WorldWideScience

Sample records for program ii revision

  1. SARP-II: Safeguards Accounting and Reports Program, Revised

    International Nuclear Information System (INIS)

    Kempf, C.R.

    1994-01-01

    A computer code, SARP (Safeguards Accounting and Reports Program) which will generate and maintain at-facility safeguards accounting records, and generate IAEA safeguards reports based on accounting data input by the user, was completed in 1990 by the Safeguards, Safety, and Nonproliferation Division (formerly the Technical Support Organization) at Brookhaven National Laboratory as a task under the US Program of Technical Support to IAEA safeguards. The code was based on a State System of Accounting for and Control of Nuclear Material (SSAC) for off-load refueled power reactor facilities, with model facility and safeguards accounting regime as described in IAEA Safeguards Publication STR-165. Since 1990, improvements in computing capabilities and comments and suggestions from users engendered revision of the original code. The result is an updated, revised version called SARP-II which is discussed in this report

  2. Seismic safety margin research program. Program plan, Revision II

    International Nuclear Information System (INIS)

    Smith, P.D.; Tokarz, F.J.; Bernreuter, D.L.; Cummings, G.E.; Chou, C.K.; Vagliente, V.N.; Johnson, J.J.; Dong, R.G.

    1978-01-01

    The document has been prepared pursuant to the second meeting of the Senior Research Review Group of the Seismic Safety Margin Research Program (SSMRP), which was held on June 15, 16, 1978. The major portion of the material contained in the document is descriptions of specific subtasks to be performed on the SSMRP. This is preceded by a brief discussion of the objective of the SSMRP and the approach to be used. Specific subtasks to be performed in Phase I of the SSMRP are as follows: (1) plant/site selection, (2) seismic input, (3) soil structure interaction, (4) structural building response, (5) structural sub-system response, (6) fragility, (7) system analysis, and (8) Phase II task definition

  3. Graphic Display Development Program. Volume II, Revision 0. Appendices

    International Nuclear Information System (INIS)

    1984-12-01

    The objective of this project is to demonstrate the feasibility and utility of developing a set of graphic displays to support symptom-based emergency operating procedures (EOPs). Development of generic graphic displays is based on Revision 3 of the symptomatic Emergency Procedure Guidelines (EPGs) prepared by the BWR Owners' Group (BWROG), and development of plant-specific graphic displays is based on a set of emergency operating procedures developed from these EPGs

  4. HERMES II experimenters' manual (revised)

    International Nuclear Information System (INIS)

    Schuch, R.L.

    1977-04-01

    The HERMES II is a high-intensity laboratory photon source for gamma-ray radiation effects experiments as well as a high-energy pulsed electron beam generator for a variety of potential applications. The purpose of this manual is to serve as a basic source of information for prospective users of HERMES. Included is a brief discussion of the design and operation of the accelerator system as well as a summary of environmental data for x-ray operation and output characteristics for electron beam modes. The manual also contains a description of the HERMES experimental facilities, including geometry of the test cell, instrumentation and data collection capabilities, and services and support available to experimenters

  5. Program plan for the DOE Office of Fusion Energy First Wall/Blanket/Shield Engineering Technology Program. Volume II. Detailed technical plan. Revision 2

    International Nuclear Information System (INIS)

    1982-08-01

    The four sections which comprise Part II describe in detail the technical basis for each of the four Program Elements (PE's) of the FWBS Engineering Technology Program (ETP). Each PE is planned to be executed in a number of phases. The purpose of the DTP's is to delineate detailed near-term research, development, and testing required to establish a FWBS engineering data base. Optimum testing strategies and construction of test facilities where needed are identified. The DTP's are based on guidelines given by Argonne National Laboratory which included the basic programmatic goals and the requirements for the types of tests and test conditions

  6. Revised GCFR safety program plan

    International Nuclear Information System (INIS)

    Kelley, A.P.; Boyack, B.E.; Torri, A.

    1980-05-01

    This paper presents a summary of the recently revised gas-cooled fast breeder reactor (GCFR) safety program plan. The activities under this plan are organized to support six lines of protection (LOPs) for protection of the public from postulated GCFR accidents. Each LOP provides an independent, sequential, quantifiable risk barrier between the public and the radiological hazards associated with postulated GCFR accidents. To implement a quantitative risk-based approach in identifying the important technology requirements for each LOP, frequency and consequence-limiting goals are allocated to each. To ensure that all necessary tasks are covered to achieve these goals, the program plan is broken into a work breakdown structure (WBS). Finally, the means by which the plan is being implemented are discussed

  7. 40 CFR 76.7 - Revised NOX emission limitations for Group 1, Phase II boilers.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 16 2010-07-01 2010-07-01 false Revised NOX emission limitations for Group 1, Phase II boilers. 76.7 Section 76.7 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) ACID RAIN NITROGEN OXIDES EMISSION REDUCTION PROGRAM § 76.7 Revised NOX...

  8. Revised inspection program for nuclear power plants

    International Nuclear Information System (INIS)

    1978-01-01

    The United States Nuclear Regulatory Commission (NRC) regulates nuclear power plants to assure adequate protection of the public and the environment from the dangers associated with nuclear materials. NRC fulfills this responsibility through comprehensive safety reviews of nuclear facilities, licensing of organizations that use nuclear materials, and continuing inspection. The NRC inspection program is currently conducted from the five regional offices in or near Philadelphia, Atlanta, Chicago, Dallas and San Francisco. Inspectors travel from the regional offices to nuclear power plants in various phases of construction, test and operation in order to conduct inspections. However, in June 1977 the Commission approved a revision to the inspection program that will include stationing inspectors at selected plants under construction and at all plants in operation. In addition, the revised program provides for appraising the performance of licensees on a national basis and involves more direct measurement and observation by NRC inspectors of work and tests in progress. The program also includes enhanced career management consisting of improved training and career development for inspectors and other professionals. The report was requested in the Conference Report on the NRC Authorization for Appropriations for Fiscal Year 1978. The report provides a discussion of the basis for both the current and revised inspection programs, describes these programs, and shows how the NRC inspection force will be trained and utilized. In addition, the report includes a discussion of the actions that will be taken to assure the objectivity of inspectors

  9. Active sites environmental monitoring Program - Program Plan: Revision 2

    International Nuclear Information System (INIS)

    Morrissey, C.M.; Hicks, D.S.; Ashwood, T.L.; Cunningham, G.R.

    1994-05-01

    The Active Sites Environmental Monitoring Program (ASEMP), initiated in 1989, provides early detection and performance monitoring of active low-level-waste (LLW) and transuranic (TRU) waste facilities at Oak Ridge National Laboratory (ORNL). Several changes have recently occurred in regard to the sites that are currently used for waste storage and disposal. These changes require a second set of revisions to the ASEMP program plan. This document incorporates those revisions. This program plan presents the organization and procedures for monitoring the active sites. The program plan also provides internal reporting levels to guide the evaluation of monitoring results

  10. Operations program plan: Revision 3

    International Nuclear Information System (INIS)

    1988-07-01

    This document, the Operations Program Plan (OPP), has been developed as the seven-year master plan for operation of WIPP. The OPP was authorized by the Albuquerque Field Office of the Department of Energy (DOE-AL) and that organization's WIPP Project Office (DOE-WPO) in Carlsbad, New Mexico. The OPP is the directive from the DOE-WPO Project Manager as to how the WIPP is to be managed, operated, and administered. As the top tier management document for WIPP, the OPP establishes organizational responsibilities and an organizational structure for the Waste Isolation Division (WID) of Westinghouse Electric Corporation. The OPP sets policy and tone for conducting WIPP operations; it requires and specifically authorizes implementing documents (e.g., manuals). It has also proven instrumental in the budgeting and planning process, most particularly in expediting the preparation of specific budgets and detailed schedules for each of the numerous work packages. The OPP is also used to communicate information about WIPP operations

  11. Waste Management Program management plan. Revision 1

    International Nuclear Information System (INIS)

    1997-02-01

    As the prime contractor to the Department of Energy Idaho Operations Office (DOE-ID), Lockheed Martin Idaho Technologies Company (LMITCO) provides comprehensive waste management services to all contractors at the Idaho National Engineering and Environmental Laboratory (INEEL) through the Waste Management (WM) Program. This Program Management Plan (PMP) provides an overview of the Waste Management Program objectives, organization and management practices, and scope of work. This document will be reviewed at least annually and updated as needed to address revisions to the Waste Management's objectives, organization and management practices, and scope of work. Waste Management Program is managed by LMITCO Waste Operations Directorate. The Waste Management Program manages transuranic, low-level, mixed low-level, hazardous, special-case, and industrial wastes generated at or transported to the INEEL

  12. Waste Management Program management plan. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-02-01

    As the prime contractor to the Department of Energy Idaho Operations Office (DOE-ID), Lockheed Martin Idaho Technologies Company (LMITCO) provides comprehensive waste management services to all contractors at the Idaho National Engineering and Environmental Laboratory (INEEL) through the Waste Management (WM) Program. This Program Management Plan (PMP) provides an overview of the Waste Management Program objectives, organization and management practices, and scope of work. This document will be reviewed at least annually and updated as needed to address revisions to the Waste Management`s objectives, organization and management practices, and scope of work. Waste Management Program is managed by LMITCO Waste Operations Directorate. The Waste Management Program manages transuranic, low-level, mixed low-level, hazardous, special-case, and industrial wastes generated at or transported to the INEEL.

  13. Typewriting Syllabus: Part II: Modules. 1976 Revision.

    Science.gov (United States)

    New York State Education Dept., Albany. Bureau of Occupational and Career Curriculum Development.

    The document is the second of a two-part set on typewriting and focuses on the nine modules of instruction. The nine modules are: (1) keyboard mastery and skill development, (2) basic typewriting competencies, (2a) personal use typewriting, (3) introduction to office typewriting I, (4) introduction to office typewriting II, (5) intermediate office…

  14. HANARO fuel irradiation test (II): revision

    Energy Technology Data Exchange (ETDEWEB)

    Sohn, D. S.; Kim, H.; Chae, H. T.; Lee, C. S.; Kim, B. G.; Lee, C. B

    2001-04-01

    In order to fulfill the requirement to prove HANARO fuel integrity when irradiated at a power greater than 112.8 kW/m, which was imposed during HANARO licensing, and to verify the irradiation performance of HANARO fuel, the in-pile irradiation test of HANARO fuel has been performed. Two types of test fuel, the un-instrumented Type A fuel for higher burnup irradiation in shorter period than the driver fuel and the instrumented Type B fuel for higher linear heat rate and precise measurement of irradiation conditions, have been designed and fabricated. The test fuel assemblies were irradiated in HANARO. The two Type A fuel assemblies were intended to be irradiated to medium and high burnup and have been discharged after 69.9 at% and 85.5 at% peak burnup, respectively. Type B fuel assembly was intended to be irradiated at high power with different instrumentations and achieved a maximum power higher than 120 kW/m without losing its integrity and without showing any irregular behavior. The Type A fuel assemblies were cooled for about 6 months and transported to the IMEF(Irradiated Material Examination Facility) for consequent evaluation. Detailed non-destructive and destructive PIE (Post-Irradiation Examination), such as the measurement of burnup distribution, fuel swelling, clad corrosion, dimensional changes, fuel rod bending strength, micro-structure, etc., has been performed. The measured results have been analysed/compared with the predicted performance values and the design criteria. It has been verified that HANARO fuel maintains proper in-pile performance and integrity even at the high power of 120 kw/m up to the high burnup of 85 at%. This report is the revision of KAERI/TR-1816/2001 on the irradiation test for HANARO fuel.

  15. Signs of revision in Don Quixote, Part II

    Directory of Open Access Journals (Sweden)

    Gonzalo Pontón

    2016-11-01

    Full Text Available This article provides new evidences in favour of the hypothesis that Cervantes, after finishing Don Quixote, Part II, partially revised the original, introducing some significant changes and additions, mainly in the last chapters. The analysis of some narrative inconsistencies, that cannot be interpreted as mere mistakes but as significant textual traces, reveals a process of re-elaboration –a process that affects at least four sections of the novel. Most of the evidence gathered here suggests that this revision is closely linked to Avellaneda’s continuation, in the sense that Cervantes tried to challenge the apocriphal Quixote making last-time interventions in his own text.

  16. Stream II-V5: Revision Of Stream II-V4 To Account For The Effects Of Rainfall Events

    International Nuclear Information System (INIS)

    Chen, K.

    2010-01-01

    STREAM II-V4 is the aqueous transport module currently used by the Savannah River Site emergency response Weather Information Display (WIND) system. The transport model of the Water Quality Analysis Simulation Program (WASP) was used by STREAM II to perform contaminant transport calculations. WASP5 is a US Environmental Protection Agency (EPA) water quality analysis program that simulates contaminant transport and fate through surface water. STREAM II-V4 predicts peak concentration and peak concentration arrival time at downstream locations for releases from the SRS facilities to the Savannah River. The input flows for STREAM II-V4 are derived from the historical flow records measured by the United States Geological Survey (USGS). The stream flow for STREAM II-V4 is fixed and the flow only varies with the month in which the releases are taking place. Therefore, the effects of flow surge due to a severe storm are not accounted for by STREAM II-V4. STREAM II-V4 has been revised to account for the effects of a storm event. The steps used in this method are: (1) generate rainfall hyetographs as a function of total rainfall in inches (or millimeters) and rainfall duration in hours; (2) generate watershed runoff flow based on the rainfall hyetographs from step 1; (3) calculate the variation of stream segment volume (cross section) as a function of flow from step 2; (4) implement the results from steps 2 and 3 into the STREAM II model. The revised model (STREAM II-V5) will find the proper stream inlet flow based on the total rainfall and rainfall duration as input by the user. STREAM II-V5 adjusts the stream segment volumes (cross sections) based on the stream inlet flow. The rainfall based stream flow and the adjusted stream segment volumes are then used for contaminant transport calculations.

  17. Engineering drawing field verification program. Revision 3

    International Nuclear Information System (INIS)

    Ulk, P.F.

    1994-01-01

    Safe, efficient operation of waste tank farm facilities is dependent in part upon the availability of accurate, up-to-date plant drawings. Accurate plant drawings are also required in support of facility upgrades and future engineering remediation projects. This supporting document establishes the procedure for performing a visual field verification of engineering drawings, the degree of visual observation being performed and documenting the results. A copy of the drawing attesting to the degree of visual observation will be paginated into the released Engineering Change Notice (ECN) documenting the field verification for future retrieval and reference. All waste tank farm essential and support drawings within the scope of this program will be converted from manual to computer aided drafting (CAD) drawings. A permanent reference to the field verification status will be placed along the right border of the CAD-converted drawing, referencing the revision level, at which the visual verification was performed and documented

  18. WASTE CERTIFICATION PROGRAM PLAN - REVISION 7

    International Nuclear Information System (INIS)

    MORGAN, LK

    2002-01-01

    The primary changes that have been made to this revision reflect the relocation of the Waste Certification Official (WCO) organizationally from the Quality Services Division (QSD) into the Laboratory Waste Services (LWS) Organization. Additionally, the responsibilities for program oversight have been differentiated between the QSD and LWS. The intent of this effort is to ensure that those oversight functions, which properly belonged to the WCO, moved with that function; but retain an independent oversight function outside of the LWS Organization ensuring the potential for introduction of organizational bias, regarding programmatic and technical issues, is minimized. The Waste Certification Program (WCP) itself has been modified to allow the waste certification function to be performed by any of the personnel within the LWS Waste Acceptance/Certification functional area. However, a single individual may not perform both the technical waste acceptance review and the final certification review on the same 2109 data package. Those reviews must be performed by separate individuals in a peer review process. There will continue to be a designated WCO who will have lead programmatic responsibility for the WCP and will exercise overall program operational oversite as well as determine the overall requirements of the certification program. The quality assurance organization will perform independent, outside oversight to ensure that any organizational bias does not degrade the integrity of the waste certification process. The core elements of the previous WCP have been retained, however, the terms and process structure have been modified.. There are now two ''control points,'' (1) the data package enters the waste certification process with the signature of the Generator Interface/Generator Interface Equivalent (GI/GIE), (2) the package is ''certified'', thus exiting the process. The WCP contains three steps, (1) the technical review for waste acceptance, (2) a review of the

  19. Belief Revision in the GOAL Agent Programming Language

    DEFF Research Database (Denmark)

    Spurkeland, Johannes Svante; Jensen, Andreas Schmidt; Villadsen, Jørgen

    2013-01-01

    Agents in a multiagent system may in many cases find themselves in situations where inconsistencies arise. In order to properly deal with these, a good belief revision procedure is required. This paper illustrates the usefulness of such a procedure: a certain belief revision algorithm is consider...... in order to deal with inconsistencies and, particularly, the issue of inconsistencies, and belief revision is examined in relation to the GOAL agent programming language....

  20. 77 FR 47302 - South Dakota: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2012-08-08

    ...: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... EPA proposed to authorize South Dakota's State Hazardous waste management Program revisions published... to the hazardous waste program revisions submitted by South Dakota. The Agency published a Proposed...

  1. 77 FR 15273 - Oklahoma: Final Authorization of State Hazardous Waste Management Program Revision

    Science.gov (United States)

    2012-03-15

    ...: Final Authorization of State Hazardous Waste Management Program Revision AGENCY: Environmental... hazardous waste management program. We authorized the following revisions: Oklahoma received authorization... its program revision in accordance with 40 CFR 271.21. The Oklahoma Hazardous Waste Management Act...

  2. Revised analysis of singly ionized xenon, Xe II

    International Nuclear Information System (INIS)

    Hansen, J.E.; Persson, W.

    1987-01-01

    We present a revised analysis of the spectrum of singly ionized xenon, Xe II. This spectrum has been reanalyzed on the basis of the wavelength material published by Drs J. C. Boyce and C. J. Humphreys. The latter has kindly placed the original wavelength list covering the wavelength range 10220-390 A at our disposal. We report 161 energy levels which have been identified on the basis of classifications of 950 lines. We report first f and g levels in Xe II. Also a number of g-factors have been determined for the first time and we give in total 75 g-factors. We have carried out least-squares fits to the even configurations and report the resulting parameter values and eigenvector compositions. A least-squares fit to the 5p 4 6p configuration is also reported. The levels have been named in jK and for many levels also in LS coupling. The former is the better coupling scheme for Xe II. We present an analysis of the 5s photoelectron satellite spectrum of Xe based on our calculated eigenvector compositions and calculations of transition probabilities for ground state transitions as well as lifetimes for the 6p levels. The latter are compared to recent experimental measurements. A list of wavelengths for observed laser transitions showing the present classifications and a discussion of the determination of the ionization potential of Xe II concludes the paper. (orig.)

  3. Communication Arts Curriculum: A Model Program. Revised.

    Science.gov (United States)

    Tamaqua Area School District, PA.

    This publication describes, in three sections, a high school Communication Arts Curriculum (CAC) program designed to further students' communication skills as they participate in student-centered learning activities in the fine arts, the practical arts, and the performing arts. "Program Operation" includes a course outline and inventories for…

  4. Revision 2 of the NPP Krsko Decommissioning Program Is Stalled

    International Nuclear Information System (INIS)

    Levanat, I.; Lokner, V.; Rapic, A.; Zeleznik, N.; Kralj, M.

    2012-01-01

    Revision 2 of the joint Slovenian-Croatian Program of NPP Krsko Decommissioning and SF andLILW Disposal was scheduled to be finished and formally approved by the end of 2009, in accordance with the bilateral Agreement on the NPP. Slightly behind the schedule, the Project team completed the entire document during spring of 2010, and in June 2010 drafted a proposal for a peer review of the Program by a dedicated IAEA expert mission. This procedure was agreed upon at the last session (May 2010) of the Intergovernmental Commission for implementation of the Agreement, when the Commission was acquainted with the five scenarios of the Revision 2 and with the estimates of their costs/financing. It was expected that the peer review would be performed soon, and that formal adoption of the Revision 2 would follow. Although in this process of approval some decisions remained to be made by the stakeholders, the Project team did select and recommend one scenario to be used for costing purposes, in order to ensure that most necessary corrections in Program financing would be timely adopted. However, the planned IAEA review was cancelled by the Advisory board, the body nominated by the Commission ''to supervise the activities and resolve the issues raised by the Project team''. By this cancellation, the process of Program revision was effectively stalled, because the Advisory board could not clearly define further course of action: differing views between the Slovenian and the Croatian part of the Advisory board appeared, in particular regarding the set of Program scenarios and regarding the appropriateness of the Revision 2 document for the IAEA review; nonetheless, the Advisory board sent to the Project team a compilation of requests to modify Revision 2 document. The Project team determined that some minor requests were easy to fulfill, but other modifications could only be carried out after changes in the boundary conditions (approved by the Commission), or changes in national

  5. Periodical test program in depth revision

    International Nuclear Information System (INIS)

    Feltin, C.; Zermizoglou, R.

    1987-11-01

    Inspection visits made to different sites during 1980 and 1981 evidenced the need to extend and define more precisely the periodical tests performed on safety related systems; thus Electricite de France was requested by the Safety Authorities to re-examine the periodical test program for all safety related systems. This paper presents the methodology adopted by Electricite de France in order to perform an exhaustive analysis of the periodical test program for the 900 and 1300 MWe plants, and the organization set up at the IPSN at one hand and Electricite de France on the other hand for the purpose of elaborating a periodical test program which would be ratified by the Safety Authorities

  6. 75 FR 48815 - Medicaid Program and Children's Health Insurance Program (CHIP); Revisions to the Medicaid...

    Science.gov (United States)

    2010-08-11

    ... Parts 431, 447, and 457 Medicaid Program and Children's Health Insurance Program (CHIP); Revisions to... 431, 447, and 457 [CMS-6150-F] RIN 0938-AP69 Medicaid Program and Children's Health Insurance Program... final rule implements provisions from the Children's Health Insurance Program Reauthorization Act of...

  7. Operating and Assurance Program Plan. Revision 4

    Energy Technology Data Exchange (ETDEWEB)

    1994-07-01

    The LBL Operating and Assurance Program (OAP) is a management system and a set of requirements designed to maintain the level of performance necessary to achieve LBL`s programmatic and administrative objectives effectively and safely through the application of quality assurance and related conduct of operations and maintenance management principles. Implement an LBL management philosophy that supports and encourages continual improvement in performance and quality at the Laboratory. Provide an integrated approach to compliance with applicable regulatory requirements and DOE orders. The OAP is intended to meet the requirements of DOE Order 5700.6C, Quality Assurance. The Program also contains management system elements of DOE Orders 5480.19, Conduct of Operations Requirements for DOE Facilities; 5480.25, Safety of Accelerator Facilities; and 4330.4A, Maintenance Management Program, and is meant to integrate these elements into the overall LBL approach to Laboratory management. The requirements of this program apply to LBL employees and organizations, and to contractors and facility users as managed by their LBL sponsors. They are also applicable to external vendors and suppliers as specified in procurement documents and contracts.

  8. Lawrence Berkeley Laboratory Affirmative Action Program. Revised

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-06-01

    The Lawrence Berkeley Laboratory`s Affirmative Action Program (AAP) serves as a working document that describes current policies, practices, and results in the area of affirmative action. It represents the Laboratory`s framework for an affirmative approach to increasing the representation of people of color and women in segments of our work force where they have been underrepresented and taking action to increase the employment of persons with disabilities and special disabled and Vietnam era veterans. The AAP describes the hierarchy of responsibility for Laboratory affirmative action, the mechanisms that exist for full Laboratory participation in the AAP, the policies and procedures governing recruitment at all levels, the Laboratory`s plan for monitoring, reporting, and evaluating affirmative action progress, and a description of special affirmative action programs and plans the Laboratory has used and will use in its efforts to increase the representation and retention of groups historically underrepresented in our work force.

  9. RAWS II: A MULTIPLE REGRESSION ANALYSIS PROGRAM,

    Science.gov (United States)

    This memorandum gives instructions for the use and operation of a revised version of RAWS, a multiple regression analysis program. The program...of preprocessed data, the directed retention of variable, listing of the matrix of the normal equations and its inverse, and the bypassing of the regression analysis to provide the input variable statistics only. (Author)

  10. 78 FR 32161 - Oklahoma: Final Authorization of State Hazardous Waste Management Program Revision

    Science.gov (United States)

    2013-05-29

    ... Authorization of State Hazardous Waste Management Program Revision AGENCY: Environmental Protection Agency (EPA... waste management program. We authorized the following revisions: Oklahoma received authorization for... authorization of its program revision in accordance with 40 CFR 271.21. The Oklahoma Hazardous Waste Management...

  11. Revised experimental program on the nuclear ship 'Mutsu'

    International Nuclear Information System (INIS)

    Mori, Yuichi

    1985-01-01

    The experimental program on the nuclear ship ''Mutsu'' has been revised by the Government. And, the responsible organization for n. s. Mutsu was turned to Japan Atomic Energy Research Institute (JAERI) from Japan Nuclear-ship Development Agency. The revised, new experimental program is as follows. (1) Experimental navigation of n. s. Mutsu is made with the already loaded 1st reactor core for about one year. (2) The mooring port for n. s. Mutsu is in a minimum scale. (3) Upon termination of the experimental navigation, n. s. Mutsu is immediately decommissioned. (4) Power-up test and experimental navigation of n. s. Mutsu are made in fiscal 1989 to 1990. The policy of research and development with n. s. Mutsu and the works assigned to JAERI with n. s. Mutsu are described. (Mori, K.)

  12. Civilian radioactive waste management program plan. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-01

    This revision of the Civilian Radioactive Waste Management Program Plan describes the objectives of the Civilian Radioactive Waste management Program (Program) as prescribed by legislative mandate, and the technical achievements, schedule, and costs planned to complete these objectives. The Plan provides Program participants and stakeholders with an updated description of Program activities and milestones for fiscal years (FY) 1998 to 2003. It describes the steps the Program will undertake to provide a viability assessment of the Yucca Mountain site in 1998; prepare the Secretary of Energy`s site recommendation to the President in 2001, if the site is found to be suitable for development as a repository; and submit a license application to the Nuclear Regulatory Commission in 2002 for authorization to construct a repository. The Program`s ultimate challenge is to provide adequate assurance to society that an operating geologic repository at a specific site meets the required standards of safety. Chapter 1 describes the Program`s mission and vision, and summarizes the Program`s broad strategic objectives. Chapter 2 describes the Program`s approach to transform strategic objectives, strategies, and success measures to specific Program activities and milestones. Chapter 3 describes the activities and milestones currently projected by the Program for the next five years for the Yucca Mountain Site Characterization Project; the Waste Acceptance, Storage and Transportation Project; ad the Program Management Center. The appendices present information on the Nuclear Waste Policy Act of 1982, as amended, and the Energy Policy Act of 1992; the history of the Program; the Program`s organization chart; the Commission`s regulations, Disposal of High-Level Radioactive Wastes in geologic Repositories; and a glossary of terms.

