of the original 30 sites and perhaps others. In future studies some of the evaluation criteria used in the preliminary study may be modified or eliminated, and new criteria may be introduced

  11. Preliminary evaluation of 30 potential granitic rock sites for a radioactive waste storage facility in southern Nevada

    Energy Technology Data Exchange (ETDEWEB)

    Boardman, C.R.; Knutson, C.F.

    1978-02-15

    Results of preliminary study are presented which was performed under subtask 2.7 of the NTS Terminal Waste Storage Program Plan for 1978. Subtask 2.7 examines the feasibility of locating a nuclear waste repository in a granitic stock or pluton in southern Nevada near the Nevada Test Site (NTS). It is assumed for the purposes of this study that such a repository cannot be located at NTS. This assumption may or may not be correct. This preliminary report does not identify a particular site as being a suitable location for a repository. Nor does it absolutely eliminate a particular site from further consideration. It does, however, answer the basic question of probable suitability of some of the sites and present a systematic method for site evaluation. Since the findings of this initial study have been favorable, it will be followed by more exhaustive and detailed studies of the original 30 sites and perhaps others. In future studies some of the evaluation criteria used in the preliminary study may be modified or eliminated, and new criteria may be introduced.

  12. Criteria for permission of radiosterilized products to application in medicine; Zasady dopuszczania wyrobow sterylizowanych radiacyjnie do stosowania w medycynie

    Energy Technology Data Exchange (ETDEWEB)

    Achmatowicz, T [Instytut Lekow, Warsaw (Poland)

    1997-10-01

    The criteria being used in Poland for permission of radiosterilized medical materials to commercial application result from regulations being in force. The international regulations are also taken into account. The all criteria and procedure needed for any product become accepted for radiosterilization and commercial medical use have been presented and discussed. 1 tab.

  13. Preliminary Design Analysis of a HGD for the NHDD Program at Korea

    International Nuclear Information System (INIS)

    Song, Kee Nam; Lee, H. Y.; Lee, S. B.; Kim, Y. W.

    2007-01-01

    Korea Atomic Energy Research Institute is in the process of carrying out a Nuclear Hydrogen Development and Demonstration (NHDD) Program by considering the indirect cycle gas cooled reactors that produce heat at temperatures in the order of 950 .deg. C. A coaxial double-tube Hot Gas Duct (HGD) is a key component connecting the reactor pressure vessel and the intermediate heat exchanger for the NHDD program. Recently, a preliminary design evaluation for the hot gas duct of the NHDD program was carried out. These preliminary design activities include a decision on the geometric dimensions, a strength evaluation, an appropriate material selection, and identifying the design code for the HGD. In this study, a preliminary strength evaluation for the HGD of the NHDD program has been undertaken based on the HTR-10 design concepts. Also, a preliminary evaluation of the creep-fatigue damage for a high temperature HGD structure has been carried out according to the draft code case for Alloy 617. Preliminary strength evaluation results for the HGD showed that the geometric dimensions of the proposed HGD would be acceptable for the design requirements

  14. Key acceptability attributes of orodispersible films.

    Science.gov (United States)

    Scarpa, Mariagiovanna; Paudel, Amrit; Kloprogge, Frank; Hsiao, Wen Kai; Bresciani, Massimo; Gaisford, Simon; Orlu, Mine

    2018-04-01

    The features rendering orodispersible films (ODFs) patient-centric formulations are widely discussed in the scientific literature. However there is a lack of research studies exploring ODF characteristics with a potential impact on end-user acceptability. The aim of this study was to identify the key ODF characteristics affecting end-user acceptability by developing in vitro test methods for the prediction of ODFs acceptability and correlate these formulation characteristics with the data obtained from a human panel study. Four drug-free single-polymer films were prepared by solvent casting. Solutions of poly(vinyl) alcohol (PVOH) 39 KDa (P1), PVOH 197 KDa (P2), carboxymethylcellulose (CMC) 395 KDa (C1), and CMC 725 KDa (C2) were prepared. Texture analysis and Dynamic Mechanical Analysis (DMA) were used to assess film tack. Petri dish and drop methods were used to assess disintegration time. A human panel of 24 healthy young adults was employed to identify end-user acceptability criteria of the four study film samples. Texture analysis data of ODF tack were not found to be in agreement with the in vivo perceived stickiness in the mouth. However, measurement of the area under the adhesive force curve obtained by DMA correlated with in vivo perceived stickiness data for all samples. The disintegration times obtained by drop method were more comparable to human panel data than the petri dish method. Hence DMA and drop methods proved to be promising methodologies for the prediction of the end-user acceptability. The type and molecular weight of the film-forming polymer had a strong influence on stickiness perception, whereas only polymeric molecular weight influenced perceived disintegration time. The human panel study showed that Participant Reported Outcomes (PROs) for the perceived stickiness in the mouth and disintegration time of test films received significantly different scores between samples, and thus were identified as the key attributes with the

  15. Application fuzzy multi-attribute decision analysis method to prioritize project success criteria

    Science.gov (United States)

    Phong, Nguyen Thanh; Quyen, Nguyen Le Hoang Thuy To

    2017-11-01

    Project success is a foundation for project owner to manage and control not only for the current project but also for future potential projects in construction companies. However, identifying the key success criteria for evaluating a particular project in real practice is a challenging task. Normally, it depends on a lot of factors, such as the expectation of the project owner and stakeholders, triple constraints of the project (cost, time, quality), and company's mission, vision, and objectives. Traditional decision-making methods for measuring the project success are usually based on subjective opinions of panel experts, resulting in irrational and inappropriate decisions. Therefore, this paper introduces a multi-attribute decision analysis method (MADAM) for weighting project success criteria by using fuzzy Analytical Hierarchy Process approach. It is found that this method is useful when dealing with imprecise and uncertain human judgments in evaluating project success criteria. Moreover, this research also suggests that although cost, time, and quality are three project success criteria projects, the satisfaction of project owner and acceptance of project stakeholders with the completed project criteria is the most important criteria for project success evaluation in Vietnam.

  16. Microbiological criteria for good manufacturing practice (GMP)

    Energy Technology Data Exchange (ETDEWEB)

    Farkas, J [Inst. of Preservation and Livestock Products Technology, Univ. of Horticulture and Food Industry, Budapest (Hungary); Zukal, E [Inst. of Preservation and Livestock Products Technology, Univ. of Horticulture and Food Industry, Budapest (Hungary)

    1992-01-01

    Good manufacturing practice (GMP) consist of an effective manufacturing operation and an effective application of food control. GMP is best supported by the Hazard Analysis Critical Control Point system (HACCP) of the preventive quality assurance, which requires that food irradiation as any food processing technology should be used only with foods of an acceptable quality and adequate handling and storage procedures should precede and follow the processing. The paper concentrates on the first element of the HACCP system for an irradiation plant: the incoming product control, i.e. whether GMP of foods to be irradiated can be assessed by establishing microbiological criteria for their previous good manufacturing practice. In this regard, it summarizes considerations and findings of a ''Consultation on Microbiological Criteria for Foods to be Further Processed Including by Irradiation'' held in 1989 by the International Consultative Group on Food irradiation at the Headquarters of the World Health Organization, Geneva. Difficulties in establishing reference values and defining good manufacturing practices will be pointed out. (orig.)