  13. Nuclear Regulatory Commission Human Factors Program Plan. Revision 2

    International Nuclear Information System (INIS)

    1986-04-01

    This document is the Second Annual Revision to the NRC Human Factors Program Plan. The first edition was published in August 1983. Revision 1 was published in July of 1984. Purpose of the NRC Human Factors Program is to ensure that proper consideration is given to human factors in the design and operation of nuclear power plants. This document describes the plans of the Office of Nuclear Reactor Regulation to address high priority human factors concerns of importance to reactor safety in FY 1986 and FY 1987. Revision 2 of the plan incorporates recent Commission decisions and policies bearing on the human factors aspects of reactor safety regulation. With a few exceptions, the principal changes from prior editions reflect a shift from developing new requirements to staff evaluation of industry progress in resolving human factors issues. The plan addresses seven major program elements: (1) Training, (2) Licensing Examinations, (3) Procedures, (4) Man-Machine Interface, (5) Staffing and Qualifications, (6) Management and Organization, and (7) Human Performance

  14. RCBI-II: The Second Revision of the Revised Cyber Bullying Inventory

    Science.gov (United States)

    Topcu, Çigdem; Erdur-Baker, Özgür

    2018-01-01

    The aim of this study is to update the Turkish version of the Revised Cyber Bullying Inventory (RCBI) and eliminate specific technology names. Validity and reliability tests were carried out with 1,803 high school students. The updated version of the RCBI yields valid and reliable scores measuring cyberbullying and victimization.

  15. 76 FR 45253 - Public Water Supply Supervision Program; Program Revision for the State of Alaska

    Science.gov (United States)

    2011-07-28

    ... ENVIRONMENTAL PROTECTION AGENCY [FRL-9444-8] Public Water Supply Supervision Program; Program... Water Supply Supervision Primacy Program. Alaska has adopted regulations analogous to the EPA's Ground Water Rule. The EPA has determined that these revisions are no less stringent than the corresponding...

  16. Revised Severe Accident Research Program plan, FY 1990--1992

    International Nuclear Information System (INIS)

    1989-08-01

    For the past 10 years, since the Three Mile Island accident, the NRC has sponsored an active research program on light-water-reactor severe accidents as part of a multi-faceted approach to reactor safety. This report describes the revised Severe Accident Research Program (SARP) and how the revisions are designed to provide confirmatory information and technical support to the NRC staff in implementing the staff's Integration Plan for Closure of Severe Accident Issues as described in SECY-88-147. The revised SARP addresses both the near-term research directed at providing a technical basis upon which decisions on important containment performance issues can be made and the long-term research needed to confirm and refine our understanding of severe accidents. In developing this plan, the staff recognized that the overall goal is to reduce the uncertainties in the source term sufficiently to enable the staff to make regulatory decisions on severe accident issues. However, the staff also recognized that for some issues it may not be practical to attempt to further reduce uncertainties, and some regulatory decisions or conclusions will have to be made with full awareness of existing uncertainties. 2 figs., 1 tab

  17. SEISRISK II; a computer program for seismic hazard estimation

    Science.gov (United States)

    Bender, Bernice; Perkins, D.M.

    1982-01-01

    The computer program SEISRISK II calculates probabilistic ground motion values for use in seismic hazard mapping. SEISRISK II employs a model that allows earthquakes to occur as points within source zones and as finite-length ruptures along faults. It assumes that earthquake occurrences have a Poisson distribution, that occurrence rates remain constant during the time period considered, that ground motion resulting from an earthquake is a known function of magnitude and distance, that seismically homogeneous source zones are defined, that fault locations are known, that fault rupture lengths depend on magnitude, and that earthquake rates as a function of magnitude are specified for each source. SEISRISK II calculates for each site on a grid of sites the level of ground motion that has a specified probability of being exceeded during a given time period. The program was designed to process a large (essentially unlimited) number of sites and sources efficiently and has been used to produce regional and national maps of seismic hazard.}t is a substantial revision of an earlier program SEISRISK I, which has never been documented. SEISRISK II runs considerably [aster and gives more accurate results than the earlier program and in addition includes rupture length and acceleration variability which were not contained in the original version. We describe the model and how it is implemented in the computer program and provide a flowchart and listing of the code.

  18. 75 FR 52976 - Issuance of Revised Users' Manual for Commission Mediation Program for Investigations Under...

    Science.gov (United States)

    2010-08-30

    ... INTERNATIONAL TRADE COMMISSION Issuance of Revised Users' Manual for Commission Mediation Program... 65615 (Nov. 8, 2008). The Commission has determined to issue a revised Users' Manual for its program for the mediation of investigations under section 337 of the Tariff Act of 1930. The revised Users' Manual...

  19. Civilian radioactive waste management program plan. Revision 2

    International Nuclear Information System (INIS)

    1998-07-01

    This revision of the Civilian Radioactive Waste Management Program Plan describes the objectives of the Civilian Radioactive Waste management Program (Program) as prescribed by legislative mandate, and the technical achievements, schedule, and costs planned to complete these objectives. The Plan provides Program participants and stakeholders with an updated description of Program activities and milestones for fiscal years (FY) 1998 to 2003. It describes the steps the Program will undertake to provide a viability assessment of the Yucca Mountain site in 1998; prepare the Secretary of Energy's site recommendation to the President in 2001, if the site is found to be suitable for development as a repository; and submit a license application to the Nuclear Regulatory Commission in 2002 for authorization to construct a repository. The Program's ultimate challenge is to provide adequate assurance to society that an operating geologic repository at a specific site meets the required standards of safety. Chapter 1 describes the Program's mission and vision, and summarizes the Program's broad strategic objectives. Chapter 2 describes the Program's approach to transform strategic objectives, strategies, and success measures to specific Program activities and milestones. Chapter 3 describes the activities and milestones currently projected by the Program for the next five years for the Yucca Mountain Site Characterization Project; the Waste Acceptance, Storage and Transportation Project; ad the Program Management Center. The appendices present information on the Nuclear Waste Policy Act of 1982, as amended, and the Energy Policy Act of 1992; the history of the Program; the Program's organization chart; the Commission's regulations, Disposal of High-Level Radioactive Wastes in geologic Repositories; and a glossary of terms

  20. 78 FR 25678 - Georgia: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2013-05-02

    ...: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... of changes to its hazardous waste program under the Resource Conservation and Recovery Act (RCRA... Gwendolyn Gleaton, Permits and State Programs Section, RCRA Programs and Materials Management Branch, RCRA...

  1. Revised

    DEFF Research Database (Denmark)

    Johannsen, Vivian Kvist; Nord-Larsen, Thomas; Riis-Nielsen, Torben

    This report is a revised analysis of the Danish data on CO2 emissions from forest, afforestation and deforestation for the period 1990 - 2008 and a prognosis for the period until 2020. Revision have included measurements from 2009 in the estimations. The report is funded by the Ministry of Climate...

  2. ERD UMTRA Project quality assurance program plan, Revision 7

    International Nuclear Information System (INIS)

    1995-09-01

    This document is the revised Quality Assurance Program Plan (QAPP) dated September, 1995 for the Environmental Restoration Division (ERD) Uranium Mill Tailings Remedial Action Project (UMTRA). Quality Assurance requirements for the ERD UMTRA Project are based on the criteria outlined in DOE Order 5700.6C or applicable sections of 10 CFR 830.120. QA requirements contained in this QAPP shall apply to all personnel, processes, and activities, including planning, scheduling, and cost control, performed by the ERD UMTRA Project and its contractors

  3. PRELIMINARY REVISIONS OF SOME GENERA OF MALAYSIAN PAPILIONACEAE II

    Directory of Open Access Journals (Sweden)

    MS van Meeuwen

    2014-01-01

    Full Text Available The revisions or notes have been prepared by Miss M. S. van Meeuwen, except for those of Pseudarthria and Sophora by C. G. G. J. van Steenis, and Tephrosia by J. Stemmerik. In Alysicarpus 4 species are distinguished in Malaysia; a key, synonymy, and discussion are given.Lourea Desv., being a homonym, has, according to Dr. Bakhuizen van den Brink, to be replaced by Christia; a key and discussion is given of 4 Malaysian species; 5 new combinations are proposed. Under Desmodium the variability of D. heterocarpon (L. DC. and its full synonymy are discussed; one new variety is proposed; an enumeration of specimens of both varieties is given. D. ormooarpoides DC. and D. zonatum Miq. are two sharply distinct species which have been confused in the past; a key, synonyms, discussion, and enumeration of specimens ;; j are provided. The discrimination of D. sequax Wall, and D. viegaphyllum Zoll. is discussed and their synonymy given; specimens have been enumerated. Distribution is given of D. scorpiurus (Sw. Desv. and D. tor-tuosum (Sw.   DC. Psoraleai is revised for Malaysia where 4 species are recorded and keyed out; a fifth species must remain dubious, as the type could not be traced in the Paris Herbarium. Of Pseudarthria only one species occurs in Malaysia; its synonymy and distribution is given.Sophora longipes Merr.; an endemic species from the Philippines, is recorded for Timor. Of Tephro&ia maculata M. & P., from Papua, the synonymy is given and specimens enumerated; T. brachystachys Laut. & K. Seh. is reduced. Notes and distribution are given of T. zollingeri Backer. For T. mollie . Val., a later homonym, the new name T. papuana is proposed.

  4. Functional design criteria for project W-252, phase II liquid effluent treatment and disposal. Revision 2

    International Nuclear Information System (INIS)

    Hatch, C.E.

    1995-05-01

    This document is the Functional Design Criteria for Project W-252. Project W-252 provides the scope to provide BAT/AKART (best available technology...) to 200 Liquid Effluent Phase II streams (B-Plant). This revision (Rev. 2) incorporates a major descoping of the project. The descoping was done to reflect a combination of budget cutting measures allowed by a less stringent regulatory posture toward the Phase II streams

  5. Calculus of Elementary Functions, Part II. Teacher's Commentary. Revised Edition.

    Science.gov (United States)

    Herriot, Sarah T.; And Others

    This course is intended for students who have a thorough knowledge of college preparatory mathematics, including algebra, axiomatic geometry, trigonometry, and analytic geometry. This teacher's guide is for Part II of the course. It is designed to follow Part I of the text. The guide contains background information, suggested instructional…

  6. Calculus of Elementary Functions, Part II. Student Text. Revised Edition.

    Science.gov (United States)

    Herriot, Sarah T.; And Others

    This course is intended for students who have a thorough knowledge of college preparatory mathematics, including algebra, axiomatic geometry, trigonometry, and analytic geometry. This text, Part II, contains material designed to follow Part I. Chapters included in this text are: (6) Derivatives of Exponential and Related Functions; (7) Area and…

  7. Revised criteria for PCOS in WHO Group II anovulatory infertility – a revival of hypothalamic amenorrhoea?

    DEFF Research Database (Denmark)

    Lauritsen, Mette Petri; Pinborg, Anja; Loft, Anne

    2015-01-01

    OBJECTIVE: To evaluate revised criteria for polycystic ovarian morphology (PCOM) in the diagnosis of polycystic ovary syndrome (PCOS) in anovulatory infertility. DESIGN: Prospective cohort study. PATIENTS: WHO Group II anovulatory infertile women (n = 75). MEASUREMENTS: Clinical, sonographic......, but according to AMH levels, the ovaries remain multifollicular. PERSPECTIVES: A better distinction between hypothalamic amenorrhoea and PCOS could improve treatment strategies for anovulatory infertility....

  8. Application Programming in AWIPS II

    Science.gov (United States)

    Smit, Matt; McGrath, Kevin; Burks, Jason; Carcione, Brian

    2012-01-01

    Since its inception almost 8 years ago, NASA's Short-term Prediction Research and Transition (SPoRT) Center has integrated NASA data into the National Weather Service's decision support system (DSS) the Advanced Weather Interactive Processing System (AWIPS). SPoRT has, in some instances, had to shape and transform data sets into various formats and manipulate configurations to visualize them in AWIPS. With the advent of the next generation of DSS, AWIPS II, developers will be able to develop their own plugins to handle any type of data. Raytheon is developing AWIPS II to be a more extensible package written mainly in Java, and built around a Service Oriented Architecture. A plugin architecture will allow users to install their own code modules, and (if all the rules have been properly followed) they will work hand-in-hand with AWIPS II as if it were originally built in. Users can bring in new datasets with existing plugins, tweak plugins to handle a nuance or desired new functionality, or create an entirely new visualization layout for a new dataset. SPoRT is developing plugins to ensure its existing NASA data will be ready for AWIPS II when it is delivered, and to prepare for the future of new instruments on upcoming satellites.

  9. Hanford Site Groundwater Protection Management Program: Revision 1

    International Nuclear Information System (INIS)

    1993-11-01

    Groundwater protection is a national priority that is promulgated in a variety of environmental regulations at local, state, and federal levels. To effectively coordinate and ensure compliance with applicable regulations, the US Department of Energy has issued DOE Order 5400.1 (now under revision) that requires all US Department of Energy facilities to prepare separate groundwater protection program descriptions and plans. This document describes the Groundwater Protection Management Program for the Hanford Site located in the state of Washington. DOE Order 5400.1 specifies that the Groundwater Protection Management Program cover the following general topical areas: (1) documentation of the groundwater regime, (2) design and implementation of a groundwater monitoring program to support resource management and comply with applicable laws and regulations, (3) a management program for groundwater protection and remediation, (4) a summary and identification of areas that may be contaminated with hazardous waste, (5) strategies for controlling these sources, (6) a remedial action program, and (7) decontamination and decommissioning and related remedial action requirements. Many of the above elements are covered by existing programs at the Hanford Site; thus, one of the primary purposes of this document is to provide a framework for coordination of existing groundwater protection activities. Additionally, it describes how information needs are identified and can be incorporated into existing or proposed new programs. The Groundwater Protection Management Program provides the general scope, philosophy, and strategies for groundwater protection/management at the Hanford Site. Subtier documents provide the detailed plans for implementing groundwater-related activities and programs. Related schedule and budget information are provided in the 5-year plan for environmental restoration and waste management at the Hanford Site

  10. 77 FR 24148 - Revision to the Hawaii State Implementation Plan, Minor New Source Review Program

    Science.gov (United States)

    2012-04-23

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 52 [EPA-R09-OAR-2012-0213; FRL-9661-6] Revision to the Hawaii State Implementation Plan, Minor New Source Review Program AGENCY: Environmental Protection Agency... final action to approve revisions to the Hawaii State Implementation Plan (SIP). These revisions would...

  11. 75 FR 60398 - California: Proposed Authorization of State Hazardous Waste Management Program Revision

    Science.gov (United States)

    2010-09-30

    ...: Proposed Authorization of State Hazardous Waste Management Program Revision AGENCY: Environmental... its hazardous waste management program by November 1, 2010. ADDRESSES: Submit your comments... waste management program. EPA continues to have independent enforcement authority under RCRA sections...

  12. 76 FR 62303 - California: Final Authorization of State Hazardous Waste Management Program Revision

    Science.gov (United States)

    2011-10-07

    ... State Hazardous Waste Management Program Revision AGENCY: Environmental Protection Agency (EPA). ACTION... the revisions to California's hazardous waste management program shall be effective at 1 p.m. on... implement the RCRA hazardous waste management program. EPA granted authorization for changes to California's...

  13. 75 FR 918 - Oregon: Final Authorization of State Hazardous Waste Management Program Revision

    Science.gov (United States)

    2010-01-07

    ... Authorization of State Hazardous Waste Management Program Revision AGENCY: Environmental Protection Agency (EPA... hazardous waste management program under the Resource Conservation and Recovery Act, as amended (RCRA). On... has decided that the revisions to the Oregon hazardous waste management program satisfy all of the...

  14. 75 FR 50932 - Massachusetts: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2010-08-18

    ...: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental...-1990. FOR FURTHER INFORMATION CONTACT: Robin Biscaia, RCRA Waste Management Section, Office of Site... final [[Page 50933

  15. Seismic safety margin research program. Program plan, Revision I

    International Nuclear Information System (INIS)

    Smith, P.D.; Tokarz, F.J.; Bernreuter, D.L.; Cummings, G.E.; Chou, C.K.; Vagliente, V.N.

    1978-01-01

    The overall objective of the SSMRP is to develop mathematical models that realistically predict the probability of radioactive releases from seismically induced events in nuclear power plants. These models will be used for four purposes: (1) To perform sensitivity studies to determine the weak links in seismic methodology. The weak links will then be improved by research and development. (2) To estimate the probability of release for a plant. It is believed that the major difficulty in the program will be to obtain acceptably small confidence limits on the probability of release. (3) To estimate the conservatisms in the Standard Review Plan (SRP) seismic design methodology. This will be done by comparing the results of the SRP methodology and the methodology resulting from the research and development in (1). (4) To develop an improved seismic design methodology based on probability. The Phase I objective proposed in this report is to develop mathematical models which will accomplish the purposes No. 1 and No. 2 with simplified assumptions such as linear elastic analysis, limited assessment on component fragility (considering only accident sequences leading to core melt), and simplified safety system

  16. 78 FR 70255 - West Virginia: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2013-11-25

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 271 [EPA-R03-RCRA-2013-0571; FRL-9903-07-Region 3] West Virginia: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY... final authorization of revisions to its hazardous waste program under the Resource Conservation and...

  17. 76 FR 18927 - Oklahoma: Final Authorization of State Hazardous Waste Management Program Revision

    Science.gov (United States)

    2011-04-06

    ...: Final Authorization of State Hazardous Waste Management Program Revision AGENCY: Environmental... hazardous waste management program. We authorized the following revisions: Oklahoma received authorization... accordance with 40 CFR 271.21. The Oklahoma Hazardous Waste Management Act (``OHWMA'') provides the ODEQ with...

  18. 77 FR 10373 - Greenhouse Gas Reporting Program: Electronics Manufacturing: Revisions to Heat Transfer Fluid...

    Science.gov (United States)

    2012-02-22

    ... Greenhouse Gas Reporting Program: Electronics Manufacturing: Revisions to Heat Transfer Fluid Provisions... technical revisions to the electronics manufacturing source category of the Greenhouse Gas Reporting Rule... final rule will also be available through the WWW on the EPA's Greenhouse Gas Reporting Program Web site...

  19. 78 FR 54200 - Virginia: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2013-09-03

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 271 [EPA-R03-RCRA-2012-0294; FRL-9900-37-Region3] Virginia: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... of revisions to its hazardous waste program under the Resource Conservation and Recovery Act (RCRA...

  20. 77 FR 65351 - Missouri: Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2012-10-26

    ...: Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental Protection Agency (EPA... Jackson-Johnson, Environmental Protection Agency, Waste Enforcement & Materials Management Branch, 11201... its hazardous waste program under the Resource Conservation and Recovery Act (RCRA). EPA proposes to...

  1. US Nuclear Regulatory Commission Human Factors Program Plan. Revision 1

    International Nuclear Information System (INIS)

    1984-09-01

    The purpose of the NRC Human Factors Program Plan (NUREG-0985) is to ensure that proper consideration is given to human factors in the design, operation, and maintenance of nuclear facilities. This revised plan addresses nuclear power plants (NPPs) and describes (1) the technical assistance and research activities planned to provide the technical bases for the resolution of the remaining human factors related tasks described in NUREG-0660, THE NRC Action Plan developed as a result of the TMI-2 Accident, and NUREG-0737, Clarification of TMI Action Plan Requirements; (2) the additional human factors efforts identified during implementation of the Action Plan that should receive NRC attention; (3) conduct of developmental activities specified in NUREG-0985 during FY-83; and (4) the impact of Section 306 of the Nuclear Waste Policy Act of 1982, PL 97-425. The plan represents a systematic and comprehensive approach for addressing human factors concerns important to NPP safety in the FY-84 through FY-86 time frame

  2. 76 FR 69734 - Public Water System Supervision Program Revision for the State of New Mexico

    Science.gov (United States)

    2011-11-09

    ... Water System Supervision Program. New Mexico has adopted the Lead and Copper Rule Short Term Revisions... water. EPA has determined that this rule revision submitted by New Mexico is no less stringent than the... the following offices: New Mexico Environment Department, Drinking Water Bureau, 525 Camino De Los...

  3. 200 area liquid effluent facility quality assurance program plan. Revision 1

    International Nuclear Information System (INIS)

    Sullivan, N.J.

    1995-01-01

    Direct revision of Supporting Document WHC-SD-LEF-QAPP-001, Rev. 0. 200 Area Liquid Effluent Facilities Quality Assurance Program Plan. Incorporates changes to references in tables. Revises test to incorporate WHC-SD-LEF-CSCM-001, Computer Software Configuration Management Plan for 200 East/West Liquid Effluent Facilities

  4. 76 FR 6594 - Florida: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2011-02-07

    ...: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... of the changes to its hazardous waste program under the Resource Conservation and Recovery Act (RCRA... and State Programs Section, RCRA Programs and Materials Management Branch, RCRA Division, U.S...

  5. 77 FR 60963 - Tennessee: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2012-10-05

    ...: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... of the changes to its hazardous waste program under the Resource Conservation and Recovery Act (RCRA... Johnson, Permits and State Programs Section, RCRA Programs and Materials Management Branch, RCRA Division...

  6. 78 FR 59661 - Revision of a Currently Approved Information Collection for the State Energy Program

    Science.gov (United States)

    2013-09-27

    ... the final version of the information collection request. The Department of Energy (DOE) invites public... information collection requests a revision and three-year extension of its State Energy Program, OMB Control...

  7. German NDE within PISC-II program

    International Nuclear Information System (INIS)

    Deuster, G.; Schmuelling, W.

    1987-01-01

    Within PISC-I, which was finished at the end of the seventies, three uncladded 200 mm thick plates were available. In this program ten European countries were participating. The test specimens came out of the American HSST-program. A series of testing according to the ASME-procedure were performed and in addition several alternative techniques. The manufacturing defects dominated but were unrealistic large. There was a lack of small cracklike defects. The PISC-II program was initiated in the early eighties with participation of twelve European countries and in addition USA, Japan and Canada. A lot of realistic service induced cracklike defects were available especially what concerned their position and size. (orig.)

  8. 76 FR 6594 - North Carolina: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2011-02-07

    ... Carolina: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... authorization of the changes to its hazardous waste program under the Resource Conservation and Recovery Act... Section, RCRA Programs and Materials Management Branch, RCRA Division, U.S. Environmental Protection...

  9. 77 FR 61326 - Indiana: Final Authorization of State Hazardous Waste Management Program Revision

    Science.gov (United States)

    2012-10-09

    ...: Final Authorization of State Hazardous Waste Management Program Revision AGENCY: Environmental... RCRA hazardous waste management program. We granted authorization for changes to their program on... 202. Hazardous Waste Management July 30, 2003; 68 329 IAC 3.1-6-2(16); System; Identification and FR...

  10. 76 FR 37021 - Louisiana: Final Authorization of State Hazardous Waste Management Program Revision

    Science.gov (United States)

    2011-06-24

    ...: Final Authorization of State Hazardous Waste Management Program Revision AGENCY: Environmental... implement its base Hazardous Waste Management Program. We granted authorization for changes to their program... opportunity to apply for final authorization to operate all aspects of their hazardous waste management...

  11. 77 FR 60919 - Tennessee: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2012-10-05

    ...: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental..., Division of Solid Waste Management, 5th Floor, L & C Tower, 401 Church Street, Nashville, Tennessee 37243... RCRA hazardous waste management program. We granted authorization for changes to Tennessee's program on...

  12. 22 CFR 518.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-04-01

    ... GRANTS AND AGREEMENTS WITH INSTITUTIONS OF HIGHER EDUCATION, HOSPITALS, AND OTHER NON-PROFIT ORGANIZATIONS Post-Award Requirements Financial and Program Management § 518.25 Revision of budget and program plans. (a) The budget plan is the financial expression of the project or program as approved during the...

  13. 34 CFR 74.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-07-01

    ... WITH INSTITUTIONS OF HIGHER EDUCATION, HOSPITALS, AND OTHER NON-PROFIT ORGANIZATIONS Post-Award Requirements Financial and Program Management § 74.25 Revision of budget and program plans. (a) The budget plan is the financial expression of the project or program as approved during the award process. It may...

  14. 77 FR 15966 - Ohio: Final Authorization of State Hazardous Waste Management Program Revision

    Science.gov (United States)

    2012-03-19

    ... Hazardous Waste Management Program Revision AGENCY: Environmental Protection Agency (EPA). ACTION: Final..., 1989 (54 FR 27170) to implement the RCRA hazardous waste management program. We granted authorization... Combustors; Final Rule, Checklist 198, February 14, 2002 (67 FR 6968); Hazardous Waste Management System...

  15. 78 FR 15299 - New York: Final Authorization of State Hazardous Waste Management Program Revision

    Science.gov (United States)

    2013-03-11

    ...: Final Authorization of State Hazardous Waste Management Program Revision AGENCY: Environmental... Waste program as addressed by the federal used oil management regulations that were published on..., New York Codes, Rules and Regulations (6 NYCRR), Volume A-2A, Hazardous Waste Management System...

  16. 76 FR 6561 - North Carolina: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2011-02-07

    ... Carolina: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... December 31, 1984 (49 FR 48694) to implement its base hazardous waste management program. EPA granted... XV are from the North Carolina Hazardous Waste Management Rules 15A NCAC 13A, effective April 23...

  17. 76 FR 56708 - Ohio: Final Authorization of State Hazardous Waste Management Program Revision

    Science.gov (United States)

    2011-09-14

    ... Hazardous Waste Management Program Revision AGENCY: Environmental Protection Agency (EPA). ACTION: Proposed..., 1989 (54 FR 27170) to implement the RCRA hazardous waste management program. We granted authorization... December 7, 2004. Waste Combustors; Final Rule; Checklist 198. Hazardous Waste Management March 13, 2002...

  18. 77 FR 13200 - Texas: Final Authorization of State Hazardous Waste Management Program Revision

    Science.gov (United States)

    2012-03-06

    ... Authorization of State Hazardous Waste Management Program Revision AGENCY: Environmental Protection Agency (EPA... December 26, 1984 (49 FR 48300), to implement its Base Hazardous Waste Management Program. This... Waste 53478, September Annotated Sections Management facilities. 8, 2005. 5.103 and 5.105 (Checklist 210...

  19. 36 CFR 1210.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-07-01

    ... may, at its option, restrict the transfer of funds among direct cost categories or programs, functions... or the objective of the project or program (even if there is no associated budget revision requiring... funds allotted for training allowances (direct payment to trainees) to other categories of expense. (8...