  17. The Success Criteria of Scientific Pedagogic Activities

    Directory of Open Access Journals (Sweden)

    M. V. Ovchinnikov

    2013-01-01

    Full Text Available The paper considers the problem of scientific pedagogic activity assessment of the higher school academic staff. The existing options of quality estimation are listed along with their deficiencies; the most acceptable in the authors’ opinion being the systematic approach. The latter allows considering almost every aspect of scientific-pedagogic activity. On that ground, the authors recommend the following success estimation criteria: gnostic, projecting, communicative, informational, and organizational. The criteria of work satisfaction and its results are taken into consideration as additional ones. The indicators of each criterion are given demonstrating that the as- sessment can be both internal (subjective and external (objective, denoted in the normative acts. The problem of complex and just quality assessment of scientific- pedagogic activity is quite relevant as it affects the academic staff motivation. The authors believe that the research findings can improve the objectivity of teachers’ work assessment and give way to differentiated approaches to their motivation and stimulation. 

  18. Microbiological criteria for good manufacturing practice (GMP)

    International Nuclear Information System (INIS)

    Farkas, J.; Zukal, E.

    1992-01-01

    Good manufacturing practice (GMP) consist of an effective manufacturing operation and an effective application of food control. GMP is best supported by the Hazard Analysis Critical Control Point system (HACCP) of the preventive quality assurance, which requires that food irradiation as any food processing technology should be used only with foods of an acceptable quality and adequate handling and storage procedures should precede and follow the processing. The paper concentrates on the first element of the HACCP system for an irradiation plant: the incoming product control, i.e. whether GMP of foods to be irradiated can be assessed by establishing microbiological criteria for their previous good manufacturing practice. In this regard, it summarizes considerations and findings of a ''Consultation on Microbiological Criteria for Foods to be Further Processed Including by Irradiation'' held in 1989 by the International Consultative Group on Food irradiation at the Headquarters of the World Health Organization, Geneva. Difficulties in establishing reference values and defining good manufacturing practices will be pointed out. (orig.) [de

  19. Site suitability criteria for solidified high level waste repositories

    International Nuclear Information System (INIS)

    Heckman, R.A.; Holdsworth, T.; Isherwood, D.; Towse, D.F.; Dayem, N.L.

    1979-01-01

    The NRC is developing a framework of regulations, criteria, and standards. Lawrence Livermore Laboratory provides broad technical support to the NRC for developing this regulatory framework, part of which involves site suitability criteria for solidified high-level wastes (SHLW). Both the regulatory framework and the technical base on which it rests have evolved in time. This document is the second report of the technical support project. It was issued as a draft working paper for a programmatic review held at LLL from August 16 to 18, 1977. It was printed and distributed solely as a briefing document on preliminary methodology and initial findings for the purpose of critical review by those in attendance. These briefing documents are being reprinted now in their original formats as UCID-series reports for the sake of the historical record. Analysis results have evolved as both the models and data base have changed. As a result, the methodology, models, and data base in this document are severely outmoded

  20. Definition of criteria related to occupational exposure for use in multi-criteria decision making process for nuclear accidents in Brazil

    International Nuclear Information System (INIS)

    Silva, Diogo N.G.; Guimaraes, Jean R.D.; Rochedo, Elaine R.R.

    2013-01-01

    After the occurrence of nuclear or radiological accidents, the selection of strategies for remediation of contaminated areas and of protective measures for members of public should be based on previously established criteria. Hence, it becomes possible to reduce the stress of population and to prevent the exposure of workers, especially if an implemented measure is not effective in reducing doses for each particular situation. When an accident with radioactive material causes environmental contamination, decisions about remediation of affected areas are complex because there are many factors associated with decontamination processes. Such complexity is related to technical procedures, public acceptance, the feasibility of implementing the measure, costs and legal aspects. This work is part of a project which aims to develop a multi-criteria tool to provide support for decision making processes in cases of nuclear or radiological accidents in Brazil. Primarily, a database containing information about protective and remediation measures for contaminated areas which can be applied nationally was created. Some criteria have already been defined for the classification of these measures regarding aspects of relevance of pathways to public exposure and of the infrastructure necessary to implement the measure. In this paper, the issues related to the exposure of the workforce are assessed and compared to the dose averted to members of the public resulting from the implementation of each remediation procedure. The procedures described in the database are then ranked according to selected criteria. In the next step, these ratings will be incorporated by the multi-criteria tool. (author)

  1. Definition of criteria related to occupational exposure for use in multi-criteria decision making process for nuclear accidents in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Diogo N.G.; Guimaraes, Jean R.D., E-mail: dneves@biof.ufrj.br, E-mail: jeanrdg@biof.ufrj.br [Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil). Instituto de Biofisica Carlos Chagas Filho; Rochedo, Elaine R.R., E-mail: elainerochedo@gmail.com [Instituto Militar de Engenharia (IME), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear

    2013-07-01

    After the occurrence of nuclear or radiological accidents, the selection of strategies for remediation of contaminated areas and of protective measures for members of public should be based on previously established criteria. Hence, it becomes possible to reduce the stress of population and to prevent the exposure of workers, especially if an implemented measure is not effective in reducing doses for each particular situation. When an accident with radioactive material causes environmental contamination, decisions about remediation of affected areas are complex because there are many factors associated with decontamination processes. Such complexity is related to technical procedures, public acceptance, the feasibility of implementing the measure, costs and legal aspects. This work is part of a project which aims to develop a multi-criteria tool to provide support for decision making processes in cases of nuclear or radiological accidents in Brazil. Primarily, a database containing information about protective and remediation measures for contaminated areas which can be applied nationally was created. Some criteria have already been defined for the classification of these measures regarding aspects of relevance of pathways to public exposure and of the infrastructure necessary to implement the measure. In this paper, the issues related to the exposure of the workforce are assessed and compared to the dose averted to members of the public resulting from the implementation of each remediation procedure. The procedures described in the database are then ranked according to selected criteria. In the next step, these ratings will be incorporated by the multi-criteria tool. (author)

  2. Human Factors Affecting the Patient's Acceptance of Wireless Biomedical Sensors

    Science.gov (United States)

    Fensli, Rune; Boisen, Egil

    In monitoring arrhythmia, the quality of medical data from the ECG sensors may be enhanced by being based on everyday life situations. Hence, the development of wireless biomedical sensors is of growing interest, both to diagnose the heart patient, as well as to adjust the regimen. However, human factors such as emotional barriers and stigmatization, may affect the patient's behavior while wearing the equipment, which in turn may influence quality of data. The study of human factors and patient acceptance is important both in relation to the development of such equipment, as well as in evaluating the quality of data gathered from the individual patient. In this paper, we highlight some important aspects in patient acceptance by comparing results from a preliminary clinical trial with patients using a wireless ECG sensor for three days out-of-hospital service, to available published results from telehomecare projects, and discuss important aspects to be taken into account in future investigations.

  3. Geomembrane selection criteria for uranium tailings ponds

    International Nuclear Information System (INIS)

    Mitchell, D.H.; Cuello, R.

    1986-09-01

    The selection criteria, particularly those involving chemical compatibility, of geomembranes to be used in ponds at uranium mill operations are discussed. The principal functional criteria which a geomembrane must meet for this application are: (1) a specified service life and (2) low permeability. Chemical compatibility with the waste is essential in meeting these functional criteria. In two different types of aging tests using simulated acidic uranium mill waste, degradation of chemical and physical properties were examined in geomembranes of high-density polyethylene, polyvinyl chloride, and chlorosulfonated polyethylene. Compatibility tests according to the National Sanitation Foundation procedures are recommended to ascertain the stability of certain physical properties of the proposed geomembrane. Actual experience with a specific geomembrane in an identical application is probably the best method to assure compatibility; however, this experience is frequently not available. Experience with a geomembrane in similar applications is valuable in the selection process, however, small differences in either the geomembrane formulation or the waste composition may result in large differences in performance of the geomembrane. It is likely that many geomembranes have acceptable chemical stability for typical uranium mill applications, therefore, additional factors in the selection processes will include seaming characteristics, mechanical properties, site characteristics, and costs

  4. Negative beliefs about accepting coworker help: Implications for employee attitudes, job performance, and reputation.

    Science.gov (United States)

    Thompson, Phillip S; Bolino, Mark C

    2018-04-16

    For more than 30 years, researchers have investigated interpersonal helping in organizations, with much of this work focusing on understanding why employees help their colleagues. Although this is important, it is also critical that employees are willing to accept assistance that is offered by peers. Indeed, helping behavior should only enhance individual and organizational effectiveness if employees are actually willing to accept offers of assistance. Unfortunately, employees may sometimes have reservations about accepting help from their peers. In four studies, we examine the negative beliefs that employees have about accepting help from coworkers. In Study 1, we use inductive research to qualitatively understand why employees accept or decline coworker help. In Study 2, we develop a preliminary, second-order reflective measure of negative beliefs about accepting coworker help that is indicated by the five specific (first-order) reservations about accepting help identified in Study 1-diminished image, reciprocity obligation, self-reliance, coworker mistrust, and coworker incompetence. In Study 3, we refine our scale and demonstrate its convergent, discriminant, and criterion-related validity. Finally, in Study 4, we investigate the consequences of negative beliefs about accepting coworker help. We find that those who hold more negative beliefs are less likely to receive help from peers (and supervisors), report more negative job attitudes, and have lower levels of in-role performance, citizenship behavior, and creativity. Furthermore, employees with more negative beliefs about accepting help from coworkers are seen less favorably by their supervisors. Implications and future research directions are discussed. (PsycINFO Database Record (c) 2018 APA, all rights reserved).

  5. ICT and OTs: a model of information and communication technology acceptance and utilisation by occupational therapists.

    Science.gov (United States)

    Schaper, Louise K; Pervan, Graham P

    2007-06-01

    There is evidence to suggest that health professionals are reluctant to accept and utilise information and communication technologies (ICT) and concern is growing within health informatics research that this is contributing to the lag in adoption and utilisation of ICT across the health sector. Technology acceptance research within the field of information systems has been limited in its application to health and there is a concurrent need to develop and gain empirical support for models of technology acceptance within health and to examine acceptance and utilisation issues amongst health professionals to improve the success of information system implementation in this arena. This paper outlines a project that examines ICT acceptance and utilisation by Australian occupational therapists. It describes the theoretical basis behind the development of a research model and the methodology being employed to empirically validate the model using substantial quantitative, qualitative and longitudinal data. Preliminary results from Phase II of the study are presented. The theoretical significance of this work is that it uses a thoroughly constructed research model, with potentially the largest sample size ever tested, to extend technology acceptance research into the health sector.

  6. Final waste forms project: Performance criteria for phase I treatability studies

    International Nuclear Information System (INIS)

    Gilliam, T.M.; Hutchins, D.A.; Chodak, P. III

    1994-06-01

    This document defines the product performance criteria to be used in Phase I of the Final Waste Forms Project. In Phase I, treatability studies will be performed to provide open-quotes proof-of-principleclose quotes data to establish the viability of stabilization/solidification (S/S) technologies. This information is required by March 1995. In Phase II, further treatability studies, some at the pilot scale, will be performed to provide sufficient data to allow treatment alternatives identified in Phase I to be more fully developed and evaluated, as well as to reduce performance uncertainties for those methods chosen to treat a specific waste. Three main factors influence the development and selection of an optimum waste form formulation and hence affect selection of performance criteria. These factors are regulatory, process-specific, and site-specific waste form standards or requirements. Clearly, the optimum waste form formulation will require consideration of performance criteria constraints from each of the three categories. Phase I will focus only on the regulatory criteria. These criteria may be considered the minimum criteria for an acceptable waste form. In other words, a S/S technology is considered viable only if it meet applicable regulatory criteria. The criteria to be utilized in the Phase I treatability studies were primarily taken from Environmental Protection Agency regulations addressed in 40 CFR 260 through 265 and 268; and Nuclear Regulatory Commission regulations addressed in 10 CFR 61. Thus the majority of the identified criteria are independent of waste form matrix composition (i.e., applicable to cement, glass, organic binders etc.)

  7. Imaging and diagnostic criteria for multiple sclerosis: are we there yet?

    International Nuclear Information System (INIS)

    Josey, Lawrence; Curley, Michael; Mousavi, Foroogh Jafari; Taylor, Bruce V.; Lucas, Robyn; Coulthard, Alan

    2012-01-01

    Excluding post traumatic injury, Multiple Sclerosis (MS) is the most common disabling neurological disorder of young adults. Although the effect on mortality is limited, the association of a young demographic and significant morbidity combine to make MS a devastating disease. Since MS was given its first detailed description in 1868, diagnostic criteria continue to evolve. Recently, there has been an international commitment to combine both clinical and paraclinical tests to arrive at an earlier diagnosis. Widespread acceptance of the use of MRI in diagnosis, monitoring and research has made the role of the radiologist more critical than ever in this disease. The primary diagnostic criteria for MS are the International Panel criteria, commonly referred to as the McDonald criteria and it is essential that the radiology community is aware of the work preceding these criteria, so that they are understood in the correct context and the importance acknowledged. Literature review utilising key word search to obtain the historical and current context of magnetic resonance imaging in the diagnosis of MS. A succinct description of the evolution of criteria for the diagnosis of MS. Radiologists must recognise that there are specific diagnostic criteria for MS that continue to evolve as a result of new research, improved technology and clinical experience and it is crucial that these criteria be applied in daily practice. It should be evident that diagnostic imaging criteria for MS will be most effective when combined with standardised MRI protocols such as those published by the international Consortium of Multiple Sclerosis Centres.

  8. Final waste forms project: Performance criteria for phase I treatability studies

    Energy Technology Data Exchange (ETDEWEB)

    Gilliam, T.M. [Oak Ridge National Lab., TN (United States); Hutchins, D.A. [Martin Marietta Energy Systems, Inc., Oak Ridge, TN (United States); Chodak, P. III [Massachusetts Institute of Technology (United States)

    1994-06-01

    This document defines the product performance criteria to be used in Phase I of the Final Waste Forms Project. In Phase I, treatability studies will be performed to provide {open_quotes}proof-of-principle{close_quotes} data to establish the viability of stabilization/solidification (S/S) technologies. This information is required by March 1995. In Phase II, further treatability studies, some at the pilot scale, will be performed to provide sufficient data to allow treatment alternatives identified in Phase I to be more fully developed and evaluated, as well as to reduce performance uncertainties for those methods chosen to treat a specific waste. Three main factors influence the development and selection of an optimum waste form formulation and hence affect selection of performance criteria. These factors are regulatory, process-specific, and site-specific waste form standards or requirements. Clearly, the optimum waste form formulation will require consideration of performance criteria constraints from each of the three categories. Phase I will focus only on the regulatory criteria. These criteria may be considered the minimum criteria for an acceptable waste form. In other words, a S/S technology is considered viable only if it meet applicable regulatory criteria. The criteria to be utilized in the Phase I treatability studies were primarily taken from Environmental Protection Agency regulations addressed in 40 CFR 260 through 265 and 268; and Nuclear Regulatory Commission regulations addressed in 10 CFR 61. Thus the majority of the identified criteria are independent of waste form matrix composition (i.e., applicable to cement, glass, organic binders etc.).