  20. 78 FR 15338 - New York: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2013-03-11

    ... authorization of changes to its hazardous waste program under the Solid Waste Disposal Act, as amended, commonly... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 271 [EPA-R02-RCRA-2013-0144; FRL-9693-3] New York: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental...

  1. 75 FR 81187 - South Dakota: Final Authorization of State Hazardous Waste Management Program Revision

    Science.gov (United States)

    2010-12-27

    ...: Final Authorization of State Hazardous Waste Management Program Revision AGENCY: Environmental Protection Agency (EPA). ACTION: Proposed Rule. SUMMARY: The Solid Waste Disposal Act, as amended, commonly... Agency (EPA) to authorize states to operate their hazardous waste management programs in lieu of the...

  2. 77 FR 47797 - Arkansas: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2012-08-10

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 271 [EPA-R06-RCRA-2010-0307; FRL-9713-2] Arkansas: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... authorization of the changes to its hazardous waste program under the Resource Conservation and Recovery Act...

  3. 76 FR 19004 - Oklahoma: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2011-04-06

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 271 [EPA-R06-RCRA-2010-0307; FRL-9290-9] Oklahoma: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... authorization of the changes to its hazardous waste program under the Resource Conservation and Recovery Act...

  4. 78 FR 32223 - Oklahoma: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2013-05-29

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 271 [EPA-R06-RCRA-2012-0821; 9817-5] Oklahoma: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental Protection Agency (EPA... changes to its hazardous waste program under the Resource Conservation and Recovery Act (RCRA). EPA...

  5. 77 FR 38566 - Louisiana: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2012-06-28

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 271 [EPA--R06-RCRA-2012-0367; FRL-9692-6] Louisiana: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... authorization of the changes to its hazardous waste program under the Resource Conservation and Recovery Act...

  6. 78 FR 25579 - Georgia: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2013-05-02

    ...: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... adopted these requirements by reference at Georgia Hazardous Waste Management Rule 391-3-11-.07(1), EPA... authorization of changes to its hazardous waste program under the Resource Conservation and Recovery Act (RCRA...

  7. 76 FR 37048 - Louisiana; Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2011-06-24

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 271 [EPA-R06-RCRA-2010-0307; FRL-9323-8] Louisiana; Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... authorization of the changes to its hazardous waste program under the Resource Conservation and Recovery Act...

  8. 77 FR 15343 - Oklahoma: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2012-03-15

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 271 [EPA-R06-RCRA-2012-0054; FRL-9647-8] Oklahoma: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... authorization of the changes to its hazardous waste program under the Resource Conservation and Recovery Act...

  9. 20 CFR 435.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-04-01

    ... GRANTS AND AGREEMENTS WITH INSTITUTIONS OF HIGHER EDUCATION, HOSPITALS, OTHER NON-PROFIT ORGANIZATIONS, AND COMMERCIAL ORGANIZATIONS Post-Award Requirements Financial and Program Management § 435.25 Revision of budget and program plans. (a) The budget plan is the financial expression of the project or...

  10. 38 CFR 49.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-07-01

    ... (CONTINUED) UNIFORM ADMINISTRATIVE REQUIREMENTS FOR GRANTS AND AGREEMENTS WITH INSTITUTIONS OF HIGHER EDUCATION, HOSPITALS, AND OTHER NON-PROFIT ORGANIZATIONS Post-Award Requirements Financial and Program Management § 49.25 Revision of budget and program plans. (a) The budget plan is the financial expression of...

  11. 22 CFR 145.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-04-01

    ... Section 145.25 Foreign Relations DEPARTMENT OF STATE CIVIL RIGHTS GRANTS AND AGREEMENTS WITH INSTITUTIONS OF HIGHER EDUCATION, HOSPITALS, AND OTHER NON-PROFIT ORGANIZATIONS Post-Award Requirements Financial and Program Management § 145.25 Revision of budget and program plans. (a) The budget plan is the...

  12. 28 CFR 70.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-07-01

    ... REQUIREMENTS FOR GRANTS AND AGREEMENTS (INCLUDING SUBAWARDS) WITH INSTITUTIONS OF HIGHER EDUCATION, HOSPITALS AND OTHER NON-PROFIT ORGANIZATIONS Post-Award Requirements Financial and Program Management § 70.25 Revision of budget and program plans. (a) The budget plan is the financial expression of the project or...

  13. 45 CFR 2543.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-10-01

    ... AND COMMUNITY SERVICE GRANTS AND AGREEMENTS WITH INSTITUTIONS OF HIGHER EDUCATION, HOSPITALS, AND OTHER NON-PROFIT ORGANIZATIONS Post-Award Requirements Financial and Program Management § 2543.25 Revision of budget and program plans. (a) The budget plan is the financial expression of the project or...

  14. 40 CFR 30.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-07-01

    ... FEDERAL ASSISTANCE UNIFORM ADMINISTRATIVE REQUIREMENTS FOR GRANTS AND AGREEMENTS WITH INSTITUTIONS OF HIGHER EDUCATION, HOSPITALS, AND OTHER NON-PROFIT ORGANIZATIONS Post-Award Requirements Financial and Program Management § 30.25 Revision of budget and program plans. (a) The budget plan is the financial...

  15. 45 CFR 74.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-10-01

    ... ADMINISTRATIVE REQUIREMENTS FOR AWARDS AND SUBAWARDS TO INSTITUTIONS OF HIGHER EDUCATION, HOSPITALS, OTHER NONPROFIT ORGANIZATIONS, AND COMMERCIAL ORGANIZATIONS Post-Award Requirements Financial and Program Management § 74.25 Revision of budget and program plans. (a) The budget plan is the financial expression of...

  16. 15 CFR 14.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-01-01

    ... ADMINISTRATIVE REQUIREMENTS FOR GRANTS AND AGREEMENTS WITH INSTITUTIONS OF HIGHER EDUCATION, HOSPITALS, OTHER NON-PROFIT, AND COMMERCIAL ORGANIZATIONS Post-Award Requirements Financial and Program Management § 14.25 Revision of budget and program plans. (a) The budget plan is the financial expression of the project or...

  17. 76 FR 1431 - Public Water System Supervision Program Revision for the State of New Mexico

    Science.gov (United States)

    2011-01-10

    ... Public Water System Supervision Program. New Mexico has adopted the Ground Water Rule (GWR), the Long... the following offices: New Mexico Environment Department, Drinking Water Bureau, 525 Camino De Los... of New Mexico proposes to revise its approved Public Water System Supervision Primacy Program. This...

  18. 76 FR 6564 - Florida: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2011-02-07

    ... hazardous pharmaceutical waste to the list of wastes that may be managed under the Universal Waste rule...: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... authorization of the changes to its hazardous waste program under the Resource Conservation and Recovery Act...

  19. 76 FR 60675 - Revision of the Commission's Program Carriage Rules

    Science.gov (United States)

    2011-09-29

    ... carriage of video programming vendors by multichannel video programming distributors (``MVPDs''), known as... and diversity in the video programming and video distribution markets. In this document, the FCC seeks... information is contained in contained in sections 4(i), 303(r), and 616 of the Communications Act of 1934, as...

  20. 77 FR 24301 - Revision of the Commission's Program Access Rules

    Science.gov (United States)

    2012-04-23

    ... afforded to multichannel video programming distributors by the program access rules--the prohibition on exclusive contracts involving satellite- delivered, cable-affiliated programming. The current exclusive... sections 4(i), 303(r), 616, and 628 of the Communications Act of 1934, as amended. Total Annual Burden: 43...

  1. 77 FR 468 - Revision of the Commission's Program Carriage Rules

    Science.gov (United States)

    2012-01-05

    ... the following methods: Federal eRulemaking Portal: http://www.regulations.gov . Follow the... business hours in the FCC Reference Center, Portals II, 445 12th Street SW., Room CY-A257, Washington, DC... (``NCTA''), Media Access Project, and Public Knowledge filed a joint request to extend the reply comment...

  2. Evaluation of revised national tuberculosis control program, district Kangra, Himachal Pradesh, India, 2007

    Directory of Open Access Journals (Sweden)

    Surender Nikhil Gupta

    2011-01-01

    Full Text Available Background: The present evaluation study has been conducted with the following objectives: (i To assess the treatment outcomes of revised national tuberculosis control program (RNTCP in five microscopic centers of Kangra district under five tuberculosis units and (ii To identify gaps and underlying contributing factors. Based upon the findings of (i and (ii we suggest appropriate measures to narrow down the existing gaps. Materials and Methods: We identified and interviewed health personnel involved, reviewed the documents and records pertaining to evaluation plan/guidelines, training records and reports generated by five tuberculosis units. We assessed the inputs, processes and outputs of the program across five tuberculosis units. We calculated the proportion of staff of various categories trained and internal quality control (case detection; availability of drugs, directly observed treatment short course (DOTS providers, and supervision (case management and information, education and communication (IEC, and funds distribution. (logic model. Result: Around 60%-88% of staffs of various categories trained with overall 25% gap of supervisory visits. In tuberculosis unit (TU Nurpur, the discordant slides while cross-checking were 8% and 25%. The total proportions of sputum positivity are 5.1%; the highest in Kangra, i.e., 2.3% (national norms of 10-15%.. There was no full cross-checking of the positive slides despite internal quality in place. Increased numbers of the extra pulmonary tuberculosis cases (EPTB are present in all TUs, as high as 61% in TU Dharamshala (Normal range 15%-20%. A gap of 20% DOT center exists-the least in (58% in TU Nurpur. The awareness level in the TU Dehra is minimum (51%; more so in females and rural set up. Conclusion: RNTCP has successfully achieved all its targets in all the five TUs of Kangra District as per national norms despite several gaps. We recommend (i filling of vacancies of medics and paramedics with

  3. Evaluation of revised national tuberculosis control program, district Kangra, Himachal Pradesh, India, 2007.

    Science.gov (United States)

    Gupta, Surender Nikhil; Gupta, Naveen

    2011-07-01

    THE PRESENT EVALUATION STUDY HAS BEEN CONDUCTED WITH THE FOLLOWING OBJECTIVES: (i) To assess the treatment outcomes of revised national tuberculosis control program (RNTCP) in five microscopic centers of Kangra district under five tuberculosis units and (ii) To identify gaps and underlying contributing factors. Based upon the findings of (i) and (ii) we suggest appropriate measures to narrow down the existing gaps. We identified and interviewed health personnel involved, reviewed the documents and records pertaining to evaluation plan/guidelines, training records and reports generated by five tuberculosis units. We assessed the inputs, processes and outputs of the program across five tuberculosis units. We calculated the proportion of staff of various categories trained and internal quality control (case detection); availability of drugs, directly observed treatment short course (DOTS) providers, and supervision (case management) and information, education and communication (IEC), and funds distribution. (logic model). Around 60%-88% of staffs of various categories trained with overall 25% gap of supervisory visits. In tuberculosis unit (TU) Nurpur, the discordant slides while cross-checking were 8% and 25%. The total proportions of sputum positivity are 5.1%; the highest in Kangra, i.e., 2.3% (national norms of 10-15%.). There was no full cross-checking of the positive slides despite internal quality in place. Increased numbers of the extra pulmonary tuberculosis cases (EPTB) are present in all TUs, as high as 61% in TU Dharamshala (Normal range 15%-20%). A gap of 20% DOT center exists-the least in (58%) in TU Nurpur. The awareness level in the TU Dehra is minimum (51%); more so in females and rural set up. RNTCP has successfully achieved all its targets in all the five TUs of Kangra District as per national norms despite several gaps. We recommend (i) filling of vacancies of medics and paramedics with reorientation trainings/refresher courses; (ii) conduction of

  4. Quality Assurance Program Plan for FFTF effluent controls. Revision 1

    International Nuclear Information System (INIS)

    Seamans, J.A.

    1995-01-01

    This Quality Assurance Program Plan is specific to environmental related activities within the FFTF Property Protected Area. The activities include effluent monitoring and Low Level Waste Certification

  5. Evaluation of the revised training program for senior control room staff: science fundamentals and equipment principles

    International Nuclear Information System (INIS)

    Jervis, R.E.; Evans, G.J.

    1996-10-01

    Canadian nuclear utilities have formed an Inter-Utility Working Group to revise their program for training nuclear generating station senior control room staff, namely Control Room Operators and Shift Supervisors, in Science Fundamentals and Equipment Principles. This report documents the findings of an external review of this revision process, addressing, amongst other topics, the process of revision undertaken by the Working Group, their outline of topics to be included, and, the pertinence and comprehensiveness of the detailed training objectives identified for two of the courses. The approach to revising the program being followed by the Working Group appears to be reasonable insomuch that some training needs have been identified and used to construct detailed sets of training objectives. However, as assessed by the consultants without full documentation being available, some important steps appear to have been missed. Specifically, much of the basis of the revision process has not been documented, neither has the approach selected for the revision process, nor has any justification for not performing a CANDU specific job and task analysis been offered. Furthermore, the Working Group has not yet proposed any criteria for evaluation of the program or provided any test items. As a result, the consultants have had to develop criteria for evaluation of the overall program and of individual courses. These criteria were applied in a more detailed review of the training objectives for two particular courses: Plant Chemistry, and Nuclear Physics and Reactor Theory. Many of the training objectives for these courses were found to be too qualitative or ones that require trainees to memorize blocks of information rather than develop in them an ability to arrive at conclusions about scientific phenomena using principles and reasoning. This assessment indicates that the training objectives are designed to achieve too low a level of cognition, inconsistent with developing an

  6. Concentrating Solar Power Program Review 2013 (Book) (Revised)

    Energy Technology Data Exchange (ETDEWEB)

    2013-06-01

    This U.S. Department of Energy (DOE) Concentrating Solar Power Program Review Meeting booklet will be provided to attendees at the Concentrating Solar Power Review Meeting in Phoenix, Arizona on April 23-25, 2013.

  7. Waste treatability guidance program. User's guide. Revision 0

    International Nuclear Information System (INIS)

    Toth, C.

    1995-01-01

    DOE sites across the country generate and manage radioactive, hazardous, mixed, and sanitary wastes. It is necessary for each site to find the technologies and associated capacities required to manage its waste. One role of DOE HQ Office of Environmental Restoration and Waste Management is to facilitate the integration of the site- specific plans into coherent national plans. DOE has developed a standard methodology for defining and categorizing waste streams into treatability groups based on characteristic parameters that influence waste management technology needs. This Waste Treatability Guidance Program automates the Guidance Document for the categorization of waste information into treatability groups; this application provides a consistent implementation of the methodology across the National TRU Program. This User's Guide provides instructions on how to use the program, including installations instructions and program operation. This document satisfies the requirements of the Software Quality Assurance Plan

  8. Waste treatability guidance program. User`s guide. Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    Toth, C.

    1995-12-21

    DOE sites across the country generate and manage radioactive, hazardous, mixed, and sanitary wastes. It is necessary for each site to find the technologies and associated capacities required to manage its waste. One role of DOE HQ Office of Environmental Restoration and Waste Management is to facilitate the integration of the site- specific plans into coherent national plans. DOE has developed a standard methodology for defining and categorizing waste streams into treatability groups based on characteristic parameters that influence waste management technology needs. This Waste Treatability Guidance Program automates the Guidance Document for the categorization of waste information into treatability groups; this application provides a consistent implementation of the methodology across the National TRU Program. This User`s Guide provides instructions on how to use the program, including installations instructions and program operation. This document satisfies the requirements of the Software Quality Assurance Plan.

  9. 75 FR 43478 - Rhode Island: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2010-07-26

    ...: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental.... Mail: Robin Biscaia, RCRA Waste Management Section, Office of Site Remediation and Restoration (OSRR 07... Delivery or Courier: Deliver your comments to: Robin Biscaia, RCRA Waste Management Section, Office of Site...

  10. 10 CFR 600.315 - Revision of budget and program plans.

    Science.gov (United States)

    2010-01-01

    ... revisions: (1) The transfer of funds among direct cost categories, functions, and activities for awards in... change in the scope or the objective of the project or program (even if there is no associated budget... accordance with the applicable costs principles for Federal funds and the requirements applicable to the...

  11. 32 CFR 34.15 - Revision of budget and program plans.

    Science.gov (United States)

    2010-07-01

    ... prior approvals are not required): (i) The transfer of funds among direct cost categories, functions and... or the objective of the project or program (even if there is no associated budget revision requiring... principles for Federal funds and recipients' cost share or match, in § 34.17 and § 34.13, respectively. (iv...

  12. 75 FR 35720 - Massachusetts: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2010-06-23

    ...: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental...: Robin Biscaia, RCRA Waste Management Section, Office of Site Remediation and Restoration (OSRR 07-1... Courier: Deliver your comments to: Robin Biscaia, RCRA Waste Management Section, Office of Site...

  13. 76 FR 72636 - Permanent Certification Program for Health Information Technology; Revisions to ONC-Approved...

    Science.gov (United States)

    2011-11-25

    ... Permanent Certification Program for Health Information Technology; Revisions to ONC-Approved Accreditor Processes AGENCY: Office of the National Coordinator for Health Information Technology (ONC), Department of... Coordinator for Health Information Technology by section 3001(c)(5) of the Public Health Service Act (PHSA) as...

  14. 76 FR 31272 - Permanent Certification Program for Health Information Technology; Revisions to ONC-Approved...

    Science.gov (United States)

    2011-05-31

    ... Permanent Certification Program for Health Information Technology; Revisions to ONC-Approved Accreditor Processes AGENCY: Office of the National Coordinator for Health Information Technology (ONC), Department of... Coordinator for Health Information Technology (the National Coordinator) by section 3001(c)(5) of the Public...

  15. 78 FR 79654 - Vermont: Proposed Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2013-12-31

    ...] Vermont: Proposed Authorization of State Hazardous Waste Management Program Revisions AGENCY... Docket ID No. EPA-R01- RCRA-2013-0554, by mail to Sharon Leitch, RCRA Waste Management and UST Section..., RCRA Waste Management and UST Section, Office of Site Remediation and Restoration (OSRR07-1), US EPA...

  16. 75 FR 69660 - Cross-Media Electronic Reporting Rule State Authorized Program Revision Approval: State of Hawaii

    Science.gov (United States)

    2010-11-15

    ... Authorized Program Revision Approval: State of Hawaii AGENCY: Environmental Protection Agency (EPA). ACTION... Reporting, of the State of Hawaii's request to revise certain of its EPA-authorized programs to allow... meet the applicable subpart D requirements. On February 16, 2010, the State of Hawaii Department of...

  17. Human Research Program Integrated Research Plan. Revision A January 2009

    Science.gov (United States)

    2009-01-01

    The Integrated Research Plan (IRP) describes the portfolio of Human Research Program (HRP) research and technology tasks. The IRP is the HRP strategic and tactical plan for research necessary to meet HRP requirements. The need to produce an IRP is established in HRP-47052, Human Research Program - Program Plan, and is under configuration management control of the Human Research Program Control Board (HRPCB). Crew health and performance is critical to successful human exploration beyond low Earth orbit. The Human Research Program (HRP) is essential to enabling extended periods of space exploration because it provides knowledge and tools to mitigate risks to human health and performance. Risks include physiological and behavioral effects from radiation and hypogravity environments, as well as unique challenges in medical support, human factors, and behavioral or psychological factors. The Human Research Program (HRP) delivers human health and performance countermeasures, knowledge, technologies and tools to enable safe, reliable, and productive human space exploration. Without HRP results, NASA will face unknown and unacceptable risks for mission success and post-mission crew health. This Integrated Research Plan (IRP) describes HRP s approach and research activities that are intended to address the needs of human space exploration and serve HRP customers and how they are integrated to provide a risk mitigation tool. The scope of the IRP is limited to the activities that can be conducted with the resources available to the HRP; it does not contain activities that would be performed if additional resources were available. The timescale of human space exploration is envisioned to take many decades. The IRP illustrates the program s research plan through the timescale of early lunar missions of extended duration.

  18. Programs of the Office of Energy Research: Revision

    International Nuclear Information System (INIS)

    1987-06-01

    In establishing each of the Federal Agencies that have been successively responsible for energy technologies and their development - the Atomic Energy Commission, the Energy Research and Development Administration, and, currently, the US Department of Energy (DOE) - Congress made specific provisions for the conduct of advanced and fundamental research. The purpose of this research has been to support the energy technology development programs by providing insight into fundamental science and associated phenomena and developing new or advanced concepts and techniques. Today, this responsibility rests with the Office of Energy Research (ER), DOE, whose present programs have their origins in pioneering energy-related research of this nature, which was initiated nearly 40 years ago. The Director, Office of Energy Research, also acts as the chief scientist and scientific advisor to the Secretary of Energy for the entire spectrum of energy research and development (R and D) programs of the Department. ER programs include several thousand individual projects and hundreds of laboratories, universities, and other research facilities throughout the Unites States. In the following pages, each of these programs and activities are described briefly for the information of the scientific community and the public at large. 5 figs., 6 tabs

  19. Nuclear Criticality Safety Organization qualification program. Revision 4

    International Nuclear Information System (INIS)

    Carroll, K.J.; Taylor, R.G.; Worley, C.A.

    1997-01-01

    The Nuclear Criticality Safety Organization (NCSO) is committed to developing and maintaining a staff of highly qualified personnel to meet the current and anticipated needs in Nuclear Criticality Safety (NCS) at the Oak Ridge Y-12 Plant. This document defines the Qualification Program to address the NCSO technical and managerial qualification as required by the Y-12 Training Implementation Matrix (TIM). It is implemented through a combination of LMES plant-wide training courses and professional nuclear criticality safety training provided within the organization. This Qualification Program is applicable to technical and managerial NCSO personnel, including temporary personnel, sub-contractors and/or LMES employees on loan to the NCSO, who perform the NCS tasks or serve NCS-related positions as defined in sections 5 and 6 of this program

  20. Independent Safety Assessment of the TOPAZ-II space nuclear reactor power system (Revised)

    International Nuclear Information System (INIS)

    1993-09-01

    The Independent Safety Assessment described in this study report was performed to assess the safety of the design and launch plans anticipated by the U.S. Department of Defense (DOD) in 1993 for a Russian-built, U.S.-modified, TOPAZ-II space nuclear reactor power system. Its conclusions, and the bases for them, were intended to provide guidance for the U.S. Department of Energy (DOE) management in the event that the DOD requested authorization under section 91b. of the Atomic Energy Act of 1954, as amended, for possession and use (including ground testing and launch) of a nuclear-fueled, modified TOPAZ-II. The scientists and engineers who were engaged to perform this assessment are nationally-known nuclear safety experts in various disciplines. They met with participants in the TOPAZ-II program during the spring and summer of 1993 and produced a report based on their analysis of the proposed TOPAZ-II mission. Their conclusions were confined to the potential impact on public safety and did not include budgetary, reliability, or risk-benefit analyses

  1. Guidance document for revision of DOE Order 5820.2A, Radioactive Waste Technical Support Program. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Kudera, D.E.; McMurtrey, C.D.; Meagher, B.G.

    1993-04-01

    This document provides guidance for the revision of DOE Order 5820.2A, ``Radioactive Waste Management.`` Technical Working Groups have been established and are responsible for writing the revised order. The Technical Working Groups will use this document as a reference for polices and procedures that have been established for the revision process. The overall intent of this guidance is to outline how the order will be revised and how the revision process will be managed. In addition, this document outlines technical issues considered for inclusion by a Department of Energy Steering Committee.

  2. TRUPACT-II Container Maintenance Program Plan

    International Nuclear Information System (INIS)

    1991-05-01

    This document details the maintenance, repair, and replacement of components, as well as the documentation required and the procedures to be followed to maintain the integrity of the TRUPACT-II container in accordance with OM-134, TRUPACT-II Container Operations and Maintenance Manual; and the TRUPACT-II Container Certificate of Compliance (Number 9218). The routine shipping and receiving inspections required by the Department of Transportation (DOT), Department of Energy (DOE), Nuclear Regulatory Commission (NRC) and other regulations are not addressed in this document. This document applies to all DOE shipping and receiving sites that use the TRUPACT-II containers

  3. Planning integration FY 1996 program plan. Revision 1

    International Nuclear Information System (INIS)

    1995-09-01

    This Multi-Year Program Plan (MAP) Planning Integration Program, Work Breakdown Structure (WBS) Element 1.8.2, is the primary management tool to document the technical, schedule, and cost baseline for work directed by the US Department of Energy (DOE), Richland Operations Office (RL). As an approved document, it establishes an agreement between RL and the performing contractors for the work to be performed. It was prepared by Westinghouse Hanford Company (WHC) and Pacific Northwest Laboratory (PNL). The MYPPs for the Hanford Site programs are to provide a picture from fiscal year (FY) 1996 through FY 2002. At RL Planning and Integration Division (PID) direction, only the FY 1996 Planning Integration Program work scope has been planned and presented in this MAP. Only those known significant activities which occur after FY 1996 are portrayed in this MAP. This is due to the uncertainty of who will be accomplishing what work scope when, following the award of the Management and Integration (M ampersand I) contract

  4. Geothermal Today: 2003 Geothermal Technologies Program Highlights (Revised)

    Energy Technology Data Exchange (ETDEWEB)

    2004-05-01

    This outreach publication highlights milestones and accomplishments of the DOE Geothermal Technologies Program for 2003. Included in this publication are discussions of geothermal fundamentals, enhanced geothermal systems, direct-use applications, geothermal potential in Idaho, coating technology, energy conversion R&D, and the GeoPowering the West initiative.

  5. Professional Student Exchange Program (PSEP) Administrative Manual. Revised

    Science.gov (United States)

    Western Interstate Commission for Higher Education, 2012

    2012-01-01

    WICHE (the Western Interstate Commission for Higher Education) is a regional, nonprofit organization. WICHE and its 15 member states work to improve access to higher education and ensure student success. Its student exchange programs, regional initiatives, and its research and policy work allow it to assist constituents throughout the West and…

  6. Guidelines for Planning the School Breakfast Program. Revised.

    Science.gov (United States)

    Georgia State Dept. of Education, Atlanta. Office of School Administrative Services.

    Some of the factors considered in these guidelines include basic nutritional requirements, food component minimums, food variety, and amounts of food served in elementary and secondary school breakfast programs. Suggestions are made for serving foods that will appeal to young people. Samples of hot and cold menus are provided. Forms for evaluating…

  7. A Revised Admissions Standard for One Community College Nursing Program

    Science.gov (United States)

    Lown, Maris A.

    2010-01-01

    Predicting success on the NCLEX-RN is of paramount importance to nursing programs as they are held accountable for this outcome by accrediting agencies and by boards of nursing. This action research study examined the relationship between the NET admission test, anatomy and physiology grades, grade point average (GPA) on admission to the program…

  8. Small Town Energy Program (STEP) Final Report revised

    Energy Technology Data Exchange (ETDEWEB)

    Wilson, Charles (Chuck) T.