  9. Acceptance and Avoidance Processes at Different Levels of Psychological Recovery from Enduring Mental Illness.

    Science.gov (United States)

    Siqueira, Vinicius R; Oades, Lindsay G

    2015-01-01

    Objective. This study examined the use of psychological acceptance and experiential avoidance, two key concepts of Acceptance and Commitment Therapy (ACT), in the psychological recovery process of people with enduring mental illness. Method. Sixty-seven participants were recruited from the metropolitan, regional, and rural areas of New South Wales, Australia. They all presented some form of chronic mental illness (at least 12 months) as reflected in DSM-IV Axis I diagnostic criteria. The Acceptance and Action Questionnaire (AAQ-19) was used to measure the presence of psychological acceptance and experiential avoidance; the Recovery Assessment Scale (RAS) was used to examine the levels of psychological recovery; and the Scales of Psychological Well-Being was used to observe if there are benefits in utilizing psychological acceptance and experiential avoidance in the recovery process. Results. An analysis of objectively quantifiable measures found no clear correlation between the use of psychological acceptance and recovery in mental illness as measured by the RAS. The data, however, showed a relationship between psychological acceptance and some components of recovery, thereby demonstrating its possible value in the recovery process. Conclusion. The major contribution of this research was the emerging correlation that was observed between psychological acceptance and positive levels of psychological well-being among individuals with mental illness.

  10. Attitudes of belgian students of medicine, philosophy, and law toward euthanasia and the conditions for its acceptance.

    Science.gov (United States)

    Roelands, Marc; Van den Block, Lieve; Geurts, Sylvie; Deliens, Luc; Cohen, Joachim

    2015-01-01

    Euthanasia is legal in Belgium if due care criteria are met, which is judged by committees including physicians, ethicists, and jurists. We examined whether students in these disciplines differ in how they judge euthanasia as an acceptable act. A cross-sectional, anonymous e-mail survey revealed that they have similar attitudes and accept its legalization. Therefore, joint decision-making of physicians, ethicists, and lawyers regarding euthanasia seems to have a common attitudinal base in Belgium. However, they differ to some extent regarding the conditions they put forward for euthanasia being acceptable. Philosophy of life (religion) was an independent predictor of these attitudes.

  11. Nevada potential repository preliminary transportation strategy Study 2. Volume 1

    International Nuclear Information System (INIS)

    1996-02-01

    The objectives of this study were to build on the findings of the Nevada Potential Repository Preliminary Transportation Strategy Study 1 (CRWMS M ampersand O 1995b), and to provide additional information for input to the repository environmental impact statement (EIS) process. In addition, this study supported the future selection of a preferred rail corridor and/or heavy haul route based on defensible data, methods, and analyses. Study research did not consider proposed legislation. Planning was conducted according to the Civilian Radioactive Waste Management Program Plan (DOE 1994a). The specific objectives of Study 2 were to: eliminate or reduce data gaps, inconsistencies, and uncertainties, and strengthen the analysis performed in Study 1; develop a preliminary list of rail route evaluation criteria that could be used to solicit input from stakeholders during scoping meetings. The evaluation criteria will be revised based on comments received during scoping; restrict and refine the width of the four rail corridors identified in Study 1 to five miles or less, based on land use constraints and engineering criteria identified and established in Study 2; evaluate national-level effects of routing spent nuclear fuel and high-level waste to the four identified branch lines, including the effects of routing through or avoiding Las Vegas; continue to gather published land use information and environmental data to support the repository EIS; continue to evaluate heavy haul truck transport over three existing routes as an alternative to rail and provide sufficient information to support the repository EIS process; and evaluate secondary uses for rail (passenger use, repository construction, shared use)

  12. DEVELOPMENT OF USABILITY CRITERIA FOR E-LEARNING CONTENT DEVELOPMENT SOFTWARE

    Directory of Open Access Journals (Sweden)

    Serkan ÇELIK

    2012-04-01

    Full Text Available Revolutionary advancements have been observed in e-learning technologies though an amalgamated evaluation methodology for new generation e-learning content development tools is not available. The evaluation of educational software for online use must consider its usability and as well as its pedagogic effectiveness. This study is a first step towards the definition of criteria for evaluating e-learning tools. A preliminary user study involving a group of pre-service instructional designers, observed during their interaction with e-learning tools, is reported. Throughout the study, specific usability attributes of these e-learning tools were identified. Participants were assigned to rate the importance of functional and pedagogical competences proposed during the criteria development phase. The findings of the study revealed 31 evaluation criteria under the headings of technical, media, and assessment competences. Among the groups of benchmarks proposed and rated by the users, assessment was considered as the most important one while technical and media features were even.The following step was actual implemention of the usability criteria into evaluation of fifteen leading software used in e-learning across the world. Mostly, tools were observed as having limitations in terms of capabilities. Comparing to the other software, Captivate, Softchalk, and Lectora were regarded as outstanding tools by the participants. Following the discussion on the limitations of the study, some implications for further research were proposed.

  13. A generic approach for containment success criteria under severe accident loads

    International Nuclear Information System (INIS)

    Sammataro, R.F.; Solonick, W.R.; Edwards, N.W.

    1992-01-01

    The U.S. Department of Energy (DOE), Office of New Production Reactors (NP), has identified safety as the foremost design criterion for the Heavy Water New Production Reactor (NPR-HWR). The DOE-NP has issued the Deterministic Severe Accident Criteria (DSACs) to guide the design of the NPR-HWR containment for resistance to severe accidents. The DSAC concept provides for a generic approach for success criteria to predict the threshold of containment failure under severe accident loads. This concept consists of two parts: (1) Problem Statements that are qualitative and quantitative bases for calculating associated loadings and containment response to those loadings, and (2) Success Criteria that specify acceptable containment response measures and limits for each problem statement. This paper is limited to a discussion of a generic approach for containment success criteria. The main elements of these success criteria are expressed in terms of elastic stresses and inelastic strains. Containment performance is based on the best estimate of failure as predicted by either stress or strain, buckling, displacements, or ability to withstand missile perforation. Since these limits are best estimates of failure, no conservatism exists in these success criteria. Rather, conservatism is to be provided in the problem statements, i.e., the quantified severe accident loads. These success criteria are presented on a multi-tiered basis for static pressure and temperature loadings, dynamic loadings, and missiles. Within the static pressure and temperature loadings and the dynamic loadings, the criteria are separated into elastic analysis success criteria and inelastic analysis success criteria. Each of these areas, in turn, defines limits on either the stress or strain measures as well as on measures for buckling and displacements