    2014-01-02

    University Park, Maryland (“UP”) is a small town of 2,540 residents, 919 homes, 2 churches, 1 school, 1 town hall, and 1 breakthrough community energy efficiency initiative: the Small Town Energy Program (“STEP”). STEP was developed with a mission to “create a model community energy transformation program that serves as a roadmap for other small towns across the U.S.” STEP first launched in January 2011 in UP and expanded in July 2012 to the neighboring communities of Hyattsville, Riverdale Park, and College Heights Estates, MD. STEP, which concluded in July 2013, was generously supported by a grant from the U.S. Department of Energy (DOE). The STEP model was designed for replication in other resource-constrained small towns similar to University Park - a sector largely neglected to date in federal and state energy efficiency programs. STEP provided a full suite of activities for replication, including: energy audits and retrofits for residential buildings, financial incentives, a community-based social marketing backbone and local community delivery partners. STEP also included the highly innovative use of an “Energy Coach” who worked one-on-one with clients throughout the program. Please see www.smalltownenergy.org for more information. In less than three years, STEP achieved the following results in University Park: • 30% of community households participated voluntarily in STEP; • 25% of homes received a Home Performance with ENERGY STAR assessment; • 16% of households made energy efficiency improvements to their home; • 64% of households proceeded with an upgrade after their assessment; • 9 Full Time Equivalent jobs were created or retained, and 39 contractors worked on STEP over the course of the project. Estimated Energy Savings - Program Totals kWh Electricity 204,407 Therms Natural Gas 24,800 Gallons of Oil 2,581 Total Estimated MMBTU Saved (Source Energy) 5,474 Total Estimated Annual Energy Cost Savings $61,343 STEP clients who

  9. TRUPACT-II container maintenance program plan

    International Nuclear Information System (INIS)

    1990-11-01

    This document details the maintenance/repair and replacement of components, as well as the documentation required and the procedures to be followed to maintain the integrity of the TRUPACT-II container, in accordance with requirements of the TRUPACT-II Container Operations and Maintenance Manual, OM-134, the TRUPACT-II Container Safety Analysis Report (SARP), and the TRUPACT-II Container Certificate of Compliance (Number 9218). The routine shipping and receiving inspections required by the Department of Transportation (DOT), Department of Energy (DOE), Nuclear Regulatory Commission (NRC) and other regulations are not addressed in this document. This document applies to all DOE shipping and receiving sites that use the TRUPACT-II containers

  10. UMTRA Project Office quality assurance program plan. Revision 6

    International Nuclear Information System (INIS)

    1994-09-01

    The Uranium Mill Tailings Remedial Action (UMTRA) Project was established to accomplish remedial actions at inactive uranium mill tailings sites. The UMTRA Project's mission is to stabilize and control the residual radioactive materials at designated sites in a safe and environmentally sound manner so as to minimize or eliminate radiation health hazards to the public. Because these efforts may involve possible risks to public health and safety, a quality assurance (QA) program that conforms to the applicable criteria has been established to control the quality of the work. This document, the Quality Assurance Program Plan (QAPP), brings into one document the essential criteria to be applied on a selective basis, depending upon the nature of the activity being conducted, and describes how those criteria shall be applied to the UMTRA Project. QA requirements contained in this QAPP shall apply to all personnel, processes, and activities, including planning, scheduling, and cost control, performed by the UMTRA Project Office and its contractors

  11. DOE Region 6 Radiological Assistance Program plan. Revision 1

    International Nuclear Information System (INIS)

    Jakubowski, F.M.

    1995-11-01

    The US Department of Energy (DOE) has sponsored a Radiological Assistance Program (RAP) since the 1950's. The RAP is designed to make DOE resources available to other DOE facilities, state, tribal, local, private businesses, and individuals for the explicit purpose of assisting during radiological incidents. The DOE has an obligation, through the Atomic Energy Act of 1954, as amended, to provide resources through the Federal Radiological Emergency Response Plan (FRERP, Nov. 1985) in the event of a radiological incident. Toward this end, the RAP program is implemented on a regional basis, and has planned for an incremental response capability with regional coordination between states and DOE response elements. This regional coordination is intended to foster a working relationship between DOE radiological assistance elements and those state, tribal, and local agencies responsible for first response to protect public health and safety

  12. LANL Safeguards and Security Assurance Program. Revision 6

    International Nuclear Information System (INIS)

    1995-01-01

    The Safeguards and Security (S and S) Assurance Program provides a continuous quality improvement approach to ensure effective, compliant S and S program implementation throughout the Los Alamos National Laboratory. Any issues identified through the various internal and external assessments are documented, tracked and closed using the Safeguards and Security Issue Management Program. The Laboratory utilizes an integrated S and S systems approach to protect US Department of Energy (DOE) interests from theft or diversion of special nuclear material (SNM), sabotage, espionage, loss or theft of classified/controlled matter or government property, and other hostile acts that may cause unacceptable impacts on national security, health and safety of employees and the public, and the environment. This document explains the basis, scope, and conduct of the S and S process to include: self-assessments, issue management, risk assessment, and root cause analysis. It also provides a discussion of S and S topical areas, roles and responsibilities, process flow charts, minimum requirements, methodology, terms, and forms

  13. Nevada Test Site Radiation Protection Program - Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Radiological Control Managers' Council

    2008-06-01

    Title 10 Code of Federal Regulations (CFR) Part 835, 'Occupational Radiation Protection,' establishes radiation protection standards, limits, and program requirements for protecting individuals from ionizing radiation resulting from the conduct of U.S. Department of Energy (DOE) activities. 10 CFR 835.101(a) mandates that DOE activities be conducted in compliance with a documented Radiation Protection Program (RPP) as approved by DOE. This document promulgates the RPP for the Nevada Test Site (NTS), related (on-site or off-site) U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) operations, and environmental restoration off-site projects. This NTS RPP promulgates the radiation protection standards, limits, and program requirements for occupational exposure to ionizing radiation resulting from NNSA/NSO activities at the NTS and other operational areas as stated in 10 CFR 835.1(a). NNSA/NSO activities (including design, construction, operation, and decommissioning) within the scope of this RPP may result in occupational exposures to radiation or radioactive material. Therefore, a system of control is implemented through specific references to the site-specific NV/YMP RCM. This system of control is intended to ensure that the following criteria are met: (1) occupational exposures are maintained as low as reasonably achievable (ALARA), (2) DOE's limiting values are not exceeded, (3) employees are aware of and are prepared to cope with emergency conditions, and (4) employees are not inadvertently exposed to radiation or radioactive material.

  14. Nevada Test Site Radiation Protection Program - Revision 1

    International Nuclear Information System (INIS)

    Nevada Test Site Radiological Control Managers' Council

    2008-01-01

    Title 10 Code of Federal Regulations (CFR) Part 835, 'Occupational Radiation Protection,' establishes radiation protection standards, limits, and program requirements for protecting individuals from ionizing radiation resulting from the conduct of U.S. Department of Energy (DOE) activities. 10 CFR 835.101(a) mandates that DOE activities be conducted in compliance with a documented Radiation Protection Program (RPP) as approved by DOE. This document promulgates the RPP for the Nevada Test Site (NTS), related (on-site or off-site) U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) operations, and environmental restoration off-site projects. This NTS RPP promulgates the radiation protection standards, limits, and program requirements for occupational exposure to ionizing radiation resulting from NNSA/NSO activities at the NTS and other operational areas as stated in 10 CFR 835.1(a). NNSA/NSO activities (including design, construction, operation, and decommissioning) within the scope of this RPP may result in occupational exposures to radiation or radioactive material. Therefore, a system of control is implemented through specific references to the site-specific NV/YMP RCM. This system of control is intended to ensure that the following criteria are met: (1) occupational exposures are maintained as low as reasonably achievable (ALARA), (2) DOE's limiting values are not exceeded, (3) employees are aware of and are prepared to cope with emergency conditions, and (4) employees are not inadvertently exposed to radiation or radioactive material

  15. Revision 2 of the Program of NPP Krsko Decommissioning and SF and LILW Disposal

    International Nuclear Information System (INIS)

    Levanat, I.; Lokner, V.; Rapic, A.

    2010-01-01

    First joint Slovenian-Croatian Program of NPP Krsko Decommissioning and SF and LILW Disposal (DP) was completed in 2004 and formally adopted in 2005. As bilateral agreement on the NPP requires periodic revisions at least each 5 years, revision 2 of DP was started in September 2008, with the purpose to incorporate relevant developments since the 1st revision, to improve the level of details and reliability of DP, and to propose updated and more accurate cost estimates and appropriate financing models. In the first phase of the revision, new supporting studies for DP modules were prepared. Among these studies, the most demanding was the NPP Krsko specific Preliminary Decommissioning Plan (PDP), complying with the IAEA-recommended format, which included development of the NPP decommissioning inventory database. For upgrade of SF management, new and more detailed descriptions with improved cost estimates were prepared. Update of LILW disposal concept was based on new developments and projects prepared for the Slovenian repository. In the second phase of the revision, integrated DP scenarios were formulated and analyzed. They integrate NPP decommissioning together with RW and SF management/disposal into rationally inter-related sequences. Boundary conditions for this revision required: (a) that the reference scenario from the previous revision should be re-examined, with appropriate variations or new alternatives; (b) that the option of the NPP Krsko life extension should also be included; and (c) that the possibility of diverging interests of the contracting parties should also be analyzed (i.e. waste division and separate management). Finally, scenario evaluation is intended to compare the analyzed scenarios taking into account both their feasibility and estimated costs. It should provide the basis for determining future financing of DP, namely the annuities to be paid by the NPP Krsko owners into the national decommissioning funds.(author).

  16. METHUSELAH II - A Fortran program and nuclear data library for the physics assessment of liquid-moderated reactors

    International Nuclear Information System (INIS)

    Brinkworth, M.J.; Griffiths, J.A.

    1966-03-01

    METHUSELAH II is a Fortran program with a nuclear data library, used to calculate cell reactivity and burn-up in liquid-moderated reactors. It has been developed from METHUSELAH I by revising the nuclear data library, and by introducing into the program improvements relating to nuclear data, improvements in efficiency and accuracy, and additional facilities which include a neutron balance edit, specialised outputs, fuel cycling, and fuel costing. These developments are described and information is given on the coding and usage of versions of METHUSELAH II for the IBM 7030 (STRETCH), IBM 7090, and KDF9 computers. (author)

  17. TRUPACT-II Content Codes (TRUCON), Revision 8 and list of chemicals and materials in TRUCON (chemical list), Revision 7

    International Nuclear Information System (INIS)

    1996-03-01

    The Transuranic Package Transporter (TRUPACT-II) Content Codes document (TRUCON) represents the development of a new content code system for shipping contact handled transuranic (CH-TRU) waste in TRUPACT-II. It will be used to convert existing waste forms, content codes, and any other identification codes into a system that is uniform throughout for all the Department of Energy (DOE) sites. These various codes can be grouped under the newly formed shipping content codes without any loss of waste characterization information. The TRUCON document provides a parametric description for each content code for waste generated and compiles this information for all ten DOE sites. Compliance with waste generation, processing and certification procedures at the sites (outlined in the TRUCON document for each content code) ensures that prohibited waste forms are not present in the waste. The content code essentially gives a description of the CH-TRU waste material in terms of processes and packaging, and the generation location. This helps to provide cradle-to-grave traceability of the waste material so that the various actions required to assess its qualification as payload for the TRUPACT-II package can be performed

  18. TRUPACT-II container maintenance program plan

    International Nuclear Information System (INIS)

    1990-01-01

    This document details the maintenance/repair and replacement of components, as well as the documentation required and the procedures to be followed to maintain the integrity of the TRUPACT-II container

  19. ANADP II Program Committee Closing Remarks 2013

    OpenAIRE

    Program Committee

    2014-01-01

    Aligning National Approaches to Digital Preservation: An Action Assembly Biblioteca de Catalunya (National Library of Catalonia) November 18-20, 2013, Barcelona, Spain summary The Aligning National Approaches to Digital Preservation (ANADP) II Action Assembly will align digital preservation efforts internationally between communities—including national libraries, academic libraries, public libraries, research centers, archives, corporations, and funding agencies. ANADP II will be a highly par...

  20. MENO-II: An AI-Based Programming Tutor.

    Science.gov (United States)

    Soloway, Elliot; And Others

    This report examines the features and performance of the BUG-FINDing component of MENO-II, a computer-based tutor for beginning PASCAL programming students. A discussion of the use of artificial intelligence techniques is followed by a summary of the system status and objectives. The two main components of MENO-II are described, beginning with the…

  1. Alternative Teacher Preparation Programs. Title II News You Can Use

    Science.gov (United States)

    Office of Postsecondary Education, US Department of Education, 2015

    2015-01-01

    Title II of the "Higher Education Act of 1965" ("HEA"), as amended in 2008 by the "Higher Education Opportunity Act," requires states to report annually on key elements of their teacher preparation programs and requirements for initial teacher credentialing, kindergarten through 12th grade. "Title II News You Can…

  2. Modeling Fe II Emission and Revised Fe II (UV) Empirical Templates for the Seyfert 1 Galaxy I Zw 1

    Science.gov (United States)

    Bruhweiler, F.; Verner, E.

    2008-03-01

    We use the narrow-lined broad-line region (BLR) of the Seyfert 1 galaxy, I Zw 1, as a laboratory for modeling the ultraviolet (UV) Fe II 2100-3050 Å emission complex. We calculate a grid of Fe II emission spectra representative of BLR clouds and compare them with the observed I Zw 1 spectrum. Our predicted spectrum for log [nH/(cm -3) ] = 11.0, log [ΦH/(cm -2 s-1) ] = 20.5, and ξ/(1 km s-1) = 20, using Cloudy and an 830 level model atom for Fe II with energies up to 14.06 eV, gives a better fit to the UV Fe II emission than models with fewer levels. Our analysis indicates (1) the observed UV Fe II emission must be corrected for an underlying Fe II pseudocontinuum; (2) Fe II emission peaks can be misidentified as that of other ions in active galactic nuclei (AGNs) with narrow-lined BLRs possibly affecting deduced physical parameters; (3) the shape of 4200-4700 Å Fe II emission in I Zw 1 and other AGNs is a relative indicator of narrow-line region (NLR) and BLR Fe II emission; (4) predicted ratios of Lyα, C III], and Fe II emission relative to Mg II λ2800 agree with extinction corrected observed I Zw 1 fluxes, except for C IV λ1549 (5) the sensitivity of Fe II emission strength to microturbulence ξ casts doubt on existing relative Fe/Mg abundances derived from Fe II (UV)/Mg II flux ratios. Our calculated Fe II emission spectra, suitable for BLRs in AGNs, are available at http://iacs.cua.edu/people/verner/FeII. Based on observations made with the NASA/ESA Hubble Space Telescope, obtained at the Space Telescope Science Institute, which is operated by the Association of Universities for Research in Astronomy, Inc., under NASA contract NAS 05-26555.

  3. Computer Program of SIE ASME-NH (Revision 1.0) Code

    Energy Technology Data Exchange (ETDEWEB)

    Koo, Gyeong Hoi; Lee, J. H

    2008-01-15

    In this report, the SIE ASME (Structural Integrity Evaluations by ASME-NH) (Revision 1.0), which has a computerized implementation of ASME Pressure Vessels and Piping Code Section III Subsection NH rules, is developed to apply to the next generation reactor design subjecting to the elevated temperature operations over 500 .deg. C and over 30 years design lifetime, and the user's manual for this program is described in detail.

  4. Computer Program of SIE ASME-NH (Revision 1.0) Code

    International Nuclear Information System (INIS)

    Koo, Gyeong Hoi; Lee, J. H.

    2008-01-01

    In this report, the SIE ASME (Structural Integrity Evaluations by ASME-NH) (Revision 1.0), which has a computerized implementation of ASME Pressure Vessels and Piping Code Section III Subsection NH rules, is developed to apply to the next generation reactor design subjecting to the elevated temperature operations over 500 .deg. C and over 30 years design lifetime, and the user's manual for this program is described in detail

  5. RADTRAN II: revised computer code to analyze transportation of radioactive material

    International Nuclear Information System (INIS)

    Taylor, J.M.; Daniel, S.L.

    1982-10-01

    A revised and updated version of the RADTRAN computer code is presented. This code has the capability to predict the radiological impacts associated with specific schemes of radioactive material shipments and mode specific transport variables

  6. A Guide to Program Planning Vol. II.

    Science.gov (United States)

    Allen, Earl, Sr.

    This booklet is a simplified guide for program planning and is intended to complement a somewhat lengthier companion booklet on program evaluation. It spells out in outline fashion the basic elements and steps involved in the planning process. Brief sections focus in turn on different phases of the planning process, including problem…

  7. The TRUPACT-II Matrix Depleton Program

    International Nuclear Information System (INIS)

    Connolly, M.J.; Djordjevic, S.M.; Loehr, C.A.; Smith, M.C.; Banjac, V.; Lyon, W.F.

    1995-01-01

    Contact-handled transuranic (CH-TRU) wastes will be shipped and disposed at the Waste Isolation Pilot Plant (WIPP) repository in the Transuranic Package Transporter-II (TRUPACT-II) shipping package. A primary transportation requirement for the TRUPACT-II is that the concentration of potentially flammable gases (i.e., hydrogen and methane) must not exceed 5 percent by volume in the package or the payload during a 60-day shipping period. Decomposition of waste materials by radiation, or radiolysis, is the predominant mechanism of gas generation during transport. The gas generation potential of a target waste material is characterized by a G-value, which is the number of molecules of gas generated per 100 eV of ionizing radiation absorbed by the target material. To demonstrate compliance with the flammable gas concentration requirement, theoretical worst-case calculations were performed to establish allowable wattage (decay heat) limits for waste containers. The calculations were based on the G-value for the waste material with the highest potential for flammable gas generation. The calculations also made no allowances for decreases of the G-value over time due to matrix depletion phenomena that have been observed by many experimenters. Matrix depletion occurs over time when an alpha-generating source particle alters the target material (by evaporation, reaction, or decomposition) into a material of lower gas generating potential. The net effect of these alterations is represented by the ''effective G-value.''

  8. International Photovoltaic Program Plan. Volume II. Appendices

    Energy Technology Data Exchange (ETDEWEB)

    Costello, D.; Koontz, R.; Posner, D.; Heiferling, P.; Carpenter, P.; Forman, S.; Perelman, L.

    1979-12-01

    This second volume of a two-part report on the International Photovoltaic Program Plan contains appendices summarizing the results of analyses conducted in preparation of the plan. These analyses include compilations of relevant statutes and existing Federal programs; strategies designed to expand the use of photovoltaics abroad; information on the domestic photovoltaic plan and its impact on the proposed international plan; perspectives on foreign competition; industry views on the international photovoltaic market and ideas about how US government actions could affect this market; international financing issues; and information on issues affecting foreign policy and developing countries.

  9. Revised Master Plan for the Hood River Production Program, Technical Report 2008.

    Energy Technology Data Exchange (ETDEWEB)

    Oregon Department of Fish and Wildlife; Confederated Tribes of the Warm Springs Reservation

    2008-04-28

    The Hood River Production Program (HRPP) is a Bonneville Power Administration (BPA) funded program initiated as a mitigation measure for Columbia River hydrosystem effects on anadromous fish. The HRPP began in the early 1990s with the release of spring Chinook and winter steelhead smolts into the basin. Prior to implementation, co-managers, including the Confederated Tribes of the Warm Springs Reservation and the Oregon Department of Fish and Wildlife drafted the Hood River Production Master Plan (O'Toole and ODFW 1991a; O'Toole and ODFW 1991b) and the Pelton Ladder Master Plan (Smith and CTWSR 1991). Both documents were completed in 1991 and subsequently approved by the Council in 1992 and authorized through a BPA-led Environmental Impact Statement in 1996. In 2003, a 10-year programmatic review was conducted for BPA-funded programs in the Hood River (Underwood et al. 2003). The primary objective of the HRPP Review (Review) was to determine if program goals were being met, and if modifications to program activities would be necessary in order to meet or revise program goals. In 2003, an agreement was signed between PacifiCorp and resource managers to remove the Powerdale Dam (RM 10) and associated adult trapping facility by 2010. The HRPP program has been dependant on the adult trap to collect broodstock for the hatchery programs; therefore, upon the dam's removal, some sort of replacement for the trap would be needed to continue the HRPP. At the same time the Hood River Subbasin Plan (Coccoli 2004) was being written and prompted the co-managers to considered future direction of the program. This included revising the numerical adult fish objectives based on the assimilated data and output from several models run on the Hood River system. In response to the Review as well as the Subbasin Plan, and intensive monitoring and evaluation of the current program, the HRPP co-managers determined the spring Chinook program was not achieving the HRPP

  10. 76 FR 28727 - Child Nutrition (CN) Labeling Program; Request for Extension and Revision of a Currently Approved...

    Science.gov (United States)

    2011-05-18

    ... (CN) Labeling Program; Request for Extension and Revision of a Currently Approved Information... INFORMATION: Title: Child Nutrition Labeling Program. OMB Number: 0581-0261 . Expiration Date of Approval: 3... collection. Abstract: The Child Nutrition (CN) Labeling Program is a voluntary technical assistance service...

  11. The revised program for measurements in intense operation mode according to AVV-IMIS

    International Nuclear Information System (INIS)

    Bieringer, J.; Wirth, E.; Buehling, A.; Mueller-Neumann, M.; Haase, G.; Heinrich, T.; Steinkopff, T.; Wiezorek, C.

    2007-01-01

    The monitoring program for measurements in intense operation mode has been revised recently by a working group at the Federal Ministry for Environment, Nature Conservation and Reactor Safety (BMU). The major issues of the revision are reported in this contribution. Measurements in intense operation must be appropriate for fast assessment of the radiological situation, for estimating the dose to the population and for decisions on countermeasures to minimize the dose. In order to meet these requirements the structure of the measurement program in intense operation mode was divided into three phases when different exposition paths are relevant: before and during dispersion of radioactive material, immediately after dispersion of radioactive material has ended and a late phase when contamination values have decreased in different environmental media. For each of these phases a special measurement program was defined that is tailored to achieve the above mentioned objectives. Minimum detectable activity concentrations were introduced similar to the measurement program in routine operation mode. They follow the intervention levels in the catalogue of countermeasures and maximum permitted values given by the European Union (EU) for food and animal feed. The minimum detectable activity concentrations were defined such that the detection of 1/10 of the intervention levels for countermeasures is ensured. (orig.)

  12. Program plan for shipment, receipt, and storage of the TMI-2 core. Revision 1

    International Nuclear Information System (INIS)

    Quinn, G.J.; Reno, H.W.; Schmitt, R.C.

    1985-01-01

    This plan addresses the preparation and shipment of core debris from Three Mile Island Unit 2 (TMI-2) to the Idaho National Engineering Laboratory (INEL) and receipt and storage of that core debris. The Manager of the Nuclear Materials Evaluation Programs Division of EG and G Idaho, Inc. will manage two separate but integrated programs, one located at TMI (Part 1) and the other at INEL (Part 2). The Technical Integration Office (at TMI) is responsible for developing and implementing Part 1, TMI-2 Core Shipment Program. The Technical Support Branch (at INEL) is responsible for developing and implementing Part 2, TMI-2 Core Receipt and Storage. The plan described herein is a revision of a previous document entitled Plan for Shipment, Storage, and Examination of TMI-2 Fuel. This revision was required to delineate changes, primarily in Part 2, Core Activities Program, of the previous document. That part of the earlier document related to core examination was reidentified in mid-FY-1984 as a separate trackable entity entitled Core Sample Acquisition and Examination Project, which is not included here

  13. Acquisition: Implementation of the DoD Management Control Program for Navy Acquisition Category II and III Programs

    National Research Council Canada - National Science Library

    2004-01-01

    ... deviations in cost, schedule, and performance requirements in acquisition program baselines for Acquisition Category II and III programs and in identifying whether program managers are reporting...

  14. 77 FR 33456 - Public Water Supply Supervision Program; Program Revision for the State of Washington

    Science.gov (United States)

    2012-06-06

    ... ENVIRONMENTAL PROTECTION AGENCY [FRL-9682-4] Public Water Supply Supervision Program; Program... State Public Water Supply Supervision Primacy Program. Washington has adopted regulations analogous to... of Health--Office of Drinking Water, [[Page 33457

  15. 76 FR 52658 - State Program Requirements; Approval of Application for Program Revision to the National...

    Science.gov (United States)

    2011-08-23

    ... program, pretreatment program, and miscellaneous non-domestic discharges; and Phase III includes mining... the EPA consider adopting stipulations related to jurisdiction issues and authorities of federally...

  16. Adapting Evidence-Based Prevention Approaches for Latino Adolescents: The Familia Adelante Program - Revised

    Directory of Open Access Journals (Sweden)

    Richard C. Cervantes

    2012-12-01

    Full Text Available Behavioral health is defined as the absence of mental illness or substance use problems and the presence of positive emotional well being. Although many U.S. Hispanic youth are at increased risk for substance abuse, suicidality, teen pregnancy, unsafe sexual practices and HIV, there exists a lack of available evidence-based practices for Hispanic youth which promotes behavioral health and HIV prevention. The objective of the current research was to adapt and revise the Familia Adelante (FA Program, a behavioral health, drug intervention and prevention program to incorporate an HIV prevention component. Through qualitative community based participatory methods, including an expert panel and members of the target population, the curriculum was redesigned to integrate effective HIV risk reduction strategies. The process of adapting the intervention is described in this paper, as well as recommendations for future research in program adaptation.

  17. 76 FR 5157 - Public Water Supply Supervision Program; Program Revision for the State of Alaska

    Science.gov (United States)

    2011-01-28

    ... ENVIRONMENTAL PROTECTION AGENCY [FRL-9259-6] Public Water Supply Supervision Program; Program... Water Supply Supervision Primacy Program. Alaska has adopted regulations analogous to EPA's Stage 2 Disinfectants and Disinfection Byproducts Rule; Long Term 2 Enhanced Surface Water Treatment Rule; and Lead and...

  18. 76 FR 366 - Public Water Supply Supervision Program; Program Revision for the State of Washington

    Science.gov (United States)

    2011-01-04

    ... ENVIRONMENTAL PROTECTION AGENCY [FRL-9247-4] Public Water Supply Supervision Program; Program... State Public Water Supply Supervision Primacy Program. Washington has adopted a definition for public water system that is analogous to EPA's definition of public water system, and has adopted regulations...