  14. Multi-criteria multi-stakeholder decision analysis using a fuzzy-stochastic approach for hydrosystem management

    Directory of Open Access Journals (Sweden)

    Y. H. Subagadis

    2014-09-01

    Full Text Available The conventional methods used to solve multi-criteria multi-stakeholder problems are less strongly formulated, as they normally incorporate only homogeneous information at a time and suggest aggregating objectives of different decision-makers avoiding water–society interactions. In this contribution, Multi-Criteria Group Decision Analysis (MCGDA using a fuzzy-stochastic approach has been proposed to rank a set of alternatives in water management decisions incorporating heterogeneous information under uncertainty. The decision making framework takes hydrologically, environmentally, and socio-economically motivated conflicting objectives into consideration. The criteria related to the performance of the physical system are optimized using multi-criteria simulation-based optimization, and fuzzy linguistic quantifiers have been used to evaluate subjective criteria and to assess stakeholders' degree of optimism. The proposed methodology is applied to find effective and robust intervention strategies for the management of a coastal hydrosystem affected by saltwater intrusion due to excessive groundwater extraction for irrigated agriculture and municipal use. Preliminary results show that the MCGDA based on a fuzzy-stochastic approach gives useful support for robust decision-making and is sensitive to the decision makers' degree of optimism.

  15. Public acceptance of nuclear power in Taiwan

    International Nuclear Information System (INIS)

    Liao, T.T.L.

    1992-01-01

    It is necessary to reach the public acceptance for nuclear power development program. During the process of the application for the approval from the government to implement the Fourth Nuclear Power Plant program in Taiwan, we initialized a series of communication program in the last two years and are expecting to convince the public that to develops nuclear power is essential to the country from a viewpoint of energy diversified. The basic strategies of the communication program not only emphasized the new nuclear power project, but also for the long term public acceptance on nuclear power. The strategies include: (1) Preview and implement the promotion program for the performance of the existing nuclear power plants. (2) Designate and communicate with the major communication target groups: elected delegates, journalists, local residents, scholars and experts. (3) Edit and incorporate the basic nuclear knowledge into the preliminary school educational materials. (4) Subsidize the adjacent communities of nuclear power plants for the public well-being construction. In order to implement the mentioned strategies, Taipower has reorganized the public service department and the existing nuclear power plants, setup the nuclear exhibition center, conducted fullscale emergency drill biannually for each of nuclear power plant, and prepared the seminars for the teacher

  16. 76 FR 50726 - Riverbank Hydro No. 14, LLC; Notice of Preliminary Permit Application Accepted for Filing and...

    Science.gov (United States)

    2011-08-16

    ... (FPA), proposing to study the feasibility of the Tuttle Creek Hydroelectric Project (Tuttle Creek Project or project) to be located at the U.S. Army Corps of Engineers' (Corps) Tuttle Creek Dam, on Big Blue River, near Manhattan, Riley County, Kansas. The sole purpose of a preliminary permit, if issued...

  17. 75 FR 66083 - Iron Mask Hydro, LLC; Notice of Preliminary Permit Application Accepted for Filing and Soliciting...

    Science.gov (United States)

    2010-10-27

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 13723-000] Iron Mask Hydro..., Iron Mask Hydro, LLC filed an application for a preliminary permit, pursuant to section 4(f) of the Federal Power Act (FPA), proposing to study the feasibility of the Iron Mask Pumped Storage Project to be...

  18. Radiological design criteria for fusion power test facilities

    International Nuclear Information System (INIS)

    Singh, M.S.; Campbell, G.W.

    1982-01-01

    The quest for fusion power and understanding of plasma physics has resulted in planning, design, and construction of several major fusion power test facilities, based largely on magnetic and inertial confinement concepts. We have considered radiological design aspects of the Joint European Torus (JET), Livermore Mirror and Inertial Fusion projects, and Princeton Tokamak. Our analyses on radiological design criteria cover acceptable exposure levels at the site boundary, man-rem doses for plant personnel and population at large, based upon experience gained for the fission reactors, and on considerations of cost-benefit analyses

  19. The effect of parental involvement in CBT of anxious children: Preliminary results from a RCT study

    DEFF Research Database (Denmark)

    Esbjørn, Barbara Hoff; Breinholst, Sonja; Reinholdt-Dunne, Marie Louise

    2011-01-01

    Esbjørn, B. H., Breinholst, S., Reinholdt-Dunne, M. L., & Leth, I. (2011). The effect of parental involvement in CBT of anxious children: Preliminary results from a RCT study. Poster accepted for the Association for Behavioral and Cognitive Therapies, Toronto, Canada....

  20. The effect of discounting, different mortality reduction schemes and predictive cohort life tables on risk acceptability criteria

    International Nuclear Information System (INIS)

    Rackwitz, Ruediger

    2006-01-01

    Technical facilities should be optimal with respect to benefits and cost. Optimization of technical facilities involving risks for human life and limb require an acceptability criterion and suitable discount rates both for the public and the operator depending on for whom the optimization is carried out. The life quality index is presented and embedded into modem socio-economic concepts. A general risk acceptability criterion is derived. The societal life saving cost to be used in optimization as life saving or compensation cost and the societal willingness-to-pay based on the societal value of a statistical life or on the societal life quality index are developed. Different mortality reduction schemes are studied. Also, predictive cohort life tables are derived and applied. Discount rates γ must be long-term averages in view of the time horizon of some 20 to more than 100 years for the facilities of interest and net of inflation and taxes. While the operator may use long-term averages from the financial market for his cost-benefit analysis the assessment of interest rates for investments of the public into risk reduction is more difficult. The classical Ramsey model decomposes the real interest rate (=output growth rate) into the rate of time preference of consumption and the rate of economical growth multiplied by the elasticity of marginal utility of consumption. It is proposed to use a relatively small interest rate of 3% implying a rate of time preference of consumption of about 1%. This appears intergenerationally acceptable from an ethical point of view. Risk-consequence curves are derived for an example

  1. Consideration of Criteria for a Conceptual Near Surface Radioactive Waste disposal Facility in Kenya

    Energy Technology Data Exchange (ETDEWEB)

    Nderitu, Stanley Werugia; Kim, Changlak [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2014-05-15

    The purpose of the criteria is to limit the consequences of events which could lead to radiation exposures. This study will present an approach for establishing radiological waste acceptance criteria using a safety assessment methodology and illustrate some of its application in establishing limits on the total activity and the activity concentrations of radioactive waste to be disposed in a conceptual near surface disposal facility in Kenya. The approach will make use of accepted methods and computational schemes currently used in assessing the safety of near surface disposal facilities. The study will mainly focus on post-closure periods. The study will employ some specific inadvertent human intrusion scenarios in the development of example concentration ranges for the disposal of near-surface wastes. The overall goal of the example calculations is to illustrate the application of the scenarios in a performance assessment to assure that people in the future cannot receive a dose greater than an established limit. The specific performance assessments will use modified scenarios and data to establish acceptable disposal concentrations for specific disposal sites and conditions. Safety and environmental impacts assessments is required in the post-closure phase to support particular decisions in development, operation, and closure of a near surface repository.

  2. Proposed limiting values for performance criteria in acceptance testing of diagnostic X-ray equipment in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Baeuml, A.