  19. 78 FR 42945 - Public Water Supply Supervision Program; Program Revision for the State of Oregon

    Science.gov (United States)

    2013-07-18

    ... ENVIRONMENTAL PROTECTION AGENCY [FRL-9834-9] Public Water Supply Supervision Program; Program... Water Supply Supervision Primacy Program. Oregon has adopted regulations analogous to EPA's Stage 2 Disinfectants and Disinfection Byproducts Rule; Long Term 2 Enhanced Surface Water Treatment Rule; Ground Water...

  20. Full-scale mark II CRT program facility description report

    International Nuclear Information System (INIS)

    Namatame, Ken; Kukita, Yutaka; Ito, Hideo; Yamamoto, Nobuo; Shiba, Masayoshi

    1980-03-01

    Started in fiscal year 1977, the Full-Scale Mark II CRT (Containment Response Test) Program is proceeding for the period of five years. The primary objective of the CRT Program is to provide a data base for evaluation of the pressure suppression pool hydrodynamic loads associated with a postulated loss-of-coolant accident in the BWR Mark II containment system. The test facility was designed and constructed from fiscal year 1977 to 1978, and completed in March 1979. It is 1/18 in volume and has a wetwell which is a full-scale replica of one 20 0 -sector of that of a reference Mark II. This report describes design concepts, dimensions and constructions of the test facility, as well as specifications, locations and installation schemes of the measuring equipments. Results of soil structure inspection, vacuum breaker test and shaker test of the containment shell are given in the appendices. (author)

  1. MAPLE-II. A program for plotting fault trees

    International Nuclear Information System (INIS)

    Poucet, A.; Van Den Muyzenberg, C.L.

    1987-01-01

    The MAPLE II code is an improved version of the MAPLE program for plotting fault trees. MAPLE II has added features which make it a versatile tool for drawing large and complex logic trees. The code is developed as part of a package for computer aided fault tree construction and analysis in which it is integrated and used as a documentation tool. However the MAPLE II code can be used as a separate program which uses as input a structure function of a tree and a description of the events and gates which make up the tree. This report includes a short description of the code and of its features. Moreover it contains the how-to-use and some indications for implementing the code and for adapting it to different graphics systems

  2. Full-Scale Mark II CRT Program data report, 1

    International Nuclear Information System (INIS)

    Namatame, Ken; Kukita, Yutaka; Yamamoto, Nobuo; Shiba, Masayoshi

    1979-12-01

    The Full-Scale Mark II CRT (Containment Response Test) Program was initiated in April 1976 to provide a full-scale data basis for the evaluation of the pressure suppression pool hydrodynamic loads associated with a hypothetical LOCA in a BWR Mark II Containment. The test facility, completed in March 1979, is 1/18 in volume of a typical 1100 MWe Mark II, and has a wetwell which is a full-scale replica of one 20 0 -sector of that of the reference Mark II. The present report documents experimental data from TEST 0002, a medium size (100 mm) water blowdown test, performed by Hitachi Ltd. for JAERI as the second of the four shakedown tests. Test data is provided for the vessel depressurization, the pressure and temperature responses in the test containment, and especially for the chugging phenomena associated with low flux steam condensation in the pool. (author)

  3. Mathematics Programming on the Apple II and IBM PC.

    Science.gov (United States)

    Myers, Roy E.; Schneider, David I.

    1987-01-01

    Details the features of BASIC used in mathematics programming and provides the information needed to translate between the Apple II and IBM PC computers. Discusses inputing a user-defined function, setting scroll windows, displaying subscripts and exponents, variable names, mathematical characters and special symbols. (TW)

  4. NWTS waste package program plan. Volume II. Program logic networks

    International Nuclear Information System (INIS)

    1981-10-01

    This document describes the work planned for developing the technology to design, test and produce packages used for the long-term isolation of nuclear waste in deep geologic repositories. Waste forms considered include spent fuel and high-level waste. The testing and selection effort for barrier materials for radionuclide containment is described. The NWTS waste package program is a design-driven effort; waste package conceptual designs are used as input for preliminary designs, which are upgraded to a final design as materials and testing data become available. Performance assessment models are developed and validated. Milestones and a detailed schedule are given for the waste package development effort. Program logic networks defining work flow, interfaces among the NWTS Projects, and interrelationships of specific activities are presented. Detailed work elements are provided for the Waste Package Program Plan subtasks - design and development, waste form, barrier materials, and performance evaluation - for salt and basalt, host rocks for which the state of waste package knowledge and the corresponding data base are advanced

  5. Savannah River interim waste management program plan: FY 1984. Revision 1

    International Nuclear Information System (INIS)

    1983-10-01

    This document provides the program plan as requested by the Savannah River Operations Office of the Department of Energy. The plan was developed to provide a working knowledge of the nature and extent of the interim waste management programs being undertaken by Savannah River (SR) contractors for the Fiscal Year 1984. In addition, the document projects activities for several years beyond 1984 to adequately plan for safe handling and storage of radioactive wastes generated at Savannah River and for developing technology for improved management of low-level solid wastes. A revised plan will be issued prior to the beginning of the first quarter of each fiscal year. In this document, work descriptions and milestone schedules are current as of the date of publication. Budgets are based on available information as of June 1983

  6. Quality Assurance Program Plan for TRUPACT-II Gas Generation Test Program

    International Nuclear Information System (INIS)

    2002-01-01

    The Gas Generation Test Program (GGTP), referred to as the Program, is designed to establish the concentration of flammable gases and/or gas generation rates in a test category waste container intended for shipment in the Transuranic Package Transporter-II (TRUPACT-II). The phrase 'gas generationtesting' shall refer to any activity that establishes the flammable gas concentration or the flammable gas generation rate. This includes, but is not limited to, measurements performed directly on waste containers or during tests performed on waste containers. This Quality Assurance Program Plan (QAPP) documents the quality assurance (QA) and quality control (QC) requirements that apply to the Program. The TRUPACT-II requirements and technical bases for allowable flammable gas concentration and gas generation rates are described in the TRUPACT-II Authorized Methods for Payload Control (TRAMPAC).

  7. Labour anxiety questionnaire (KLP II)- revised-the construction and psychological validation

    OpenAIRE

    Putyński, Leszek; Paciorek, Mariusz

    2008-01-01

    Self-report Labour Anxiety Questionnaire (KLP II) was developed to asses the level of labour anxiety in pregnant women. This short tool consists of 9 items, which include attitudes toward labour and fear of labour. The questionnaire was valided on 53 pregnant women. The results of the study indicate that the Labour Anxiety Questionnaire (KLP II) is reliable and valid method to identify pregnant women with high level of labour anxiety.

  8. KAFEPA-II program users' manual and description

    International Nuclear Information System (INIS)

    Suk, H. C.; Hwang, W.; Kim, B. G.; Sim, K. S.; Heo, Y. H.; Byun, T. S.; Park, G. S.

    1992-04-01

    KAFEPA-II is a computer program for simulating the behaviour of UO 2 fuel elements under normal operating conditions of a CANDU reactor. It computes the one-dimensional temperature distribution and thermal expansion of the fuel pellets. The amount of gas released during irradiation of the fuel is also computed. Thermal expansion and gas pressure inside the fuel element are then used to compute the strains and stresses in the sheath. This document is intended as a user's manual and description for KAFEPA-II. (Author)

  9. Laterally positioned flap-revised technique along with platelet rich fibrin in the management of Miller class II gingival recession

    Directory of Open Access Journals (Sweden)

    Jagmohan Singh

    2013-01-01

    Full Text Available Gingival recession is a complex phenomenon that may present numerous therapeutic challenges to the clinician. The laterally positioned flap is commonly used to cover isolated, denuded roots that have adequate donor tissue laterally and vestibular depth. Various modifications in laterally sliding flap have been proposed in order to avoid the reported undesirable results on the donor teeth. Recently, use of growth factors has been proposed in combination with surgical techniques. This article highlights the use of laterally positioned pedicle flap-revised technique as a modification of laterally sliding flap technique along with autologous suspension of growth factors, platelet rich fibrin membrane (PRF for the management of localized Miller class-II gingival recession. After 6 months of follow-up, the clinical condition was stable with 80% root coverage and satisfactory gingival tissue healing at both donor and recipient site with no signs of inflammation. An excellent esthetical outcome was achieved and the patient was satisfied with case resolution.

  10. Quality Assurance Program Plan for the Hazardous Materials Transportation and Packaging Program. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Calihan, T.W. III; Votaw, E.F.

    1995-05-01

    This QAPP covers only the implementation accomplished through Level I and II manuals. It covers the quality affecting activities identified in USDOE orders (both HQ and Richland Operations Office), US DOT, US EPA, and NRC regulations, IAEA guidelines, and the WHC manuals. It covers activities related to hazardous materials transportation performed on and off the Hanford site under the jurisdictional authority of WHC. (Hazardous materials include radioactive, hazardous waste, and mixed waste.)

  11. Quality Assurance Program Plan for the Hazardous Materials Transportation and Packaging Program. Revision 1

    International Nuclear Information System (INIS)

    Calihan, T.W. III; Votaw, E.F.

    1995-01-01

    This QAPP covers only the implementation accomplished through Level I and II manuals. It covers the quality affecting activities identified in USDOE orders (both HQ and Richland Operations Office), US DOT, US EPA, and NRC regulations, IAEA guidelines, and the WHC manuals. It covers activities related to hazardous materials transportation performed on and off the Hanford site under the jurisdictional authority of WHC. (Hazardous materials include radioactive, hazardous waste, and mixed waste.)

  12. Revised Methods for Characterizing Stream Habitat in the National Water-Quality Assessment Program

    Science.gov (United States)

    Fitzpatrick, Faith A.; Waite, Ian R.; D'Arconte, Patricia J.; Meador, Michael R.; Maupin, Molly A.; Gurtz, Martin E.

    1998-01-01

    Stream habitat is characterized in the U.S. Geological Survey's National Water-Quality Assessment (NAWQA) Program as part of an integrated physical, chemical, and biological assessment of the Nation's water quality. The goal of stream habitat characterization is to relate habitat to other physical, chemical, and biological factors that describe water-quality conditions. To accomplish this goal, environmental settings are described at sites selected for water-quality assessment. In addition, spatial and temporal patterns in habitat are examined at local, regional, and national scales. This habitat protocol contains updated methods for evaluating habitat in NAWQA Study Units. Revisions are based on lessons learned after 6 years of applying the original NAWQA habitat protocol to NAWQA Study Unit ecological surveys. Similar to the original protocol, these revised methods for evaluating stream habitat are based on a spatially hierarchical framework that incorporates habitat data at basin, segment, reach, and microhabitat scales. This framework provides a basis for national consistency in collection techniques while allowing flexibility in habitat assessment within individual Study Units. Procedures are described for collecting habitat data at basin and segment scales; these procedures include use of geographic information system data bases, topographic maps, and aerial photographs. Data collected at the reach scale include channel, bank, and riparian characteristics.

  13. A suggested revision to the specific activity limit for tritiated water transported as LSA-II

    International Nuclear Information System (INIS)

    Nandakumar, A.N.

    2003-01-01

    Tritiated water of specific activity not greater than 0.8 TBq L -1 is classified as LSA-II. This paper demonstrates by some simple calculations that the dose that may result from an accident involving tritiated water of this specific activity is very low and suggests that even if the specific activity limit of tritiated water which may be transported as LSA-II is raised above 0.8 TBq kg -1 , the resulting dose in accident conditions would not be unacceptable. (author)

  14. The principles of radio engineering and antennas. II Antennas (2nd revised and enlarged edition)

    Science.gov (United States)

    Belotserkovskii, G. B.

    This book represents the second part of a textbook for technical schools. The characteristics and parameters of antennas are considered along with transmission lines, the theory of single dipoles and radiator systems, and the technological realization of elements and units of the antenna-feeder system, taking into account filters and multiport networks for microwave communications applications, and ferrite circulators and isolators. The first edition of this textbook was published in 1969. For the current edition, the material in the first edition has been revised, and new material has been introduced. Much attention is given to microwave antennas, including, in particular, arrays with electrical scanning characteristics. Other topics discussed are related to the general principles of antennas, the matching of the impedance of transmission lines, the elements of transmission lines, aperture-type antennas for microwaves, and the functional characteristics of antennas for ultrashort waves.

  15. Full-scale mark II CRT program data report, (5)

    International Nuclear Information System (INIS)

    Kukita, Yutaka; Namatame, Ken; Yamamoto, Nobuo; Takeshita, Isao; Shiba, Masayoshi

    1980-03-01

    The Full-Scale Mark II CRT (Containment Response Test) Program was initiated in 1977 to provide a data base for evaluation of the LOCA hydrodynamic loads for the Mark II pressure suppression system. The test facility is 1/18 in volume and has a wetwell which is a fullscale replica of one 20 0 -sector of that of a reference Mark II. This report documents test data obtained from TEST 2101, which is a medium size (74 mm) water break test performed on April 27, 1979. TEST 2101 was designed to roughly approximate an intermediate break accident in which so-called chugging phenomenon associated with low-flux steam condensation is anticipated to continue for a longer duration than in a large break accident. (author)

  16. Recent operating experiences and programs at EBR-II

    International Nuclear Information System (INIS)

    Lentz, G.L.

    1984-01-01

    Experimental Breeder Reactor No. II (EBR-II) is a pool-type, unmoderated, sodium-cooled reactor with a design power of 62.5 MWt and an electrical generation capability of 20 MW. It has been operated by Argonne National Laboratory for the US government for almost 20 years. During that time, it has operated safely and has demonstrated stable operating characteristics, high availability, and excellent performance of its sodium components. The 20 years of operating experience of EBR-II is a valuable resource to the nuclear community for the development and design of future LMFBR's. Since past operating experience has been extensively reported, this report will focus on recent programs and events

  17. Revised constraints and Belle II sensitivity for visible and invisible axion-like particles

    International Nuclear Information System (INIS)

    Dolan, Matthew J.; Kahlhoefer, Felix

    2017-09-01

    Light pseudoscalars interacting pre-dominantly with Standard Model gauge bosons (so-called axion-like particles or ALPs) occur frequently in extensions of the Standard Model. In this work we review and update existing constraints on ALPs in the keV to GeV mass region from colliders, beam dump experiments and astrophysics. We furthermore provide a detailed calculation of the expected sensitivity of Belle II, which can search for visibly and invisibly decaying ALPs, as well as long-lived ALPs. The Belle II sensitivity is found to be substantially better than previously estimated, covering wide ranges of relevant parameter space. In particular, Belle II can explore an interesting class of dark matter models, in which ALPs mediate the interactions between the Standard Model and dark matter. In these models, the relic abundance can be set via resonant freeze-out, leading to a highly predictive scenario consistent with all existing constraints but testable with single-photon searches at Belle II in the near future.

  18. Revised constraints and Belle II sensitivity for visible and invisible axion-like particles

    Energy Technology Data Exchange (ETDEWEB)

    Dolan, Matthew J. [Melbourne Univ. (Australia). ARC Centre of Excellence for Particle Physics at the Terascale; Ferber, Torben [British Columbia Univ., Vancouver, BC (Canada). Dept. of Physics and Astronomy; Hearty, Christopher [British Columbia Univ., Vancouver, BC (Canada). Dept. of Physics and Astronomy; Institute of Particle Physics, Vancouver, BC (Canada); Kahlhoefer, Felix [Deutsches Elektronen-Synchrotron (DESY), Hamburg (Germany); RWTH Aachen Univ. (Germany). Inst. for Theoretical Particle Physics and Cosmology; Schmidt-Hoberg, Kai [Deutsches Elektronen-Synchrotron (DESY), Hamburg (Germany)

    2017-09-15

    Light pseudoscalars interacting pre-dominantly with Standard Model gauge bosons (so-called axion-like particles or ALPs) occur frequently in extensions of the Standard Model. In this work we review and update existing constraints on ALPs in the keV to GeV mass region from colliders, beam dump experiments and astrophysics. We furthermore provide a detailed calculation of the expected sensitivity of Belle II, which can search for visibly and invisibly decaying ALPs, as well as long-lived ALPs. The Belle II sensitivity is found to be substantially better than previously estimated, covering wide ranges of relevant parameter space. In particular, Belle II can explore an interesting class of dark matter models, in which ALPs mediate the interactions between the Standard Model and dark matter. In these models, the relic abundance can be set via resonant freeze-out, leading to a highly predictive scenario consistent with all existing constraints but testable with single-photon searches at Belle II in the near future.

  19. Phase I Report, US DOE GRED II Program

    Energy Technology Data Exchange (ETDEWEB)

    Fairbank Engineering Ltd.

    2003-04-23

    Noramex Corporation Inc, a Nevada company, owns a 100% interest in geothermal leases at the Blue Mountain Geothermal Area, Humboldt County, Nevada. The company is exploring the site for a geothermal resource suitable for development for electric power generation or In the spring of 2002, Noramex drilled the first geothermal observation hole at Blue Mountain, under a cost-share program with the U.S Department of Energy (DOE), under the DOE's Geothermal Exploration and Resource Definition (GRED) program, (Cooperative Agreement No. DE-FC04-00AL66972). DEEP BLUE No.1 was drilled to a total depth of 672.1 meters (2205 feet) and recorded a maximum temperature of 144.7 C (292.5 F). Noramex Corporation will now drill a second slim geothermal observation test hole at Blue Mountain, designated DEEP BLUE No.2. The hole will be drilled under a cost-share program with the DOE, under the DOE's Geothermal Exploration and Resource Definition II (GRED II) program, (Cooperative Agreement No. DE-FC04-2002AL68297). This report comprises Phase I of Cooperative Agreement No. DE-FC04-2002AL68297 of the GRED II program. The report provides an update on the status of resource confirmation at the Blue Mountain Geothermal Area, incorporating the results from DEEP BLUE No.1, and provides the technical background for a second test hole. The report also outlines the proposed drilling program for slim geothermal observation test hole DEEP BLUE No.2.

  20. Implementasi Program Pembinaan Napi di Lapas Kelas II B Metro

    Directory of Open Access Journals (Sweden)

    Narsidi Narsidi

    2004-01-01

    Full Text Available Penelitian ini bertujuan untuk mengungkap kesiapan sarana fisik dan nonfisik, jenis program pembinaan yang dilaksanakan, proses pelaksanaan program pembinaan, hasil, dan kemanfaatan program bagi narapidana di Lapas. Penelitian ini adalah jenis penelitian studi kasus dengan pendekatan kualitatif fenomenologis naturalistik. Pengumpulan data dilakukan melalui teknik observasi dan wawancara Teknik analisis data menggunakan model analisis interaktif dari Miles dan Huberman (1984. Hasil analisis data menunjukkan, bahwa Lapas Kelas II B Metro secara nonfisik masih memiliki kekurangan, baik kuantitas maupun kualitas. Proses pembinaan narapidana di Lapas belum banyak mengadopsi teori pembelajaran orang dewasa sehingga model pembelajarannya masih cenderung menggunakan model pembelajaran anak-anak (paedagogik. Secara umum dapat dikatakan bahwa pembinaan yang dilakukan Lapas dirasakan kemanfaatannya oleh narapidana.Namun, pembinaan yang dilakukan belum dapat memenuhi minat dan kebutuhan narapidana. Kata kunci: implementasi, program, pembinaan, narapidana.

  1. Security programs for Category I or II nuclear material or certain nuclear facilities. Regulatory guide G-274

    International Nuclear Information System (INIS)

    2003-03-01

    The purpose of this regulatory guide is to help applicants for a Canadian Nuclear Safety Commission (CNSC) licence in respect of Category I or II nuclear material - other than a licence to transport - , or a nuclear facility consisting of a nuclear reactor that may exceed 10 MW thermal power during normal operation, prepare and submit the security information to be included with the application, pursuant to the Nuclear Safety and Control Act (NSCA). Category I and II nuclear material are defined in Appendix B to this guide. This guide describes: the security information that should typically be included with the application for any licence referred to above; how the security information may be organized and presented in a separate document (hereinafter 'the security program description'), in order to assist CNSC review and processing of the application; and, the administrative procedures to be followed when preparing, submitting or revising the security program description. (author)

  2. FY 1981 HTGR program summary-level program outline (revision 1/30/81)

    International Nuclear Information System (INIS)

    1981-01-01

    The objective of the DOE HTGR Program is the development of technology for the most important HTGR applications. Through this support, DOE seeks to encourage private sector initiatives which will lead to the development of commercially attractive HTGR applications that concurrently support national energy goals. Currently perceived as important to national energy goals are applications that primarily address the process heat market with a view toward reduction of national requirements for oil, natural gas and coal. A high priority during FY 1981, therefore, will be to further identify and define the details of the Technology Program so as to assure that it is both necessary and sufficient to provide the required support. In the establishment of a supportive Technology Program, key elements which will be addressed are as follows: studies will be conducted to further identify and characterize important unique HTGR applications and to evaluate their potential in the context of market opportunities, utility/user interest, and national objectives to develop new energy supply options; based upon the configurations and operating characteristics projected for selected applications, Technology Program requirements must be identified to support development, verification, and ultimately licensing of components and systems comprising the facilities of interest; and in the context of limited resources, sufficient analysis and evaluation must be accomplished so as to prioritize technology elements in accordance with appropriately developed criteria

  3. Guidance document for revision of DOE Order 5820.2A, Radioactive Waste Technical Support Program

    International Nuclear Information System (INIS)

    Kudera, D.E.; McMurtrey, C.D.; Meagher, B.G.

    1993-04-01

    This document provides guidance for the revision of DOE Order 5820.2A, ''Radioactive Waste Management.'' Technical Working Groups have been established and are responsible for writing the revised order. The Technical Working Groups will use this document as a reference for polices and procedures that have been established for the revision process. The overall intent of this guidance is to outline how the order will be revised and how the revision process will be managed. In addition, this document outlines technical issues considered for inclusion by a Department of Energy Steering Committee

  4. A revision of the genus Muricea Lamouroux, 1821 (Anthozoa, Octocorallia) in the eastern Pacific. Part II.

    Science.gov (United States)

    Breedy, Odalisca; Guzman, Hector M

    2016-01-01

    The species of the genus Muricea were mainly described from 1846 to 1870. After that very few contributions were published. Although the highest richness of Muricea species is in the eastern Pacific shallow waters, a comprehensive systematic study of the genus does not exist. Recently we started a taxonomic review of the genus in order to validate the status of four species previously included in the genus Eumuricea. Herein we present the second part of the Muricea revision dealing with the species-group characterised by shelf-like calyces instead of tubular-like calyces (the Muricea squarrosa-group). Original type material was morphologically analysed and illustrated using optical and scanning electron microscopy. Comparative character tables are provided for the genus. The taxonomic status of the species was analysed and established by designating lectotypes, alternatively by recognising a holotype by monotypy. We conclude that the genus Muricea comprises 20 valid species, including the previous four in the Muricea squarrosa-group. We propose 10 lectotypes, a new combination and three more species groups for the genus based on morphology: the Muricea fruticosa-group, Muricea plantaginea-group and Muricea austera-group.

  5. Fire Protection Program fiscal year 1996, site support program plan Hanford Fire Department. Revision 2

    International Nuclear Information System (INIS)

    Good, D.E.

    1995-09-01

    The mission of the Hanford Fire Department (HFD) is to support the safe and timely cleanup of the Hanford site by providing fire suppression, fire prevention, emergency rescue, emergency medical service, and hazardous materials response; and to be capable of dealing with and terminating emergency situations which could threaten the operations, employees, or interest of the US Department of Energy operated Hanford Site. This includes response to surrounding fire departments/districts under a mutual aid agreement and contractual fire fighting, hazardous materials, and ambulance support to Washington Public Power Supply System (Supply System). The fire department also provides site fire marshal overview authority, fire system testing and maintenance, self-contained breathing apparatus maintenance, building tours and inspections, ignitable and reactive waste site inspections, prefire planning, and employee fire prevention education. This report gives a program overview, technical program baselines, and cost and schedule baseline

  6. Kilowatt isotope power system. Phase II plan. Volume I. Phase II program plan

    International Nuclear Information System (INIS)

    1978-01-01

    The development of a Kilowatt Isotope Power System (KIPS) was begun in 1975 for the purpose of satisfying the power requirements of satellites in the 1980's. The KIPS is a 238 PuO 2 -fueled organic Rankine cycle turbine power system to provide a design output of 500 to 2000 W. Phase II of the overall 3-phase KIPS program is described. This volume presents a program plan for qualifying the organic Rankine power system for flight test in 1982. The program plan calls for the design and fabrication of the proposed flight power system; conducting a development and a qualification program including both environmental and endurance testing, using an electrical and a radioisotope heat source; planning for flight test and spacecraft integration; and continuing ground demonstration system testing to act as a flight system breadboard and to accumulate life data

  7. Performance Demonstration Program Plan for Nondestructive Assay for the TRU Waste Characterization Program. Revision 1

    International Nuclear Information System (INIS)

    1997-01-01

    The Performance Demonstration Program (PDP) for Nondestructive Assay (NDA) consists of a series of tests conducted on a regular frequency to evaluate the capability for nondestructive assay of transuranic (TRU) waste throughout the Department of Energy (DOE) complex. Each test is termed a PDP cycle. These evaluation cycles provide an objective measure of the reliability of measurements performed with TRU waste characterization systems. Measurement facility performance will be demonstrated by the successful analysis of blind audit samples according to the criteria set by this Program Plan. Intercomparison between measurement groups of the DOE complex will be achieved by comparing the results of measurements on similar or identical blind samples reported by the different measurement facilities. Blind audit samples (hereinafter referred to as PDP samples) will be used as an independent means to assess the performance of measurement groups regarding compliance with established Quality Assurance Objectives (QAOs). As defined for this program, a PDP sample consists of a 55-gallon matrix drum emplaced with radioactive standards and fabricated matrix inserts. These PDP sample components, once manufactured, will be secured and stored at each participating measurement facility designated and authorized by Carlsbad Area Office (CAO) under secure conditions to protect them from loss, tampering, or accidental damage

  8. 77 FR 801 - National Vaccine Injury Compensation Program: Revised Amount of the Average Cost of a Health...

    Science.gov (United States)

    2012-01-06

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Health Resources and Services Administration National Vaccine Injury Compensation Program: Revised Amount of the Average Cost of a Health Insurance Policy The Health Resources and Services Administration (HRSA) is publishing an updated monetary amount of the average cost of a health insurance policy as it...

  9. 40 CFR 3.1000 - How does a state, tribe, or local government revise or modify its authorized program to allow...

    Science.gov (United States)

    2010-07-01

    ... government revise or modify its authorized program to allow electronic reporting? 3.1000 Section 3.1000... government revise or modify its authorized program to allow electronic reporting? (a) A state, tribe, or local government that receives or plans to begin receiving electronic documents in lieu of paper...