    1989-01-01

    In the Federal Republic of Germany a new X-ray ordinance came into force in 1988 containing a specific paragraph on quality assurance for all medical X-ray units stipulating acceptance tests, regular checks and supervision by medical bodies and the competent authorities. Acceptance testing is to be performed by engineers from equipment suppliers of manufacturers in new and existing installations. It is expected that the service engineers will adjust the equipment in such a way as to obtain optimal performance before measurements are made, the results of which are to be stated in a certificate describing quality status of the equipment. A working group has developed guidelines for these acceptance tests. Items to be measured are reported and proposed limiting values and their tolerances are discussed. (author)

  3. Proposed limiting values for performance criteria in acceptance testing of diagnostic X-ray equipment in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Baeuml, A.

    1989-01-01

    In the Federal Republic of Germany a new X-ray ordinance came into force in 1988 containing a specific paragraph on quality assurance for all medical X-ray units stipulating acceptance tests, regular checks and supervision by medical bodies and the competent authorities. Acceptance testing is to be performed by engineers from the equipment suppliers or manufacturers in new and also existing installations. It is expected that the service engineers will adjust the equipment in such a way as to obtain optimal performance before measurements are made, the results of which are to be stated in a certificate describing the quality status of the equipment. A working group has developed guidelines for these acceptance tests. The items to be measured are reported and the proposed limiting values and their tolerances are discussed. (author)

  4. Creating a common Danish list of railway timetable evaluation criteria and revising the timetabling process accordingly

    DEFF Research Database (Denmark)

    Schittenhelm, Bernd; Landex, Alex

    2012-01-01

    criteria: capacity consumption on line sections and systematic timetable. Rank 2 criteria: robustness of the timetable and societal acceptance of the timetable and rank 3 criteria: travel time of trains and attractive transfer options. With this new tool a revised timetabling process at Rail Net Denmark...... is proposed. The very basic structure of the process cannot be changed due to EU legislation and Rail Net Europe guidelines. Key performance indicators derived from the identified timetabling criteria are introduced. As is a more iterative approach to the timetabling process due to the assumption of major...... improvements within timetable planning systems. This new iterative timetabling process using key performance indicators will result in improved future timetables and in lower levels of disagreement between timetable stakeholders....

  5. Research on geological disposal

    International Nuclear Information System (INIS)

    Uchida, Masahiro

    2011-01-01

    The aims of this research are to develop criteria for reviewing acceptability of the adequacy of the result of Preliminary and Detailed Investigations submitted by the implementor, and to establish a basic policy to secure safety for safety review. In FY 2010, 13 geology/climate related events for development of acceptance criteria for reviewing the adequacy of the result of Preliminary and Detailed Investigations were extracted. And the accuracy of geophysical exploration methods necessary for the Preliminary Investigation was evaluated. Regarding the research for safety review, we developed an idea of safety concept of Japanese geological disposal, and analyzed basic safety functions to secure safety. In order to verify the groundwater flow evaluation methods developed in regulatory research, the hydrological and geochemical data at Horonobe, northern Hokkaido were obtained, and simulated result of regional groundwater flow were compared with measured data. And we developed the safety scenario of geology/climate related events categorized by geological and geomorphological properties. Also we created a system to check the quality of research results in Japan and other countries in order to utilize for safety regulation, and developed a database system to compile them. (author)

  6. Acceptance test report, 241-SY-101 Flexible Receiver System, Phase 1 testing

    International Nuclear Information System (INIS)

    Ritter, G.A.

    1995-01-01

    This document summarizes the results of the Phase 1 acceptance test of the 241-SY-101 Flexible Receiver System (FRS). This acceptance test consisted of a pressure-decay/leak test of the containment bag to verify that the seams along the length of the bag had been adequately sealed. The sealing integrity of the FRS must be verified to ensure that the release of waste and aerosols will be minimized during the removal of the test mixer pump from Tank 241-SY-101. The FRS is one of six major components of the Equipment Removal System, which has been designed to retrieve, transport, and store the mixer pump. This acceptance test was performed at Lancs Industries in Kirkland, Washington on January 17, 1995. The bag temperature-compensated pressure loss of 575 Pa was below the acceptance criteria of 625 Pa and the test results were therefore found to be acceptable. The bag manufacturer estimates that 80--90% of the pressure loss is attributed to leakage around the bag inflation valve where the pressure gage was connected. A leak detector was applied over the entire bag during the pre-tests and no leakage was found. Furthermore, the leak rate corresponding to this pressure loss is very small when compared to the acceptable leak rate of the completely assembled FRS. The sealing integrity of the assembled FRS is verified in Phase 3 testing

  7. Methodology and preliminary models for analyzing nuclear safeguards decisions

    International Nuclear Information System (INIS)

    1978-11-01

    This report describes a general analytical tool designed to assist the NRC in making nuclear safeguards decisions. The approach is based on decision analysis--a quantitative procedure for making decisions under uncertain conditions. The report: describes illustrative models that quantify the probability and consequences of diverted special nuclear material and the costs of safeguarding the material, demonstrates a methodology for using this information to set safeguards regulations (safeguards criteria), and summarizes insights gained in a very preliminary assessment of a hypothetical reprocessing plant

  8. UO3 deactivation end point criteria

    International Nuclear Information System (INIS)

    Stefanski, L.D.

    1994-01-01

    The UO 3 Deactivation End Point Criteria are necessary to facilitate the transfer of the UO 3 Facility from the Office of Facility Transition and Management (EM-60) to the office of Environmental Restoration (EM-40). The criteria were derived from a logical process for determining end points for the systems and spaces at the UO 3 , Facility based on the objectives, tasks, and expected future uses pertinent to that system or space. Furthermore, the established criteria meets the intent and supports the draft guidance for acceptance criteria prepared by EM-40, open-quotes U.S. Department of Energy office of Environmental Restoration (EM-40) Decontamination and Decommissioning Guidance Document (Draft).close quotes For the UO 3 Facility, the overall objective of deactivation is to achieve a safe, stable and environmentally sound condition, suitable for an extended period, as quickly and economically as possible. Once deactivated, the facility is kept in its stable condition by means of a methodical surveillance and maintenance (S ampersand M) program, pending ultimate decontamination and decommissioning (D ampersand D). Deactivation work involves a range of tasks, such as removal of hazardous material, elimination or shielding of radiation fields, partial decontamination to permit access for inspection, installation of monitors and alarms, etc. it is important that the end point of each of these tasks be established clearly and in advance, for the following reasons: (1) End points must be such that the central element of the deactivation objective - to achieve stability - is unquestionably achieved. (2) Much of the deactivation work involves worker exposure to radiation or dangerous materials. This can be minimized by avoiding unnecessary work. (3) Each task is, in effect, competing for resources with other deactivation tasks and other facilities. By assuring that each task is appropriately bounded, DOE's overall resources can be used most fully and effectively

  9. Criteria for high-level waste disposal

    International Nuclear Information System (INIS)

    Sousselier, Y.