  10. DECOVALEX II PROJECT. Technical report - Task 2A and 2B. (Revised edition)

    International Nuclear Information System (INIS)

    Lanru Jing; Stephansson, Ove

    1998-08-01

    DECOVALEX II project started in November 1995 as a continuation of the DECOVALEX I project, which was completed at the end of 1994. The project was initiated by recognizing the fact that a proper evaluation of the current capacities of numerical modelling of the coupled T-H-M processes in fractured media is needed not only for small scale, well controlled laboratory test cases such as those studied in DECOVALEX 1, but also for less characterised, more complex and realistic in-situ experiments. This will contribute to validation and confidence building in the current mathematical models, numerical methods and computer codes. Four tasks were defined in the DECOVALEX II project: TASK 1 - numerical study of the RCF3 pumping test and shaft excavation at Sellafield by Nirex, UK; TASK 2 - numerical study of the in-situ T-H-M experiments at Kamaishi Mine by PNC, Japan; TASK 3 - review of current state-of-the-art of rock joint research and TASK 4 - report on the coupled T-H-M issues related to repository design and performance assessment. This report is one of the technical reports of the DECOVALEX II project, describing the work performed for TASK 2A and 2B - the predictions and model calibration for the hydro-mechanical effect of the excavation of the test pit for the in-situ T-H-M experiments at Kamaishi Mine by PNC, Japan. Presented in this report are the descriptions of the project, definition of Task 2, and approaches, methods and results of numerical modelling work carried out by the research teams. The report is a summary of the research reports written by the research teams and the discussions held during project workshops and task force group meetings. The opinions and conclusions in this report, however, reflect only ideas of the authors, not necessarily a collective representation of the funding organisations of the project

  11. Revision of the Bee Genus Chlerogella (Hymenoptera, Halictidae, Part II: South American Species and Generic Diagnosis

    Directory of Open Access Journals (Sweden)

    Michael Engel

    2010-05-01

    Full Text Available The South American species of the rare bee genus Chlerogella Michener (Halictinae: Augochlorini are revised, completing the study of the genus. Chlerogella diversity is significantly expanded beyond the five previously described South American species of Cherlogella azurea (Enderlein, comb. n., C. nasus (Enderlein, C. mourella Engel, C. octogesima (Brooks & Engel, comb. n., and C. buyssoni (Vachal. Twenty-two new species are described – C. agaylei sp. n., C. arhyncha sp. n., C. borysthenis sp. n., C. breviceps sp. n., C. cochabambensis sp. n., C. cooperella sp. n., C. cyranoi sp. n., C. dolichorhina sp. n., C. elysia sp. n., C. eumorpha sp. n., C. euprepia sp. n., C. hauseri sp. n., C. hypermeces sp. n., C. materdonnae sp. n., C. oresbios sp. n., C. picketti sp. n., C. rostrata sp. n., C. silvula sp. n., C. terpsichore sp. n., C. tychoi sp. n., C. vachali sp. n., C. xuthopleura sp. n. – and the distribution of the genus is expanded beyond Perú and Ecuador to include Bolivia, Colombia, and Venezuela. The female of C. azurea is described for the first time while the placement of Halictus buyssoni Vachal in Chlerogella is considered tentative, following the usage of previous authors, as the holotype and sole specimen is untraceable. The genus is newly diagnosed based on a greater understanding of variation in malar length across the species and a dichotomous key is provided. New floral records for species of Chlerogella include Psychotria pongoana Standl. (Rubiaceae and a putative record on Phragmopedium longifolium (Warsz. & Rchb.f. Rolfe (Orchidaceae.

  12. Facility Decontamination and Decommissioning Program Surveillance and Maintenance Plan, Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Poderis, Reed J. [NSTec; King, Rebecca A. [NSTec

    2013-09-30

    This Surveillance and Maintenance (S&M) Plan describes the activities performed between deactivation and final decommissioning of the following facilities located on the Nevada National Security Site, as documented in the Federal Facility Agreement and Consent Order under the Industrial Sites program as decontamination and decommissioning sites: ? Engine Maintenance, Assembly, and Disassembly (EMAD) Facility: o EMAD Building (Building 25-3900) o Locomotive Storage Shed (Building 25-3901) ? Test Cell C (TCC) Facility: o Equipment Building (Building 25-3220) o Motor Drive Building (Building 25-3230) o Pump Shop (Building 25-3231) o Cryogenic Lab (Building 25-3232) o Ancillary Structures (e.g., dewars, water tower, piping, tanks) These facilities have been declared excess and are in various stages of deactivation (low-risk, long-term stewardship disposition state). This S&M Plan establishes and implements a solid, cost-effective, and balanced S&M program consistent with federal, state, and regulatory requirements. A graded approach is used to plan and conduct S&M activities. The goal is to maintain the facilities in a safe condition in a cost-effective manner until their final end state is achieved. This plan accomplishes the following: ? Establishes S&M objectives and framework ? Identifies programmatic guidance for S&M activities to be conducted by National Security Technologies, LLC, for the U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office (NNSA/NFO) ? Provides present facility condition information and identifies hazards ? Identifies facility-specific S&M activities to be performed and their frequency ? Identifies regulatory drivers, NNSA/NFO policies and procedures, and best management practices that necessitate implementation of S&M activities ? Provides criteria and frequencies for revisions and updates ? Establishes the process for identifying and dispositioning a condition that has not been previously identified or

  13. International Performance Measurement & Verification Protocol: Concepts and Practices for Improved Indoor Environmental Quality, Volume II (Revised)

    Energy Technology Data Exchange (ETDEWEB)

    2002-03-01

    This protocol serves as a framework to determine energy and water savings resulting from the implementation of an energy efficiency program. It is also intended to help monitor the performance of renewable energy systems and to enhance indoor environmental quality in buildings.

  14. Super Energy Savings Performance Contracts: Federal Energy Management Program (FEMP) Program Overview (revision)

    International Nuclear Information System (INIS)

    Pitchford, P.

    2001-01-01

    This four-page publication describes the U.S. Department of Energy's (DOE's) streamlined energy savings performance contracting, or ''Super ESPC,'' process, which is managed by DOE's Federal Energy Management Program (FEMP). Under a Super ESPC, a qualifying energy service company (ESCO) from the private sector pays for energy efficiency improvements or advanced renewable energy technologies (e.g., photovoltaic systems, wind turbines, or geothermal heat pumps, among others) for a facility of a government agency. The ESCO is then repaid over time from the agency's resulting energy cost savings. Delivery orders under these contracts specify the level of performance (energy savings) and the repayment schedule; the contract term can be up to 25 years, although many Super ESPCs are for about 10 years or less

  15. Cement augmentation in the proximal femur to prevent stem subsidence in revision hip arthroplasty with Paprosky type II/IIIa defects

    Directory of Open Access Journals (Sweden)

    Shang-Wen Tsai

    2018-06-01

    Full Text Available Background: Subsidence remains a common complication after revision hip arthroplasty which may lead to prolonged weight-bearing restrictions, leg-length discrepancies or considerable loss of function. We evaluated the effectiveness of cement augmentation in the proximal femoral metaphysis during a revision of femoral components to prevent post-operative stem subsidence. Methods: Forty patients were enrolled. Follow-up averaged 67.7 months (range: 24–149. Twenty-seven patients had a Paprosky type II defect and 13 had a type IIIa defect. All revision hip arthroplasty used a cementless, cylindrical, non-modular cobalt–chromium stem. The defect in the metaphysis was filled with antibiotic-loaded bone cement. Thirteen patients who had undergone stem revision only was allowed to walk immediately without weight-bearing restrictions. Twenty-seven patients who had undergone revision total hip arthroplasty was allowed partial weight-bearing within 6 weeks after surgery in the consideration of acetabular reconstruction. Results: Three patients (7.5% had post-surgery stem subsidences of three mm, five mm, and 10 mm, respectively, at three, one, and 14 months. There were no acute surgical site infections. There were three femoral stem failures: two delayed infections and one periprosthetic Vancouver B2 fracture. Both five- and 10-year survivorships of the femoral implant were 90.1%. Conclusion: An adequate length of the scratch-fit segment and diaphyseal ingrowth remain of paramount importance when revising femoral components. To fill metaphyseal bone defects with antibiotic-loaded bone cement may be an alternative method in dealing with proximal femoral bone loss during a femoral revision. Keywords: Bone defect, Cement augmentation, Femur, Revision hip arthroplasty, Subsidence

  16. PROSID - a program to evaluate SIMMER-II results

    International Nuclear Information System (INIS)

    Flad, M.; Kuefner, K.; Maschek, W.

    1990-02-01

    The PROSID program supports the evaluation of SIMMER-II results. PROSID enables the user to get a printout of variables, to get a linear combination of variables or quadrats of variables, to sum up variables or quadrats of variables, to compare variables or whole datasets, to interpolate to a new meshgrid and to get weighted mean values. As special options are available the calculation of the volume of connected gas regions, the evaluation of the fuel enrichment, an estimation of reactivity changes and the retransformation of interpolated velocity values. The results can be stored for further evaluations. (orig.) [de

  17. Spectroscopic properties of reaction center pigments in photosystem II core complexes: revision of the multimer model.

    Science.gov (United States)

    Raszewski, Grzegorz; Diner, Bruce A; Schlodder, Eberhard; Renger, Thomas

    2008-07-01

    Absorbance difference spectra associated with the light-induced formation of functional states in photosystem II core complexes from Thermosynechococcus elongatus and Synechocystis sp. PCC 6803 (e.g., P(+)Pheo(-),P(+)Q(A)(-),(3)P) are described quantitatively in the framework of exciton theory. In addition, effects are analyzed of site-directed mutations of D1-His(198), the axial ligand of the special-pair chlorophyll P(D1), and D1-Thr(179), an amino-acid residue nearest to the accessory chlorophyll Chl(D1), on the spectral properties of the reaction center pigments. Using pigment transition energies (site energies) determined previously from independent experiments on D1-D2-cytb559 complexes, good agreement between calculated and experimental spectra is obtained. The only difference in site energies of the reaction center pigments in D1-D2-cytb559 and photosystem II core complexes concerns Chl(D1). Compared to isolated reaction centers, the site energy of Chl(D1) is red-shifted by 4 nm and less inhomogeneously distributed in core complexes. The site energies cause primary electron transfer at cryogenic temperatures to be initiated by an excited state that is strongly localized on Chl(D1) rather than from a delocalized state as assumed in the previously described multimer model. This result is consistent with earlier experimental data on special-pair mutants and with our previous calculations on D1-D2-cytb559 complexes. The calculations show that at 5 K the lowest excited state of the reaction center is lower by approximately 10 nm than the low-energy exciton state of the two special-pair chlorophylls P(D1) and P(D2) which form an excitonic dimer. The experimental temperature dependence of the wild-type difference spectra can only be understood in this model if temperature-dependent site energies are assumed for Chl(D1) and P(D1), reducing the above energy gap from 10 to 6 nm upon increasing the temperature from 5 to 300 K. At physiological temperature, there are

  18. Phase II Transport Model of Corrective Action Unit 98: Frenchman Flat, Nevada Test Site, Nye County, Nevada, Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Gregg Ruskuaff

    2010-01-01

    This document, the Phase II Frenchman Flat transport report, presents the results of radionuclide transport simulations that incorporate groundwater radionuclide transport model statistical and structural uncertainty, and lead to forecasts of the contaminant boundary (CB) for a set of representative models from an ensemble of possible models. This work, as described in the Federal Facility Agreement and Consent Order (FFACO) Underground Test Area (UGTA) strategy (FFACO, 1996; amended 2010), forms an essential part of the technical basis for subsequent negotiation of the compliance boundary of the Frenchman Flat corrective action unit (CAU) by Nevada Division of Environmental Protection (NDEP) and National Nuclear Security Administration Nevada Site Office (NNSA/NSO). Underground nuclear testing via deep vertical shafts was conducted at the Nevada Test Site (NTS) from 1951 until 1992. The Frenchman Flat area, the subject of this report, was used for seven years, with 10 underground nuclear tests being conducted. The U.S. Department of Energy (DOE), NNSA/NSO initiated the UGTA Project to assess and evaluate the effects of underground nuclear tests on groundwater at the NTS and vicinity through the FFACO (1996, amended 2010). The processes that will be used to complete UGTA corrective actions are described in the “Corrective Action Strategy” in the FFACO Appendix VI, Revision No. 2 (February 20, 2008).

  19. 78 FR 70225 - West Virginia: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2013-11-25

    ... 04. 45-25-1.1.a, 45-25- Trucks, Revision Checklist 1.5.a/Table 25-A, 205. Item 9. RCRA Cluster XV...- Pigments, and Food, Drug, and 70 FR 35032, 6/ 10.1. Cosmetic Colorants, Revision 16/05. Checklist 206...

  20. 78 FR 54178 - Virginia: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2013-09-03

    ... XIX Academic Laboratories 73 FR 72912, 9 VAC Sec. Sec. 20- Generator Standards, Revision December 1... 17, 60-18, 20-60-261 A, Hazardous Constituents, 2010. 20-60-268 A. Revision Checklist 225. Academic... steps to eliminate drafting errors and ambiguity, minimize potential litigation, and provide a clear...

  1. Idaho National Engineering Laboratory (INEL) Environmental Restoration Program (ERP), Baseline Safety Analysis File (BSAF). Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-20

    This document was prepared to take the place of a Safety Evaluation Report since the Baseline Safety Analysis File (BSAF)and associated Baseline Technical Safety Requirements (TSR) File do not meet the requirements of a complete safety analysis documentation. Its purpose is to present in summary form the background of how the BSAF and Baseline TSR originated and a description of the process by which it was produced and approved for use in the Environmental Restoration Program.The BSAF is a facility safety reference document for INEL environmental restoration activities including environmental remediation of inactive waste sites and decontamination and decommissioning (D&D) of surplus facilities. The BSAF contains safety bases common to environmental restoration activities and guidelines for performing and documenting safety analysis. The common safety bases can be incorporated by reference into the safety analysis documentation prepared for individual environmental restoration activities with justification and any necessary revisions. The safety analysis guidelines in BSAF provide an accepted method for hazard analysis; analysis of normal, abnormal, and accident conditions; human factors analysis; and derivation of TSRS. The BSAF safety bases and guidelines are graded for environmental restoration activities.

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

    International Nuclear Information System (INIS)

    2003-01-01

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

  3. Idaho National Engineering Laboratory (INEL) Environmental Restoration Program (ERP), Baseline Safety Analysis File (BSAF). Revision 1

    International Nuclear Information System (INIS)

    1994-01-01

    This document was prepared to take the place of a Safety Evaluation Report since the Baseline Safety Analysis File (BSAF)and associated Baseline Technical Safety Requirements (TSR) File do not meet the requirements of a complete safety analysis documentation. Its purpose is to present in summary form the background of how the BSAF and Baseline TSR originated and a description of the process by which it was produced and approved for use in the Environmental Restoration Program.The BSAF is a facility safety reference document for INEL environmental restoration activities including environmental remediation of inactive waste sites and decontamination and decommissioning (D ampersand D) of surplus facilities. The BSAF contains safety bases common to environmental restoration activities and guidelines for performing and documenting safety analysis. The common safety bases can be incorporated by reference into the safety analysis documentation prepared for individual environmental restoration activities with justification and any necessary revisions. The safety analysis guidelines in BSAF provide an accepted method for hazard analysis; analysis of normal, abnormal, and accident conditions; human factors analysis; and derivation of TSRS. The BSAF safety bases and guidelines are graded for environmental restoration activities

  4. Steam generator tube integrity program: Phase II, Final report

    Energy Technology Data Exchange (ETDEWEB)

    Kurtz, R.J.; Bickford, R.L.; Clark, R.A.; Morris, C.J.; Simonen, F.A.; Wheeler, K.R.

    1988-08-01

    The Steam Generator Tube Integrity Program (SGTIP) was a three phase program conducted for the US Nuclear Regulatory Commission (NRC) by Pacific Northwest Laboratory (PNL). The first phase involved burst and collapse testing of typical steam generator tubing with machined defects. The second phase of the SGTIP continued the integrity testing work of Phase I, but tube specimens were degraded by chemical means rather than machining methods. The third phase of the program used a removed-from-service steam generator as a test bed for investigating the reliability and effectiveness of in-service nondestructive eddy-current inspection methods and as a source of service degraded tubes for validating the Phase I and Phase II data on tube integrity. This report describes the results of Phase II of the SGTIP. The object of this effort included burst and collapse testing of chemically defected pressurized water reactor (PWR) steam generator tubing to validate empirical equations of remaining tube integrity developed during Phase I. Three types of defect geometries were investigated: stress corrosion cracking (SCC), uniform thinning and elliptical wastage. In addition, a review of the publicly available leak rate data for steam generator tubes with axial and circumferential SCC and a comparison with an analytical leak rate model is presented. Lastly, nondestructive eddy-current (EC) measurements to determine accuracy of defect depth sizing using conventional and alternate standards is described. To supplement the laboratory EC data and obtain an estimate of EC capability to detect and size SCC, a mini-round robin test utilizing several firms that routinely perform in-service inspections was conducted.

  5. Steam generator tube integrity program: Phase II, Final report

    International Nuclear Information System (INIS)

    Kurtz, R.J.; Bickford, R.L.; Clark, R.A.; Morris, C.J.; Simonen, F.A.; Wheeler, K.R.

    1988-08-01

    The Steam Generator Tube Integrity Program (SGTIP) was a three phase program conducted for the US Nuclear Regulatory Commission (NRC) by Pacific Northwest Laboratory (PNL). The first phase involved burst and collapse testing of typical steam generator tubing with machined defects. The second phase of the SGTIP continued the integrity testing work of Phase I, but tube specimens were degraded by chemical means rather than machining methods. The third phase of the program used a removed-from-service steam generator as a test bed for investigating the reliability and effectiveness of in-service nondestructive eddy-current inspection methods and as a source of service degraded tubes for validating the Phase I and Phase II data on tube integrity. This report describes the results of Phase II of the SGTIP. The object of this effort included burst and collapse testing of chemically defected pressurized water reactor (PWR) steam generator tubing to validate empirical equations of remaining tube integrity developed during Phase I. Three types of defect geometries were investigated: stress corrosion cracking (SCC), uniform thinning and elliptical wastage. In addition, a review of the publicly available leak rate data for steam generator tubes with axial and circumferential SCC and a comparison with an analytical leak rate model is presented. Lastly, nondestructive eddy-current (EC) measurements to determine accuracy of defect depth sizing using conventional and alternate standards is described. To supplement the laboratory EC data and obtain an estimate of EC capability to detect and size SCC, a mini-round robin test utilizing several firms that routinely perform in-service inspections was conducted

  6. The Revised WIPP Passive Institutional Controls Program - A Conceptual Plan - 13145

    International Nuclear Information System (INIS)

    Patterson, Russ; Klein, Thomas; Van Luik, Abraham

    2013-01-01

    with the international guidance being developed. International guidance currently under development may suggest that the inter-generational equity principle strives to warn the future, however, in doing so not to unduly burden present generations. Building markers and monuments that are out of proportion to the risk being presented to the future is not in keeping with generational equity. With this in mind the DOE/CBFO is developing conceptual plans for re-evaluating and revising the current WIPP PIC's program. These conceptual plans will suggest scientific and technical work that must be completed to develop a 'new' PICs program that takes the best ideas of the present plan, blended with new ideas from the RK and M project, and proposed alternative permanent markers designs and materials in consideration. (authors)

  7. Y-12 Groundwater Protection Program Groundwater Monitoring Data Compendium, Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    None

    2006-12-01

    This document is a compendium of water quality and hydrologic characterization data obtained through December 2005 from the network of groundwater monitoring wells and surface water sampling stations (including springs and building sumps) at the U.S. Department of Energy (DOE) Y-12 National Security Complex (Y-12) in Oak Ridge, Tennessee that have been sampled since January 2003. The primary objectives of this document, hereafter referenced as the Y-12 Groundwater Protection Program (GWPP) Compendium, are to: (1) Serve as a single-source reference for monitoring data that meet the requirements of the Y-12 GWPP, as defined in the Y-12 GWPP Management Plan (BWXT Y-12 L.L.C. [BWXT] 2004); (2) Maintain a detailed analysis and evaluation of the monitoring data for each applicable well, spring, and surface water sampling station, with a focus on results for the primary inorganic, organic, and radiological contaminants in groundwater and surface water at Y-12; and (3) Ensure retention of ''institutional knowledge'' obtained over the long-term (>20-year) history of groundwater and surface water monitoring at Y-12 and the related sources of groundwater and surface water contamination. To achieve these goals, the Y-12 GWPP Compendium brings together salient hydrologic, geologic, geochemical, water-quality, and environmental compliance information that is otherwise disseminated throughout numerous technical documents and reports prepared in support of completed and ongoing environmental contamination assessment, remediation, and monitoring activities performed at Y-12. The following subsections provide background information regarding the overall scope and format of the Y-12 GWPP Compendium and the planned approach for distribution and revision (i.e., administration) of this ''living'' document.

  8. VASCOMP 2. The V/STOL aircraft sizing and performance computer program. Volume 6: User's manual, revision 3

    Science.gov (United States)

    Schoen, A. H.; Rosenstein, H.; Stanzione, K.; Wisniewski, J. S.

    1980-01-01

    This report describes the use of the V/STOL Aircraft Sizing and Performance Computer Program (VASCOMP II). The program is useful in performing aircraft parametric studies in a quick and cost efficient manner. Problem formulation and data development were performed by the Boeing Vertol Company and reflects the present preliminary design technology. The computer program, written in FORTRAN IV, has a broad range of input parameters, to enable investigation of a wide variety of aircraft. User oriented features of the program include minimized input requirements, diagnostic capabilities, and various options for program flexibility.

  9. Next Generation Nuclear Plant Materials Research and Development Program Plan, Revision 3

    International Nuclear Information System (INIS)

    G.O. Hayner; R.L. Bratton; R.E. Mizia; W.E. Windes; W.R. Corwin; T.D. Burchell; C.E. Duty; Y. Katoh; J.W. Klett; T.E. McGreevy; R.K. Nanstad; W. Ren; P.L. Rittenhouse; L.L. Snead; R.W. Swindeman; D.F. Wlson

    2006-01-01

    This is the 2006 update (Revision 3) of the NGNP Materials Research and Development Program Plan. This law established that the U.S Department of Energy (DOE) Secretary of Energy shall establish a ''Next Generation Nuclear Plant'' (NGNP) project. The NGNP project named in the Act was given the following attributes and guiding principles to manage its development: (1) The NGNP consists of research, development, design (R and DD), construction, and operation of a prototype reactor to generate electricity and hydrogen; (2) The project shall be managed by the DOE Office of Nuclear Energy; (3) The Idaho National Laboratory (INL) shall be the lead DOE laboratory for the NGNP; (4) The INL shall establish collaborations with selected institutions of higher education, other research institutes and international researchers; (5) The INL shall organize an industrial consortium of partners for cost-shared R and DD, construction; (6) The project shall be sited at the INL; (7) The project shall be licensed by the Nuclear Regulatory Commission (NRC) and by July, 2008 the NRC and DOE shall jointly submit a licensing strategy to Congress; (8) The project shall be organized to maximize technical interchange with the nuclear power industry, nuclear power plant construction firms, the chemical process industry and to seek international cooperation, participation and contributions; (9) The Nuclear Energy Research Advisory Committee (NERAC) shall review all program plans for the NGNP; (10) Phase 1 of the project (selection of hydrogen production technology, conduct R and DD and initial design activities) shall be completed no later than September 30, 2011; (11) Phase 2 of the project (continue R and DD, develop final design, apply for a license, construct and start operations) shall be completed by September 30, 2021; and (12) Provision for authorization of appropriations was made. As a result of the direction provided, the INL and the DOE issued an NGNP Preliminary Project Management

  10. 78 FR 47697 - Public Water System Supervision Program Revision for the State of Louisiana

    Science.gov (United States)

    2013-08-06

    ...: 1) Long Term 2 Enhanced Surface Water Treatment Rule (LT2), 2) the Stage 2 Disinfectants and Disinfection Byproducts Rule (DBP2), and 3) the Lead and Copper Rule Short-Term Revisions and Clarifications...: Louisiana Department of Health and Hospitals, Office of Public Health, Bienville Building, 628 4th Street...

  11. 77 FR 47779 - Arkansas: Final Authorization of State Hazardous Waste Management Program Revision

    Science.gov (United States)

    2012-08-10

    ... Protection Agency (EPA). ACTION: Direct final rule. SUMMARY: Arkansas has applied to the EPA for Final..., Arkansas Department of Pollution Control and Ecology (ADPC&E), revised its Regulation Number 23 from one of... Ecology Commission Regulation Number 23 (Hazardous Waste Management), adopted on April 25, 2008 and April...

  12. 77 FR 50617 - Pesticide Tolerance Crop Grouping Program III; Revisions to General Tolerance Regulations

    Science.gov (United States)

    2012-08-22

    ... American Pistachio Growers trade association. III. Response to Comments In this section, EPA describes the.... EPA received one comment from the American Pistachio Growers trade association that supported including pistachio in the revised tree nut crop group. They noted that including pistachio will...

  13. 78 FR 74229 - Medicare Program; Revisions to Payment Policies Under the Physician Fee Schedule, Clinical...

    Science.gov (United States)

    2013-12-10

    ... MFP Multi-Factor Productivity MGMA Medical Group Management Association MIEA-TRHCA The Medicare... 69624), we revised the methodology for calculating direct PE RVUs from the top- down to the bottom-up... Based on RVUs To calculate the payment for each physicians' service, the components of the fee schedule...

  14. PODESY program for flux mapping of CNA II reactor:

    International Nuclear Information System (INIS)

    Ribeiro Guevara, Sergio

    1988-01-01

    The PODESY program, developed by KWU, calculates the spatial flux distribution of CNA II reactor through a three-dimensional expansion of 90 incore detector measurements. The calculation is made in three steps: a) short-term calculation which considers the control rod positions and it has to be done each time the flux mapping is calculated; b) medium-term calculation which includes local burn-up dependent calculation made by diffusion methods in macro-cell configurations (seven channels in hexagonal distribution), and c) long-term calculation, or macroscopic flux determination, that is a fitting and expansion of measured fluxes, previously corrected by local effects, using the eigen functions of the modified diffusion equation. The paper outlines development of step (c) of the calculation. The incore detectors have been located in the central zone of the core. In order to obtain low errors in the expansion procedure it is necessary to include additional points, whose flux values are assumed to be equivalent to detector measurements. These flux values are calculated with detector measurements and a spatial flux distribution calculated by a PUMA code. This PUMA calculation employs a smooth burn-up distribution (local burn-up variations are considered in step (b) of the whole calculation) representing the state of core evolution at the calculation time. The core evolution referred to ends when the equilibrium core condition is reached. Additionally, a calculation method to be employed in the plant in case of incore detector failures, is proposed. (Author) [es

  15. PEP-II Large Power Supplies Rebuild Program at SLAC

    CERN Document Server

    de Lira, Antonio C; Lipari, James J; da Silva Rafael, Fernando

    2005-01-01

    At PEP-II, seven large power supplies (LGPS) are used to power quad magnets in the electron-positron collider region. The LGPS ratings range from 72kW to 270kW, and were installed in 1997. They are unipolar off-line switch mode supplies, with a 6 pulse bridge rectifying 480VAC, 3-phase input power to yield 650VDC unregulated. This unregulated 650VDC is then input into one (or two) IGBT H-bridges, which convert the DC into PWM 16 kHz square wave AC. This high frequency AC drives the primary side of a step-down transformer followed by rectifiers and low pass filters. Over the years, these LGPS have presented many problems mainly in their control circuits, making it difficult to troubleshoot and affecting the overall accelerator availability. A redesign/rebuilding program for these power supplies was established under the coordination of the Power Conversion Department at SLAC. During the 2004 accelerator summer shutdown all the control circuits in these supplies were redesigned and replaced. A new PWM control b...

  16. 40 CFR 147.2551 - State-administered program-Class II wells.

    Science.gov (United States)

    2010-07-01

    ..., “Re: Application for Primacy in the Regulation of Class II Injection Wells,” March 8, 1982; (5) Letter... Class II Injection Wells under Section 1425 of the Safe Drinking Water Act,” November 1981; (2) Letter...) WATER PROGRAMS (CONTINUED) STATE, TRIBAL, AND EPA-ADMINISTERED UNDERGROUND INJECTION CONTROL PROGRAMS...

  17. National Registry of Cardiac Rehabilitation Programs in Mexico II (RENAPREC II).

    Science.gov (United States)

    Ilarraza-Lomelí, Hermes; García-Saldivia, Marianna; Rojano-Castillo, Jessica; Justiniano, Samuel; Cerón, Norma; Aranda-Ayala, Zulema-L; Rodríguez, Azucena; Hernández, Alejandro; Cassaigne, María-Elena; Cantero, Raúl; Gasca, Pablo; Hinojosa, Tania; Alonso, Jesús; Romo, Ricardo; Lara, Jorge; Pimentel, Elizabeth; Zavala, Juana; Rius-Suárez, María-Dolores; Cherebetiu, Gabriel; Cortés, Othniel; Almaraz, Alejandro; Mendoza, Pedro; Silva, Jesús; Tirado, Enrique; Martínez, Leonel

    The aim of this paper is to compare the state of Cardiac Rehabilitation Programs (CRP) in 2009 with 2015. Focus is directed on health care, training of health-providers, research, and the barriers to their implementation. All authors of RENAPREC-2009, and other cardiac rehabilitation leaders in Mexico were requested to participate. These centres were distributed into two groups: RENAPREC-2009 centres that participated in 2015, and the new CRP units. In 2009 there were 14 centres, two of which disappeared and another two did not respond. CRP-units increased by 71% (n=24), and their geographic distribution shows a centripetal pattern. The coverage of CRP-units was 0.02 centres per 100,000 inhabitants. Only 4.4% of eligible patients were referred to CRP, with a rate of 10.4 patients/100,000 inhabitants in 2015. The ratio of Clinical Cardiologists to Cardiac Rehabilitation Specialists was 94:1, and the ratio of Intervention Specialists to cardiac rehabilitation experts was 16:1. Cardiac rehabilitation activities and costs varied widely. Patient dropout rate in phase II was 12%. Several barriers were identified: financial crisis (83%), lack of skilled personnel (67%), deficient equipment (46%), inadequate areas (42%), and a reduced number of operating centres (38%). CRPs in Mexico are still in the process of maturing. Mexican CRP-centres have several strengths, like the quality of the education of the professionals and the multidisciplinary programs. However, the lack of referral of patients and the heterogeneity of procedures are still their main weaknesses. Copyright © 2016 Instituto Nacional de Cardiología Ignacio Chávez. Publicado por Masson Doyma México S.A. All rights reserved.

  18. Special initiatives FY 1996 multi-year program plan (MYPP) WBS 5.0. Revision 1

    International Nuclear Information System (INIS)

    Howald, S.C.

    1995-09-01

    The Special Initiatives mission supports programmatic requests for service to DOE offices, other organizations and agencies. These requests can include the following: Supporting priority DOE initiatives, researching special programs, studying locating new activities ar the Hanford Site, producing specialty materials, providing consulting support to other sites, and managing a broad spectrum of US and international test programs. The Special Initiatives Program discussed in this plan consists of the following elements: space power programs, advanced programs, special programs, and program strategy

  19. Seismic Safety Margins Research Program: Phase II program plan (FY 83-FY 84)

    International Nuclear Information System (INIS)

    Bohn, M.P.; Bernreuter, D.L.; Cover, L.E.; Johnson, J.J.; Shieh, L.C.; Shukla, S.N.; Wells, J.E.

    1982-01-01

    The Seismic Safety Margins Research Program (SSMRP) is an NRC-funded, multiyear program conducted by Lawrence Livermore National Laboratory (LLNL). Its goal is to develop a complete, fully coupled analysis procedure (including methods and computer codes) for estimating the risk of an earthquake-caused radioactive release from a commercial nuclear power plant. The analysis procedure is based upon a state-of-the-art evaluation of the current seismic analysis and design process and explicitly includes the uncertainties inherent in such a process. The results will be used to improve seismic licensing requirements for nuclear power plants. As currently planned, the SSMRP will be completed in September, 1984. This document presents the program plan for work to be done during the remainder of the program. In Phase I of the SSMRP, the necessary tools (both computer codes and data bases) for performing a detailed seismic risk analysis were identified and developed. Demonstration calculations were performed on the Zion Nuclear Power Plant. In the remainder of the program (Phase II) work will be concentrated on developing a simplified SSMRP methodology for routine probabilistic risk assessments, quantitative validation of the tools developed and application of the simplified methodology to a Boiling Water Reactor. (The Zion plant is a pressurized water reactor.) In addition, considerable effort will be devoted to making the codes and data bases easily accessible to the public

  20. Exploration of Logistics Information Technology (IT) Solutions for the Royal Saudi Naval Force Within the Saudi Naval Expansion Program II (SNEP II)

    Science.gov (United States)

    2017-12-01

    NAVAL POSTGRADUATE SCHOOL MONTEREY, CALIFORNIA MBA PROFESSIONAL REPORT EXPLORATION OF LOGISTICS INFORMATION TECHNOLOGY (IT) SOLUTIONS FOR THE...INFORMATION TECHNOLOGY (IT) SOLUTIONS FOR THE ROYAL SAUDI NAVAL FORCE WITHIN THE SAUDI NAVAL EXPANSION PROGRAM II (SNEP II) 5. FUNDING NUMBERS 6. AUTHOR(S...Expansion Program II (SNEP II). A part of this program includes upgrading and rebuilding its information technology (IT) infrastructure. The United

  1. 75 FR 807 - Pesticide Tolerance Crop Grouping Program II; Revision to General Tolerance Regulations

    Science.gov (United States)

    2010-01-06

    .... pubescens Ruiz & Pav., Capsicum spp.; (12) Roselle, Hibiscus sabdariffa L.; (13) Scarlet eggplant, Solanum..., specialty crop producers, pesticide registrants, the environment, or human health. No crop group tolerance... Environmental Health Risks and Safety Risks (62 FR 19885, April 23, 1997) does not apply to this proposed rule...

  2. 75 FR 76284 - Pesticide Tolerance Crop Grouping Program II; Revisions to General Tolerance Regulations

    Science.gov (United States)

    2010-12-08

    ... scabrum Mill 8-10A Goji berry, Lycium barbarum L 8-10A Groundcherry, Physalis alkekengi L., P. 8-10A grisea (Waterf.) M. Martinez, P. peruviana L., P. pubescens L. Martynia, Proboscidea louisianica 8-10B, 8... aethiopicum L. 8-10B, 8-10C Sunberry, Solanum retroflexum Dunal..... 8-10A Tomatillo, Physalis philadelphica...

  3. Financial services FY 1996 site support program plan, WBS 6.10.4. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Schafer, D.D.

    1995-09-01

    This program plan outlines the financial services to be provided to the Hanford reservation by the Westinghouse Hanford Company. The topics of the plan include the Hanford strategic plan, program mission, program strategy, technical requirements baseline, schedule baseline, cost baseline, performance measures, technical objectives, program performance and program funding required.

  4. Financial services FY 1996 site support program plan, WBS 6.10.4. Revision 1

    International Nuclear Information System (INIS)

    Schafer, D.D.

    1995-09-01

    This program plan outlines the financial services to be provided to the Hanford reservation by the Westinghouse Hanford Company. The topics of the plan include the Hanford strategic plan, program mission, program strategy, technical requirements baseline, schedule baseline, cost baseline, performance measures, technical objectives, program performance and program funding required

  5. Scenario development and evaluation for the NPP Krsko revised decommissioning program

    International Nuclear Information System (INIS)

    Levanat, I.; Lokner, V.; Subasic, D.

    2004-01-01

    In this first revision, several integrated scenarios of the NPP Krsko dismantling and waste management were developed and analyzed in order to estimate the decommissioning program (DP) costs and to propose an appropriate funding plan. Most dismantling technologies and cost estimates were derived from the original decommissioning plan adopted in 1996. The LILW disposal cost estimates, however, rely on the tunnel type facility design which was developed in Slovenia a few years ago, whereas the SF repository design for this DP was adapted from the Swedish deep disposal concept. The starting assumptions for this DP were that the LILW repository would be licensed by 2013, the NPP would be permanently shut down in 2023, and the SF repository would become available in 2030. The boundary conditions also specified that DP should first re-evaluate the SID strategy from the original plan (Strategy Immediate Dismantling with immediate SF disposal, but also with a long period of on-site decay storage for the activated components, so that it actually terminates only after 96 years), and then modify it to achieve truly prompt decommissioning in which all planned activities should be completed within about 15 years after the NPP shut-down. In addition, the option of SF export to a third country should be introduced in all DP scenarios, as a realistic alternative to SF disposal into the local repository (in Slovenia or in Croatia). And finally, dry storage of SF for some 30 years before disposal or export, in an independent installation on unspecified location, should be evaluated within the DP sensitivity analysis. After a thorough analysis of the original SID strategy, it became clear that substantial modifications would be necessary in order to meet the boundary conditions while complying with the specified design and technologies of the assumed LILW and SF disposal facilities. Therefore, a systematic procedure for development and financial evaluation of feasible scenarios was

  6. 2 CFR 215.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-01-01

    ... option, restrict the transfer of funds among direct cost categories or programs, functions and activities... scope or the objective of the project or program. (2) The need arises for additional Federal funds to... program or budget related reasons. (1) Change in the scope or the objective of the project or program...

  7. The new revision of NPP Krsko decommissioning, radioactive waste and spent fuel management program: analyses and results

    International Nuclear Information System (INIS)

    Zeleznik, Nadja; Kralj, Metka; Lokner, Vladimir; Levanat, Ivica; Rapic, Andrea; Mele, Irena

    2010-01-01

    The preparation of the new revision of the Decommissioning and Spent Fuel (SF) and Low and Intermediate level Waste (LILW) Disposal Program for the NPP Krsko (Program) started in September 2008 after the acceptance of the Term of Reference for the work by Intergovernmental Committee responsible for implementation of the Agreement between the governments of Slovenia and Croatia on the status and other legal issues related to investment, exploitation, and decommissioning of the Nuclear power plant Krsko. The responsible organizations, APO and ARAO together with NEK prepared all new technical and financial data and relevant inputs for the new revision in which several scenarios based on the accepted boundary conditions were investigated. The strategy of immediate dismantling was analyzed for planned and extended NPP life time together with linked radioactive waste and spent fuel management to calculate yearly annuity to be paid by the owners into the decommissioning funds in Slovenia and Croatia. The new Program incorporated among others new data on the LILW repository including the costs for siting, construction and operation of silos at the location Vrbina in Krsko municipality, the site specific Preliminary Decommissioning Plan for NPP Krsko which included besides dismantling and decontamination approaches also site specific activated and contaminated radioactive waste, and results from the referenced scenario for spent fuel disposal but at very early stage. Important inputs for calculations presented also new amounts of compensations to the local communities for different nuclear facilities which were taken from the supplemented Slovenian regulation and updated fiscal parameters (inflation, interest, discount factors) used in the financial model based on the current development in economical environment. From the obtained data the nominal and discounted costs for the whole nuclear program related to NPP Krsko which is jointly owned by Slovenia and Croatia have

  8. 75 FR 44144 - Washington: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2010-07-28

    ...)(c)(ix)(K), 400(3)(c)(ix)(L), 400(3)(c)(x), 400(3)(c)(xi)(A), 400(3)(c)(xii)(B), 400(3)(a)(xiii), 400.... definition--Upda ted to match Federal rule. 040 Staging Pile 260.10. definition--Upda ted to match Federal... test methods to latest revision date. 110(3)(g)(x) Duplicate deleted 260.11(15). [see 110(3)(g)(vii...

  9. Antimicrobial Exposure Assessment Task Force II (AEATF II) Volume 5: Governing Document for a Multi-Year Antimicrobial Chemical Exposure Monitoring Program (interim draft document with changes)

    Science.gov (United States)

    This document describes the overall scope of the AEATF II program, demonstrates the need for additional human exposure monitoring data and explains the proposed methodology for the exposure monitoring studies proposed for conduct by the AEATF II.

  10. Antimicrobial Exposure Assessment Task Force II (AEATF II) Volume 5: Governing Document for a Multi-Year Antimicrobial Chemical Exposure Monitoring Program (interim draft document)

    Science.gov (United States)

    Describes the overall scope of the AEATF II program, demonstrates the need for additional human exposure monitoring data and explains the proposed methodology for the exposure monitoring studies proposed for conduct by the AEATF II.

  11. 40 CFR 147.50 - State-administered program-Class II wells.

    Science.gov (United States)

    2010-07-01

    ... Carry Out Underground Injection Control Program Relating to Class II Wells as Described in Federal Safe... PROGRAMS (CONTINUED) STATE, TRIBAL, AND EPA-ADMINISTERED UNDERGROUND INJECTION CONTROL PROGRAMS Alabama... application: (a) Incorporation by reference. The requirements set forth in the State statutes and regulations...

  12. Solid Waste Program Fiscal Year 1996 Multi-Year Program Plan WBS 1.2.1, Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    This document contains the Fiscal Year 1996 Multi-Year Program Plan for the Solid Waste Program at the Hanford Reservation in Richland, Washington. The Solid Waste Program treats, stores, and disposes of a wide variety of solid wastes consisting of radioactive, nonradioactive and hazardous material types. Solid waste types are typically classified as transuranic waste, low-level radioactive waste, low-level mixed waste, and non-radioactive hazardous waste. This report describes the mission, goals and program strategies for the Solid Waste Program for fiscal year 1996 and beyond.

  13. Solid Waste Program Fiscal Year 1996 Multi-Year Program Plan WBS 1.2.1, Revision 1

    International Nuclear Information System (INIS)

    1995-09-01

    This document contains the Fiscal Year 1996 Multi-Year Program Plan for the Solid Waste Program at the Hanford Reservation in Richland, Washington. The Solid Waste Program treats, stores, and disposes of a wide variety of solid wastes consisting of radioactive, nonradioactive and hazardous material types. Solid waste types are typically classified as transuranic waste, low-level radioactive waste, low-level mixed waste, and non-radioactive hazardous waste. This report describes the mission, goals and program strategies for the Solid Waste Program for fiscal year 1996 and beyond

  14. Review IPEEE C.N. external event Vandellos II; Revision del IPEEE de otros sucesos externos de C.N. Vandellos II

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez, H.; Gasca, C.; Beltran, F.; Salvat, M.; Pifarre, D.; Canadell, F.; Aleman, A.

    2010-07-01

    Within the process of maintaining and updating the risk analysis of CN Vandellos II, results from the review of the study of vulnerability of the plant against severe accidents caused by external events (Individual Plant Examination on Extornal Events, IPEEE).

  15. 40 CFR 147.2201 - State-administered program-Class II wells

    Science.gov (United States)

    2010-07-01

    ... Application to Oil, Gas, and Geothermal Resource Operations, sections .051.02.02.000 to .051.02.02.080... wells 147.2201 Section 147.2201 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED... Texas § 147.2201 State-administered program—Class II wells The UIC program for Class II wells in the...

  16. Preliminary psychometric properties of the Acceptance and Action Questionnaire-II: a revised measure of psychological inflexibility and experiential avoidance.

    Science.gov (United States)

    Bond, Frank W; Hayes, Steven C; Baer, Ruth A; Carpenter, Kenneth M; Guenole, Nigel; Orcutt, Holly K; Waltz, Tom; Zettle, Robert D

    2011-12-01

    The present research describes the development and psychometric evaluation of a second version of the Acceptance and Action Questionnaire (AAQ-II), which assesses the construct referred to as, variously, acceptance, experiential avoidance, and psychological inflexibility. Results from 2,816 participants across six samples indicate the satisfactory structure, reliability, and validity of this measure. For example, the mean alpha coefficient is .84 (.78-.88), and the 3- and 12-month test-retest reliability is .81 and .79, respectively. Results indicate that AAQ-II scores concurrently, longitudinally, and incrementally predict a range of outcomes, from mental health to work absence rates, that are consistent with its underlying theory. The AAQ-II also demonstrates appropriate discriminant validity. The AAQ-II appears to measure the same concept as the AAQ-I (r=.97) but with better psychometric consistency. Copyright © 2011. Published by Elsevier Ltd.

  17. BLAKE - A Thermodynamics Code Based on TIGER: Users' Guide to the Revised Program

    National Research Council Canada - National Science Library

    Freedman, Eli

    1998-01-01

    .... This code, which was derived from the original version of SRI's TIGER program, is intended primarily for making calculations on the combustion products from conventional military and electrically...

  18. Waste certification program plan for Oak Ridge National Laboratory. Revision 2

    International Nuclear Information System (INIS)

    1997-09-01

    This document defines the waste certification program (WCP) developed for implementation at Oak Ridge National Laboratory (ORNL). The document describes the program structure, logic, and methodology for certification of ORNL wastes. The purpose of the WCP is to provide assurance that wastes are properly characterized and that the Waste Acceptance Criteria (WAC) for receiving facilities are met. The program meets the waste certification requirements for mixed (both radioactive and hazardous) and hazardous ncluding polychlorinated biphenyls (PCB) waste. Program activities will be conducted according to ORNL Level 1 document requirements

  19. 1992 Resource Program, 10 Year Plan : Draft II.

    Energy Technology Data Exchange (ETDEWEB)

    United States. Bonneville Power Administration.

    1992-05-01

    The Resource Program is the Bonneville Power Administration's primary process for deciding how to meet future electricity resource needs, how much new resources to develop, which types of resources to acquire or option and how to go about acquiring them, and how much BPA will have to spend for these resources. Recognizing that BPA must make a long-term commitment to acquiring conservation effectively, the 1992 Resource Program outlines a 10-year plan. Draft 2 of the 1992 Resource Program provides a framework for discussing the funding levels proposed in the Programs in Perspective (PIP) process. Previous final resource programs have been released prior to the PIP process. This version of the Resource Program recognizes that the PIP discussions are an integral part of the resource decision-making process and, therefore, it will be finalized after PIP.

  20. 1992 Resource Program, 10 Year Plan : Draft II.

    Energy Technology Data Exchange (ETDEWEB)

    United States. Bonneville Power Administration.

    1992-05-01

    The Resource Program is the Bonneville Power Administration`s primary process for deciding how to meet future electricity resource needs, how much new resources to develop, which types of resources to acquire or option and how to go about acquiring them, and how much BPA will have to spend for these resources. Recognizing that BPA must make a long-term commitment to acquiring conservation effectively, the 1992 Resource Program outlines a 10-year plan. Draft 2 of the 1992 Resource Program provides a framework for discussing the funding levels proposed in the Programs in Perspective (PIP) process. Previous final resource programs have been released prior to the PIP process. This version of the Resource Program recognizes that the PIP discussions are an integral part of the resource decision-making process and, therefore, it will be finalized after PIP.

  1. Complex exercise rehabilitation program for women of the II period of age with metabolic syndrome

    OpenAIRE

    Lee, Eun-Ok; Olga, Kozyreva

    2013-01-01

    The purpose of this study was to develop a complex exercise program integrating Eastern and Western complex exercise rehabilitation programs in order to examine the effects of it on the human body with the subjects for women of the II period of mature age with metabolic syndrome. The subjects of this study are 60 II period of mature aged women with metabolic syndrome living in G City, and the experimental group conducted Taekwon-aerobic exercise, European rehabilitation gymnastics, gym ball e...

  2. Development of a safety and regulation systems simulation program II

    International Nuclear Information System (INIS)

    1985-05-01

    This report describes the development of a safety and regulation systems simulation program under contract to the Atomic Energy Control Board of Canada. A systems logic interaction simulation (SLISIM) program was developed for the AECB's HP-1000 computer which operates in the interactive simulation (INSIM) program environment. The SLISIM program simulates the spatial neutron dynamics, the regulation of the reactor power and in this version the CANDU-PHW 600 MW(e) computerized shutdown systems' trip parameters. The modular concept and interactive capability of the INSIM environment provides the user with considerable flexibility of the setup and control of the simulation

  3. 24 CFR 84.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-04-01

    ... transfer of funds among direct cost categories or programs, functions and activities for awards in which...) Change in the scope or the objective of the project or program (even if there is no associated budget...) The transfer of funds allotted for training allowances (direct payment to trainees) to other...

  4. 41 CFR 105-72.305 - Revision of budget and program plans.

    Science.gov (United States)

    2010-07-01

    ... transfer of funds among direct cost categories or programs, functions and activities for awards in which... related reasons. (1) Change in the scope or the objective of the project or program (even if there is no..., “Contract Cost Principles and Procedures,” as applicable. (7) The transfer of funds allotted for training...

  5. 10 CFR 600.125 - Revision of budget and program plans.

    Science.gov (United States)

    2010-01-01

    ... requires additional Federal funds. (iii) The extension involves any change in the approved objectives or... regulations may restrict the transfer of funds among direct cost categories or programs, functions and... objective of the project or program. (2) The need arises for additional Federal funds to complete the...

  6. A Manual for the Anchorage School District Bilingual Education Program Revised Scope and Sequence, K-3.

    Science.gov (United States)

    Heinrich, Maria Nieves Bumanlag Lilagan

    The manual offers a systematic set of procedures and relevant information to facilitate effective use of the Anchorage school district (ASD) bilingual education program (BEP). The historical background of the program's development is presented, available manuals for teaching English to limited English proficiency (LEP) students and related…

  7. Liquid effluent FY 1996 program plan WBS 1.2.2.1. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    The Liquid Effluents Program supports the three Hanford Site mission components: (1) Clean up the site, (2) provide scientific and technological excellence to meet global needs, and (3) Partner in the economic diversification of the region. Nine Hanford Site objectives have been established for the Hanford Site programs to accomplish all three components of this mission.

  8. 75 FR 45088 - Lamb Promotion, Research, and Information Program; Notice of Request for Extension and Revision...

    Science.gov (United States)

    2010-08-02

    ... DEPARTMENT OF AGRICULTURE Agricultural Marketing Service [Document AMS-LS-10-0056] Lamb Promotion... the Lamb Promotion, Research, and Information Program. Once approved, AMS will be requesting OMB merge... INFORMATION: Title: Lamb Promotion, Research, and Information Program. OMB Number: 0581-0198. Expiration Date...

  9. Liquid effluent FY 1996 program plan WBS 1.2.2.1. Revision 1

    International Nuclear Information System (INIS)

    1995-09-01

    The Liquid Effluents Program supports the three Hanford Site mission components: (1) Clean up the site, (2) provide scientific and technological excellence to meet global needs, and (3) Partner in the economic diversification of the region. Nine Hanford Site objectives have been established for the Hanford Site programs to accomplish all three components of this mission

  10. 77 FR 22792 - Non-Competitive Program Expansion Supplement To Revise, Update, and Disseminate Educational...

    Science.gov (United States)

    2012-04-17

    ... Administration (HRSA) will be issuing a non-competitive program expansion supplement to 45 Geriatric Education... educational programming. The programmatic supplements will allow the Bureau of Health Professions to... and Interdisciplinary Education, 5600 Fishers Lane, Room 9C-05, Rockville, Maryland 20857, or email...

  11. Multi-Function Waste Tank Facility Quality Assurance Program Plan, Project W-236A. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Hall, L.R.

    1995-05-30

    This document describes the Quality Assurance (QA) program for the Multi-Function Waste Tank Facility (MWTF) Project. The purpose of this QA program is to control project activities in such a manner as to achieve the mission of the MWTF Project in a safe and reliable manner. The QA program for the MWTF Project is founded on DOE Order 5700.6C, Quality Assurance, and implemented through the use of ASME NQA-1, Quality Assurance Program Requirements for Nuclear Facilities (ASME 1989 with addenda la-1989, lb-1991 and lc-1992). This document describes the program and planned actions which the Westinghouse Hanford Company (WHC) will implement to demonstrate and ensure that the project meets the requirements of DOE Order 5700.6C through the interpretive guidance of ASME NQA-1.

  12. Waste certification program plan for Oak Ridge National Laboratory. Revision 1

    International Nuclear Information System (INIS)

    Orrin, R.C.

    1997-05-01

    This document defines the waste certification program developed for implementation at Oak Ridge National Laboratory (ORNL). The document describes the program structure, logic, and methodology for certification of ORNL wastes. The purpose of the waste certification program is to provide assurance that wastes are properly characterized and that the Waste Acceptance Criteria (WAC) for receiving facilities are met. The program meets the waste certification requirements outlined in US Department of Energy (DOE) Order 5820.2A, Radioactive Waste Management, and ensures that 40 CFR documentation requirements for waste characterization are met for mixed (both radioactive and hazardous) and hazardous (including polychlorinated biphenyls) waste. Program activities will be conducted according to ORNL Level 1 document requirements

  13. Multi-Function Waste Tank Facility Quality Assurance Program Plan, Project W-236A. Revision 2

    International Nuclear Information System (INIS)

    Hall, L.R.