    1981-01-01

    Disposal of radioactive wastes is storage without the intention of retrieval. But in such storage, it may be useful and in some cases necessary to have the possibility of retrieval at least for a certain period of time. In order to propose some criteria for HLW disposal, one has to examine how this basic concept is to be applied. HLW is waste separated as a raffinate in the first cycle of solvent extraction in reprocessing. Such waste contains the bulk of fission products which have long half lives, therefore the safety of a disposal site, at least after a certain period of time, must be intrinsic, i.e. not based on human intervention. There is a consensus that such a disposal is feasible in a suitable geological formation in which the integrity of the container will be reinforced by several additional barriers. Criteria for disposal can be proposed for all aspects of the question. The author discusses the aims of the safety analysis, particularly the length of time for this analysis, and the acceptable dose commitments resulting from the release of radionuclides, the number and role of each barrier, and a holistic analysis of safety external factors. (Auth.)

  10. Decision modeling and acceptance criteria

    DEFF Research Database (Denmark)

    Ditlevsen, Ove Dalager

    2003-01-01

    compensation value of a human life and a public money equivalent of a human life, where the last value usually is considerably larger than the first value, it is possible from the decision analysis to determine an upper limit that the public should impose on the ratio of the owner´s expected loss rate......) that combines wealth in terms of Gross Domestic Product per person, life expectancy at birth, and yearly work time into a single number. The philosophy behind the published evaluations is that the prevention of a loss of a life is counteracted by a cost such that the LQI remains unchanged (Skjong R, Ronold K......; Decision Analysis; Life quality index; Random interest rate; Risk aversion; Socio-economic value; Uncertainty aversion...

  11. Bayesian risk-based acceptance criteria

    International Nuclear Information System (INIS)

    Martz, H.F.; Abramson, L.R.; Johnson, J.W.

    1996-04-01

    Mechanistic (or deterministic) analysis is traditionally performed in the process of designing a new nuclear reactor or reactor core and also as part of the safety analysis of existing reactors or reload cores. Mechanistic accident analysis is characterized by the specification of an initial operating condition, an initiating event, and subsequent system faults. These subsequent faults are often chosen, through such mechanisms as the worst single failure criterion, so as to maximize the consequences of the accident. Thus, the behavior of all reactor system hardware is prescribed before this analysis begins. Mechanistic analysis then attempts to predict the dynamic response of the system and usually involves detailed reactor physics and thermal-hydraulic predictions of the system behavior, including such parameters as power distributions in the reactor core, coolant temperatures and flow rates, and fuel clad temperature distributions. The objective of this analysis has typically been to establish and verify reactor operating limits and technical specifications, so that severe core damage (SCD) is prevented for a wide variety of reactor accidents

  12. Bridging the Gap between Social Acceptance and Ethical Acceptability.

    Science.gov (United States)

    Taebi, Behnam

    2017-10-01

    New technology brings great benefits, but it can also create new and significant risks. When evaluating those risks in policymaking, there is a tendency to focus on social acceptance. By solely focusing on social acceptance, we could, however, overlook important ethical aspects of technological risk, particularly when we evaluate technologies with transnational and intergenerational risks. I argue that good governance of risky technology requires analyzing both social acceptance and ethical acceptability. Conceptually, these two notions are mostly complementary. Social acceptance studies are not capable of sufficiently capturing all the morally relevant features of risky technologies; ethical analyses do not typically include stakeholders' opinions, and they therefore lack the relevant empirical input for a thorough ethical evaluation. Only when carried out in conjunction are these two types of analysis relevant to national and international governance of risky technology. I discuss the Rawlsian wide reflective equilibrium as a method for marrying social acceptance and ethical acceptability. Although the rationale of my argument is broadly applicable, I will examine the case of multinational nuclear waste repositories in particular. This example will show how ethical issues may be overlooked if we focus only on social acceptance, and will provide a test case for demonstrating how the wide reflective equilibrium can help to bridge the proverbial acceptance-acceptability gap. © 2016 The Authors Risk Analysis published by Wiley Periodicals, Inc. on behalf of Society for Risk Analysis.

  13. A generic approach for steel containment vessel success criteria for severe accident loads

    International Nuclear Information System (INIS)

    Sammataro, R.F.; Solonick, W.R.; Edwards, N.W.

    1993-01-01

    Safety has been defined as the foremost design criterion for the Heavy Water New Production Reactor (NPR-HWR) by the U.S. DOE, Office of New Production Reactors (NP). The DOE-NP issued the Deterministic Severe Accident Criteria (DSAC) concept to guide the design of the NPR-HWR containment for resistance to severe accidents. The DSAC concept provides for a generic approach for containment vessel success criteria to predict the threshold of containment failure under severe accident loads. This concept consists of two parts: (1) Problem Statements and (2) Success Criteria. The paper is limited to a discussion of a success criteria. These criteria define acceptable containment response measures and limits for each problem statement. The criteria are based on the 'best estimate' of failure with no conservatism. Rather, conservatism, if required, is to be provided in the problem statements prepared by the designer and/or the regulatory authorities. The success criteria are presented on a multi-tiered basis for static pressure and temperature loadings, dynamic loadings, and missiles that may impact the containment. Within the static pressure and temperature loadings and the dynamic loadings, the criteria are separated into elastic analysis success criteria and inelastic analysis success criteria. Each of these areas, in turn, defines limits on either the stress or strain measures as well as on measures for buckling and displacements. The rationale upon which these criteria are based is contained in referenced documents. Rigorous validation of the criteria by comparison with results from analytical or experimental programs and application of the criteria to a containment design remain as future tasks. (orig./HP)

  14. Decommissioning of nuclear facilities using current criteria

    International Nuclear Information System (INIS)

    Shum, E.Y.; Swift, J.J.; Malaro, J.C.

    1991-01-01

    When a licensed nuclear facility ceases operation, the US Nuclear Regulatory Commission (NRC) is responsible for ensuring that the facility and its site are decontaminated to an acceptable level so that it is safe to release that facility and site for unrestricted public use. Currently, the NRC is developing decommissioning criteria based on reducing public doses from residual contamination in soils and structures at sites released for unrestricted use to as low as is reasonably achievable (ALARA). Plans are to quantify ALARA in terms of an annual total effective dose equivalent (TEDE) to an average member of the most highly exposed population group. The NRC is working on a regulatory guidance document to provide a technical basis for translating residual contamination levels to annual dose levels. Another regulatory guide is being developed to provide guidance to the licensee on how to conduct radiological surveys to demonstration compliance with the NRC decommissioning criteria. The methods and approaches used in these regulatory guides on the decommissioning of a nuclear facility are discussed in the paper

  15. Microbiological criteria for good manufacturing practice (GMP)

    Energy Technology Data Exchange (ETDEWEB)

    Farkas, J. (Inst. of Preservation and Livestock Products Technology, Univ. of Horticulture and Food Industry, Budapest (Hungary)); Zukal, E. (Inst. of Preservation and Livestock Products Technology, Univ. of Horticulture and Food Industry, Budapest (Hungary))

    1992-01-01

    Good manufacturing practice (GMP) consist of an effective manufacturing operation and an effective application of food control. GMP is best supported by the Hazard Analysis Critical Control Point system (HACCP) of the preventive quality assurance, which requires that food irradiation as any food processing technology should be used only with foods of an acceptable quality and adequate handling and storage procedures should precede and follow the processing. The paper concentrates on the first element of the HACCP system for an irradiation plant: the incoming product control, i.e. whether GMP of foods to be irradiated can be assessed by establishing microbiological criteria for their previous good manufacturing practice. In this regard, it summarizes considerations and findings of a ''Consultation on Microbiological Criteria for Foods to be Further Processed Including by Irradiation'' held in 1989 by the International Consultative Group on Food irradiation at the Headquarters of the World Health Organization, Geneva. Difficulties in establishing reference values and defining good manufacturing practices will be pointed out. (orig.)

  16. Toward optimizing patient-specific IMRT QA techniques in the accurate detection of dosimetrically acceptable and unacceptable patient plans.

    Science.gov (United States)

    McKenzie, Elizabeth M; Balter, Peter A; Stingo, Francesco C; Jones, Jimmy; Followill, David S; Kry, Stephen F

    2014-12-01

    The authors investigated the performance of several patient-specific intensity-modulated radiation therapy (IMRT) quality assurance (QA) dosimeters in terms of their ability to correctly identify dosimetrically acceptable and unacceptable IMRT patient plans, as determined by an in-house-designed multiple ion chamber phantom used as the gold standard. A further goal was to examine optimal threshold criteria that were consistent and based on the same criteria among the various dosimeters. The authors used receiver operating characteristic (ROC) curves to determine the sensitivity and specificity of (1) a 2D diode array undergoing anterior irradiation with field-by-field evaluation, (2) a 2D diode array undergoing anterior irradiation with composite evaluation, (3) a 2D diode array using planned irradiation angles with composite evaluation, (4) a helical diode array, (5) radiographic film, and (6) an ion chamber. This was done with a variety of evaluation criteria for a set of 15 dosimetrically unacceptable and 9 acceptable clinical IMRT patient plans, where acceptability was defined on the basis of multiple ion chamber measurements using independent ion chambers and a phantom. The area under the curve (AUC) on the ROC curves was used to compare dosimeter performance across all thresholds. Optimal threshold values were obtained from the ROC curves while incorporating considerations for cost and prevalence of unacceptable plans. Using common clinical acceptance thresholds, most devices performed very poorly in terms of identifying unacceptable plans. Grouping the detector performance based on AUC showed two significantly different groups. The ion chamber, radiographic film, helical diode array, and anterior-delivered composite 2D diode array were in the better-performing group, whereas the anterior-delivered field-by-field and planned gantry angle delivery using the 2D diode array performed less well. Additionally, based on the AUCs, there was no significant difference

  17. PRELIMINARY SELECTION OF MGR DESIGN BASIS EVENTS

    International Nuclear Information System (INIS)

    Kappes, J.A.

    1999-01-01

    The purpose of this analysis is to identify the preliminary design basis events (DBEs) for consideration in the design of the Monitored Geologic Repository (MGR). For external events and natural phenomena (e.g., earthquake), the objective is to identify those initiating events that the MGR will be designed to withstand. Design criteria will ensure that radiological release scenarios resulting from these initiating events are beyond design basis (i.e., have a scenario frequency less than once per million years). For internal (i.e., human-induced and random equipment failures) events, the objective is to identify credible event sequences that result in bounding radiological releases. These sequences will be used to establish the design basis criteria for MGR structures, systems, and components (SSCs) design basis criteria in order to prevent or mitigate radiological releases. The safety strategy presented in this analysis for preventing or mitigating DBEs is based on the preclosure safety strategy outlined in ''Strategy to Mitigate Preclosure Offsite Exposure'' (CRWMS M andO 1998f). DBE analysis is necessary to provide feedback and requirements to the design process, and also to demonstrate compliance with proposed 10 CFR 63 (Dyer 1999b) requirements. DBE analysis is also required to identify and classify the SSCs that are important to safety (ITS)

  18. [Early diagnosis of HIV in Primary Care in Spain. Results of a pilot study based on targeted screening based on indicator conditions, behavioral criteria and region of origin].

    Science.gov (United States)

    Agustí, Cristina; Martín-Rabadán, María; Zarco, José; Aguado, Cristina; Carrillo, Ricard; Codinachs, Roger; Carmona, Jose Manuel; Casabona, Jordi

    2018-03-01

    To estimate the prevalence of HIV infection in patients diagnosed with an indicator condition (IC) for HIV and/or risk behavior for their acquisition and/or coming from high prevalence countries. To determine the acceptability and feasibility of offering HIV testing based on IC and behavioral and origin criteria in Primary Care (PC). Cross-sectional study in a convenience sample. Six PC centers in Spain. The inclusion criteria were: patients between 16 and 65years old who presented at least one of the proposed ICs and/or at least one of the proposed behavioral and/or origin criteria. A total of 388 patients participated. HIV serology was offered to all patients who met the inclusion criteria. Description of IC frequency, behavioral and origin criteria. Prevalence of HIV infection. Level of acceptability and feasibility of the HIV screening based on IC and behavioral and origin criteria. A total of 174 patients had an IC (44.84%). The most common behavioral criterion was: having unprotected sex at some time in life with people who did not know their HIV status (298; 76.8%). Four HIV+ patients (1.03%) were diagnosed. All had an IC and were men who had sex with men. The level of acceptability in PC was high. Offering HIV testing to patients with IC and behavioral criteria is feasible and effective in PC. Copyright © 2017 Elsevier España, S.L.U. All rights reserved.

  19. Acceptability of HIV self-testing: a systematic literature review.

    Science.gov (United States)

    Krause, Janne; Subklew-Sehume, Friederike; Kenyon, Chris; Colebunders, Robert

    2013-08-08

    The uptake of HIV testing and counselling services remains low in risk groups around the world. Fear of stigmatisation, discrimination and breach of confidentiality results in low service usage among risk groups. HIV self-testing (HST) is a confidential HIV testing option that enables people to find out their status in the privacy of their homes. We evaluated the acceptability of HST and the benefits and challenges linked to the introduction of HST. A literature review was conducted on the acceptability of HST in projects in which HST was offered to study participants. Besides acceptability rates of HST, accuracy rates of self-testing, referral rates of HIV-positive individuals into medical care, disclosure rates and rates of first-time testers were assessed. In addition, the utilisation rate of a telephone hotline for counselling issues and clients` attitudes towards HST were extracted. Eleven studies met the inclusion criteria (HST had been offered effectively to study participants and had been administered by participants themselves) and demonstrated universally high acceptability of HST among study populations. Studies included populations from resource poor settings (Kenya and Malawi) and from high-income countries (USA, Spain and Singapore). The majority of study participants were able to perform HST accurately with no or little support from trained staff. Participants appreciated the confidentiality and privacy but felt that the provision of adequate counselling services was inadequate. The review demonstrates that HST is an acceptable testing alternative for risk groups and can be performed accurately by the majority of self-testers. Clients especially value the privacy and confidentiality of HST. Linkage to counselling as well as to treatment and care services remain major challenges.

  20. The Relationship between Treatment Integrity and Acceptability of Reading Interventions for Children with Attention-Deficit/Hyperactivity Disorder

    Science.gov (United States)

    Mautone, Jennifer A.; DuPaul, George J.; Jitendra, Asha K.; Tresco, Katy E.; Junod, Rosemary Vile; Volpe, Robert J.

    2009-01-01

    This study examined the relationship between treatment integrity and acceptability for reading interventions across two consultation models, intensive data-based academic intervention (IDAI) and traditional data-based academic intervention (TDAI). Participants included 83 first- through fourth-grade students who met research criteria for…

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