    1995-01-01

    This document describes the Quality Assurance (QA) program for the Multi-Function Waste Tank Facility (MWTF) Project. The purpose of this QA program is to control project activities in such a manner as to achieve the mission of the MWTF Project in a safe and reliable manner. The QA program for the MWTF Project is founded on DOE Order 5700.6C, Quality Assurance, and implemented through the use of ASME NQA-1, Quality Assurance Program Requirements for Nuclear Facilities (ASME 1989 with addenda la-1989, lb-1991 and lc-1992). This document describes the program and planned actions which the Westinghouse Hanford Company (WHC) will implement to demonstrate and ensure that the project meets the requirements of DOE Order 5700.6C through the interpretive guidance of ASME NQA-1

  14. 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

  15. Modeling transducer impulse responses for predicting calibrated pressure pulses with the ultrasound simulation program Field II

    DEFF Research Database (Denmark)

    Bæk, David; Jensen, Jørgen Arendt; Willatzen, Morten

    2010-01-01

    FIELD II is a simulation software capable of predicting the field pressure in front of transducers having any complicated geometry. A calibrated prediction with this program is, however, dependent on an exact voltage-to-surface acceleration impulse response of the transducer. Such impulse response...... is not calculated by FIELD II. This work investigates the usability of combining a one-dimensional multilayer transducer modeling principle with the FIELD II software. Multilayer here refers to a transducer composed of several material layers. Measurements of pressure and current from Pz27 piezoceramic disks...... transducer model and the FIELD II software in combination give good agreement with measurements....

  16. Training and qualification program for nuclear criticality safety technical staff. Revision 1

    International Nuclear Information System (INIS)

    Taylor, R.G.; Worley, C.A.

    1997-01-01

    A training and qualification program for nuclear criticality safety technical staff personnel has been developed and implemented. All personnel who are to perform nuclear criticality safety technical work are required to participate in the program. The program includes both general nuclear criticality safety and plant specific knowledge components. Advantage can be taken of previous experience for that knowledge which is portable such as performance of computer calculations. Candidates step through a structured process which exposes them to basic background information, general plant information, and plant specific information which they need to safely and competently perform their jobs. Extensive documentation is generated to demonstrate that candidates have met the standards established for qualification

  17. Survey Procedures Manual for the Environmental Survey and Site Assessment Program (ESSAP). Revision 10

    International Nuclear Information System (INIS)

    2000-01-01

    The Environmental Survey and Site Assessment Program (ESSAP) of the Oak Ridge Institute for Science and Education (ORISE) conducts radiological survey activities under a contract with the U. S. Department of Energy (DOE) and for the U.S. Nuclear Regulatory Commission (NRC). ORISE and its programs are operated by Oak Ridge Associated Universities (ORAU) through a contract with DOE. The purpose of this Procedures Manual is to provide a standardized set of procedures that document activities of the program in an auditable manner. These procedures are applicable to both DOE and NRC operations. Procedures presented in this manual are limited to those associated with site survey activities

  18. Reduced enrichment program for the FRM-II, status 2004

    International Nuclear Information System (INIS)

    Roehrmoser, A.; Petry, W.; Boening, K; Wieschalla, N.

    2005-01-01

    The new research reactor FRM-II of the Technische Universitaet Muenchen (TUM) has been designed to provide a maximal thermal neutron flux at mere 20 MW power. The single element design uses silicide fuel of densities 3.0 and 1.5 g/cm 3 of highly enriched uranium (HEU, 93 % U-235). With the nuclear license, that was granted in May 2003, a condition was imposed to reduce the enrichment of FRM-II to medium enriched uranium (MEU) with not more than 50 % U-235 until the end of the year 2010. The TUM has established an international working group to meet this target. This paper presents the backgrounds and the results and plannings for the first of three 2 1/2 year periods to reach the conversion in time. (author)

  19. Program plan for the DOE Office of Fusion Energy First Wall/Blanket/Shield Engineering Technology Program. Volume I. Summary, objectives and management. Revision 2

    International Nuclear Information System (INIS)

    1982-08-01

    This document defines a plan for conducting selected aspects of the engineering testing required for magnetic fusion reactor FWBS components and systems. The ultimate product of this program is an established data base that contributes to a functional, reliable, maintainable, economically attractive, and environmentally acceptable commercial fusion reactor first wall, blanket, and shield system. This program plan updates the initial plan issued in November of 1980 by the DOE/Office of Fusion Energy (unnumbered report). The plan consists of two parts. Part I is a summary of activities, responsibilities and program management including reporting and interfaces with other programs. Part II is a compilation of the Detailed Technical Plans for Phase I (1982 to 1984) developed by the participants during Phase 0 of the program

  20. RECON: a computer program for analyzing repository economics. Documentation and user's manual. Revision 1

    International Nuclear Information System (INIS)

    Clark, L.L.; Schutz, M.E.; Luksic, A.T.

    1985-07-01

    From 1981 through 1984 the Pacific Northwest Laboratory has been developing a computer model named RECON to calculate repository costs from parametric data input. The objective of the program has been to develop the capability to evaluate the effect on costs of changes in repository design parameters and operating scenario assumptions. This report documents the development of the model through September of 1984. Included in the report are: (1) descriptions of model development and the underlying equations, assumptions and definitions; (2) descriptions of data input using either card images or an interactive data input program; and (3) detailed listings of the program and definitions of program variables. Cost estimates generated using the model have been verified against independent estimates and good agreement has been obtained. 2 refs

  1. B and W NPGD quality assurance program for nuclear equipment. Revision 1

    International Nuclear Information System (INIS)

    1975-03-01

    B and W's Quality Assurance Program (QAP) is described. The program is implemented through the Nuclear Power Generation Division (NPGD) and includes design, procurement, and manufacturing activities of NPGD and all its suppliers furnishing items in the B and W scope of supply including other Divisions/ Subsidiaries of B and W. These activities are controlled by including applicable quality assurance requirements, as described, in NPGD procurement documents imposed on its suppliers. Each supplier must then establish and/or maintain a documented QA Program to meet the requirements imposed by the procurement documents. Implementation of the suppliers' NPGD-approved QA Program is verified by NPGD through Audit and QC Surveillance activities. The position and relationships of the NPGD within the Company's corporate structure are described. An overview of the QAP describing its implementation, its operation, the controls imposed on all suppliers (both corporate and vendor) and site consulting activities is presented. (U.S.)

  2. Quality assurance program requirements (design and construction). Task RS 002-5. Revision 3

    International Nuclear Information System (INIS)

    1985-08-01

    This regulatory guide describes a method acceptable to the NRC staff for complying with regard to establishing and implementing the requisite quality assurance program for the design and construction of nuclear power plants. Guidance for the establishment and execution of quality assurance programs during operation and decommissioning of nuclear power plants have been or will be addressed in separate regulatory guides. Similarly, quality assurance provisions concerning fuel cycle facilities have been or will be addressed in separate regulatory guides

  3. Revising the ACS Guidelines for Chemistry Programs in Two-Year Colleges: Shaping the Next Edition

    Science.gov (United States)

    Clevenger, John V.; Wesemann, Jodi L.

    2008-06-01

    Much has changed since the second edition of the ACS Guidelines for Chemistry Programs in Two-Year Colleges was prepared in 1997. The roles that two-year college programs can and do play in providing access to and success in higher education are receiving more attention. Increased knowledge on how people learn, advances in technology, and demands for accountability are changing the educational landscape.

  4. Solving seismological problems using sgraph program: II-waveform modeling

    International Nuclear Information System (INIS)

    Abdelwahed, Mohamed F.

    2012-01-01

    One of the seismological programs to manipulate seismic data is SGRAPH program. It consists of integrated tools to perform advanced seismological techniques. SGRAPH is considered a new system for maintaining and analyze seismic waveform data in a stand-alone Windows-based application that manipulate a wide range of data formats. SGRAPH was described in detail in the first part of this paper. In this part, I discuss the advanced techniques including in the program and its applications in seismology. Because of the numerous tools included in the program, only SGRAPH is sufficient to perform the basic waveform analysis and to solve advanced seismological problems. In the first part of this paper, the application of the source parameters estimation and hypocentral location was given. Here, I discuss SGRAPH waveform modeling tools. This paper exhibits examples of how to apply the SGRAPH tools to perform waveform modeling for estimating the focal mechanism and crustal structure of local earthquakes.

  5. High-heat tank safety issue resolution program plan. Revision 2

    International Nuclear Information System (INIS)

    Wang, O.S.

    1994-12-01

    The purpose of this program plan is to provide a guide for selecting corrective actions that will mitigate and/or remediate the high-heat waste tank safety issue for single-shell tank 241-C-106. The heat source of approximately 110,000 Btu/hr is the radioactive decay of the stored waste material (primarily 90 Sr) inadvertently transferred into the tank in the later 1960s. Currently, forced ventilation, with added water to promote thermal conductivity and evaporation cooling, is used for heat removal. The method is very effective and economical. At this time, the only viable solution identified to permanently resolve this safety issue is the removal of heat-generating waste in the tank. This solution is being aggressively pursued as the only remediation method to this safety issue, and tank 241-C-106 has been selected as the first single-shell tank for retrieval. The current cooling method and other alternatives are addressed in this program as means to mitigate this safety issue before retrieval. This program plan has three parts. The first part establishes program objectives and defines safety issue, drivers, and resolution criteria and strategy. The second part evaluates the high-heat safety issue and its mitigation and remediation methods and other alternatives according to resolution logic. The third part identifies major tasks and alternatives for mitigation and resolution of the safety issue. A table of best-estimate schedules for the key tasks is also included in this program plan

  6. National Synchrotron Light Source Facility Manual Maintenance Management Program. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Fewell, N.

    1993-12-01

    The purpose of this program s to meet the policy and objectives for the management and performance of cost-effective maintenance and repair of the National Synchrotron Light Source, as required by the US Department of Energy order DOE 433O.4A. It is the DOE`s policy that: The maintenance management program for the NSLS be consistent with this Order and that NSLS property is maintained in a manner which promotes operational safety, worker health, environmental protection and compliance, property preservation, and cost-effectiveness while meeting the NSLS`s programmatic mission. Structures, components and systems (active and passive) that are imporant to safe operation of the NSLS shall be subject to a maintenance program to ensure that they meet or exceed their design requirements throughout the life of the NSLS. Periodic examination of structures, systems components and equipment be performed to determine deterioration or technical obsolescence which may threaten performance and/or safety. Primary responsibility, authority, and accountability for the direction and management of the maintenance program at the NSLS reside with the line management assigned direct programmatic responsibility. Budgeting and accounting for maintenance programs are consistent with DOE Orders guidance.

  7. USAF Summer Faculty Research Program. 1981 Research Reports. Volume II.

    Science.gov (United States)

    1981-10-01

    Spec ialty : IIS F ,re ign Policy ; American Indiana State University Nat ioinal Security Policy Dept. of Political Science A. si ,niled: A! Terre Haute...0 C-4 44 C E) I IC C z)~ w z . 0 cnCd d CCC C’) 0-4-9- ..- E-4 (-4 7-A.A).)).) (QUADI) was constructed in the same manner as for the plate bending...IV modifications in accordance with current policy . They are to expedite safety modifications that could ground airborne systems or inactivate ground

  8. HIBAL Program. Preliminary Warhead-Design. Volume II. Appendices.

    Science.gov (United States)

    1980-09-15

    Mild Steel (iAi i018). ............. 11-2 B. SAE 4130 .. .. .. .... ...... ....... 11-3 C. SAE 4140 ......... .... .... ......... 11-3 D, SAE 4340...11-7 - Test Data for SAE 4140 Steel Frag- ments ...... ................ 11-14 Figure II-7A - 4142 ... .............. 11-15 Figure 11-8 - Test Data...included the following types of steel: SAE 1018, 4130, 4140 and 4340; 5-317 and 5-876 Carpenter tool steel; Anico HY-80 and SSS-100 steel; AISI-S7

  9. U.S. Department of Energy, Carlsbad Area Office quality assurance program document. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-01

    Mission of the Carlsbad Area Office (CAO) is to protect human health and the environment by opening and operating the Waste Isolation Pilot Plant (WIPP) for safe disposal of TRU waste, and establishing an effective system for management of TRU waste from generation to disposal. To help in fulfilling this mission and to ensure that risks and environmental impacts are identified and minimized, and that safety, reliability, and performance are optimized, CAO`s policy is to establish and maintain an effective quality assurance (QA) program that supports compliance with applicable Federal, State, and local regulations, and DOE orders and requirements. This document establishes QA program requirements for all programs, projects, and activities sponsored by CAO.

  10. Training Services Site Support Program Plan WBS 6.13. Revision 1

    International Nuclear Information System (INIS)

    1995-09-01

    The mission of Hanford Reservation's Training Services is to procure, promote, and provide ''Tomorrow's Training Today'' by innovatively adapting services to meet the needs of current programs. The program objectives are: provide the workforce with the knowledge and skills to safely and effectively achieve the Hanford Mission; Provide customer-driven training services in a quality, cost efficient manner; provide the Hanford community retraining opportunities consistent with the Hanford Mission and Columbia Basin economic viability; and provide workforce with knowledge and expertise with new and more effective technology

  11. Optimisation in radiotherapy II: Programmed and inversion optimisation algorithms

    International Nuclear Information System (INIS)

    Ebert, M.

    1997-01-01

    This is the second article in a three part examination of optimisation in radiotherapy. The previous article established the bases of optimisation in radiotherapy, and the formulation of the optimisation problem. This paper outlines several algorithms that have been used in radiotherapy, for searching for the best irradiation strategy within the full set of possible strategies. Two principle classes of algorithm are considered - those associated with mathematical programming which employ specific search techniques, linear programming type searches or artificial intelligence - and those which seek to perform a numerical inversion of the optimisation problem, finishing with deterministic iterative inversion. (author)

  12. Program Design Report of the CNC Machine Tool(II)

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jong Kiun; Youm, K. U.; Kim, K. S.; Lee, I. B.; Yoon, K. B.; Lee, C. K.; Youm, J. H

    2007-06-15

    The application of CNC machine tool being widely expanded according to variety of machine work method and rapid promotion of machine tool, cutting tool, for high speed efficient machine work. In order to conduct of the project of manufacture and maintenance of laboratory equipment, production design and machine work technology are continually developed, especially the application of CNC machine tool is very important for the improvement of productivity, quality and clearing up a manpower shortage. We publish technical report which it includes CNC machine tool program and drawing, it contributes to the systematic development of CNC program design and machine work technology.

  13. Program Design Report of the CNC Machine Tool(II)

    International Nuclear Information System (INIS)

    Kim, Jong Kiun; Youm, K. U.; Kim, K. S.; Lee, I. B.; Yoon, K. B.; Lee, C. K.; Youm, J. H.

    2007-06-01

    The application of CNC machine tool being widely expanded according to variety of machine work method and rapid promotion of machine tool, cutting tool, for high speed efficient machine work. In order to conduct of the project of manufacture and maintenance of laboratory equipment, production design and machine work technology are continually developed, especially the application of CNC machine tool is very important for the improvement of productivity, quality and clearing up a manpower shortage. We publish technical report which it includes CNC machine tool program and drawing, it contributes to the systematic development of CNC program design and machine work technology

  14. 75 FR 23264 - Public Water System Supervision Program Revision for the State of Alabama

    Science.gov (United States)

    2010-05-03

    ... Public Water System Supervision Program. Alabama has adopted the following rules: Arsenic Rule, Lead and... motion, this determination shall become final and effective on June 2, 2010. Any request for a public... the Regional Administrator's determination and a brief statement of the information that the...

  15. 22 CFR 226.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-04-01

    ... Section 226.25 Foreign Relations AGENCY FOR INTERNATIONAL DEVELOPMENT ADMINISTRATION OF ASSISTANCE AWARDS TO U.S. NON-GOVERNMENTAL ORGANIZATIONS Post-award Requirements Financial and Program Management § 226... Principles for Non-Profit Organizations,” or 45 CFR part 74, Appendix E, “Principles for Determining Costs...

  16. 78 FR 73858 - Public Water System Supervision Program Revision for the State of Oklahoma

    Science.gov (United States)

    2013-12-09

    ... approved Public Water System Supervision Program. Oklahoma has adopted three EPA drinking water rules... and Disinfection Byproducts Rule (DBP2), and (3) the Ground Water Rule (GWR). EPA has determined that... Protection Agency, Region 6, Drinking Water Section (6WQ-SD), 1445 Ross Avenue, Suite 1200, Dallas, Texas...

  17. 78 FR 9047 - Public Water System Supervision Program Revision for the State of Texas

    Science.gov (United States)

    2013-02-07

    ... Water System Supervision Program. Texas has adopted three EPA drinking water rules, namely the: (1) Long Term 2 Enhanced Surface Water Treatment Rule (LT2), (2) the Stage 2 Disinfectants and Disinfection... Drinking Water Section (MC-155), Building F, 12100 Park 35 Circle, Austin, TX 78753; and United States...

  18. Operation of Wastewater Treatment Plants. Volume 1. A Field Study Training Program. Third Edition. Revised.

    Science.gov (United States)

    California State Univ., Sacramento. Dept. of Civil Engineering.

    The purpose of this wastewater treatment field study training program is to: (1) develop new qualified wastewater treatment plant operators; (2) expand the abilities of existing operators, permitting better service both to employers and public; and (3) prepare operators for civil service and certification examinations (examinations administered by…

  19. Water Treatment Plant Operation Volume 2. A Field Study Training Program. Revised.

    Science.gov (United States)

    California State Univ., Sacramento. School of Engineering.

    The purpose of this water treatment field study training program is to: (1) develop new qualified water treatment plant operators; (2) expand the abilities of existing operators, permitting better service both to employers and public; and (3) prepare operators for civil service and certification examinations (examinations administered by…

  20. Competency Based Curriculum. Revised Delivery Systems for Culinary Arts Program. Project Report.

    Science.gov (United States)

    Spokane Community Coll., WA.

    Developed through a grant that enabled faculty members to work together to define goals and set objectives, this curriculum guide contains course objectives for the culinary arts program at Spokane Community College in Washington. Objectives are provided for the following courses: culinary techniques and skill development (two levels),…

  1. 7 CFR 3019.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-01-01

    ... described in this paragraph (e) are automatically waived (i.e., recipients need not obtain such prior... the needs of the recipient for the project period by more than $5000 or five percent of the Federal... appropriate. (b) Recipients are required to report deviations from budget and program plans, and request prior...

  2. 32 CFR 32.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-07-01

    ..., recipients need not obtain prior approvals before: (i) Incurring pre-award costs 90 calendar days prior to... the needs of the recipient for the project period by more than $5000 or five percent of the Federal... shall be related to performance for program evaluation purposes whenever appropriate. (b) Recipients are...

  3. 43 CFR 12.925 - Revision of budget and program plans.

    Science.gov (United States)

    2010-10-01

    ...) through (3) of this section are automatically waived (i.e., recipients need not obtain such prior... promptly whenever the amount of Federal authorized funds is expected to exceed the needs of the recipient...) Recipients are required to report deviations from budget and program plans, and request prior approvals for...

  4. 49 CFR 19.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-10-01

    ... described in paragraph (e) of this section are automatically waived (i.e., recipients need not obtain such... exceed the needs of the recipient for the project period by more than $5,000 or five percent of the...) Recipients are required to report deviations from budget and program plans, and request prior approvals for...

  5. 29 CFR 95.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-07-01

    ...., recipients need not obtain such prior written approvals) unless one of the conditions included in paragraph... is expected to exceed the needs of the recipient for the project period by more than $5,000 or five...) Recipients are required to report deviations from budget and program plans, and request prior approvals for...

  6. 77 FR 32015 - Revision to the Section 8 Management Assessment Program Lease-Up Indicator

    Science.gov (United States)

    2012-05-31

    ... the HCV program and programmatic inefficiency. To eliminate such complexity, and reduce inefficiency... many HCVs, so the PHA may need to hold turnover HCVs so they will be available to assist new PBV... created after SEMAP began) have separate procedures or requirements that reduce the PHA's control over...

  7. The Arts and 504, A Handbook for Accessible Arts Programming. Revised.

    Science.gov (United States)

    National Endowment for the Arts, Washington, DC.

    This handbook is designed to assist arts organizations in complying with disability access regulations. It details how to include the needs of disabled people into programming efforts and also provides information on the Arts Endowment's 504 Regulation, which applies to federally funded organizations, and the 1990 Americans with Disabilities Act…

  8. Overview of the Defense Programs Research and Technology Development Program for fiscal year 1993. Appendix II research laboratories and facilities

    Energy Technology Data Exchange (ETDEWEB)

    1993-09-30

    This document contains summaries of the research facilities that support the Defense Programs Research and Technology Development Program for FY 1993. The nine program elements are aggregated into three program clusters as follows: (1) Advanced materials sciences and technologies; chemistry and materials, explosives, special nuclear materials (SNM), and tritium. (2) Design sciences and advanced computation; physics, conceptual design and assessment, and computation and modeling. (3) Advanced manufacturing technologies and capabilities; system engineering science and technology, and electronics, photonics, sensors, and mechanical components. Section I gives a brief summary of 23 major defense program (DP) research and technology facilities and shows how these major facilities are organized by program elements. Section II gives a more detailed breakdown of the over 200 research and technology facilities being used at the Laboratories to support the Defense Programs mission.

  9. China Public Budget Reform Program (CPBR) - Phase II | IDRC ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    The Government of China has adopted a national reform program aimed at making budgeting more transparent and accountable through public involvement and enhanced oversight. Building on work carried out under Phase I (102965), the China Development Research Foundation (CDRF) will analyze China's current ...

  10. LP II--A GOAL PROGRAMMING MODEL FOR MEDIA.

    Science.gov (United States)

    CHARNES, A.; AND OTHERS

    A GOAL PROGRAMING MODEL FOR SELECTING MEDIA IS PRESENTED WHICH ALTERS THE OBJECTIVE AND EXTENDS PREVIOUS MEDIA MODELS BY ACCOUNTING FOR CUMULATIVE DUPLICATING AUDIENCES OVER A VARIETY OF TIME PERIODS. THIS PERMITS DETAILED CONTROL OF THE DISTRIBUTION OF MESSAGE FREQUENCIES DIRECTED AT EACH OF NUMEROUS MARKETING TARGETS OVER A SEQUENCE OF…

  11. Sequence and batch language programs and alarm-related ``C`` programs for the 242-A MCS. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Berger, J.F.

    1995-03-01

    A Distributive Process Control system was purchased by Project B-534, ``242-A Evaporator/Crystallizer Upgrades``. This control system, called the Monitor and Control System (MCS), was installed in the 242-A Evaporator located in the 200 East Area. The purpose of the MCS is to monitor and control the Evaporator and monitor a number of alarms and other signals from various Tank Farm facilities. Applications software for the MCS was developed by the Waste Treatment Systems Engineering (WTSE) group of Westinghouse. The standard displays and alarm scheme provide for control and monitoring, but do not directly indicate the signal location or depict the overall process. To do this, WTSE developed a second alarm scheme which uses special programs, annunciator keys, and process graphics. The special programs are written in two languages; Sequence and Batch Language (SABL), and ``C`` language. The WTSE-developed alarm scheme works as described below: SABL relates signals and alarms to the annunciator keys, called SKID keys. When an alarm occurs, a SABL program causes a SKID key to flash, and if the alarm is of yellow or white priority then a ``C`` program turns on an audible horn (the D/3 system uses a different audible horn for the red priority alarms). The horn and flashing key draws the attention of the operator.

  12. Status of the GPD program rate at COMPASS II

    Energy Technology Data Exchange (ETDEWEB)

    Gorzellik, Matthias; Fischer, Horst; Joerg, Philipp; Koenigsmann, Kay; Landgraf, Steffen; Regali, Christopher; Schmidt, Katharina; Sirtl, Stefan; Szameitat, Tobias; Wolbeek, Johannes ter [Physikalisches Institut, Albert-Ludwigs-Universitaet Freiburg (Germany); Collaboration: COMPASS collaboration

    2015-07-01

    The COMPASS-II experiment is a fixed target experiment situated at CERN. A tertiary myon beam from the SPS scattered of protons from a liquid hydrogen target is used to measure Deeply Virtual Compton Scattering (DVCS) and Hard Exclusive Meson Production (HEMP). Both processes open a unique window to constrain Generalized Parton Distributions, which are related to the total angular momentum of quarks, antiquarks and gluons in the nucleon. An upgrade of the previous experiment was started in 2012. The major parts of the upgrade for the measurement of exclusive reactions are the recoil proton detector (CAMERA) and an additional Electromagnetic Calorimeter. The close to final setup allows for a measurement of exclusive reactions with very low cross sections in a wide kinematic range. A pilot run, covering five weeks of data taking, was performed at the end of 2012. In this talk we present first results from the analysis.

  13. Laboratory Directed Research & Development Program. Annual report to the Department of Energy, Revised December 1993

    Energy Technology Data Exchange (ETDEWEB)

    Ogeka, G.J.; Romano, A.J.

    1993-12-01

    At Brookhaven National Laboratory the Laboratory Directed Research and Development (LDRD) Program is a discretionary research and development tool critical in maintaining the scientific excellence and vitality of the laboratory. It is also a means to stimulate the scientific community, fostering new science and technology ideas, which is the major factor in achieving and maintaining staff excellence, and a means to address national needs, within the overall mission of the Department of Energy and Brookhaven National Laboratory. This report summarizes research which was funded by this program during fiscal year 1993. The research fell in a number of broad technical and scientific categories: new directions for energy technologies; global change; radiation therapies and imaging; genetic studies; new directions for the development and utilization of BNL facilities; miscellaneous projects. Two million dollars in funding supported 28 projects which were spread throughout all BNL scientific departments.

  14. Constellation Program Human-System Integration Requirements. Revision E, Nov. 19, 2010

    Science.gov (United States)

    Dory, Jonathan

    2010-01-01

    The Human-Systems Integration Requirements (HSIR) in this document drive the design of space vehicles, their systems, and equipment with which humans interface in the Constellation Program (CxP). These requirements ensure that the design of Constellation (Cx) systems is centered on the needs, capabilities, and limitations of the human. The HSIR provides requirements to ensure proper integration of human-to-system interfaces. These requirements apply to all mission phases, including pre-launch, ascent, Earth orbit, trans-lunar flight, lunar orbit, lunar landing, lunar ascent, Earth return, Earth entry, Earth landing, post-landing, and recovery. The Constellation Program must meet NASA's Agency-level human rating requirements, which are intended to ensure crew survival without permanent disability. The HSIR provides a key mechanism for achieving human rating of Constellation systems.

  15. San Diego Multiple Species Conservation Program (MSCP) Rare Plant Monitoring Review and Revision

    Science.gov (United States)

    McEachern, Kathryn; Pavlik, Bruce M.; Rebman, Jon; Sutter, Rob

    2007-01-01

    Introduction The San Diego Multiple Species Conservation Program (MSCP) was developed for the conservation of plants and animals in the south part of San Diego County, under the California Natural Community Conservation Planning Act of 1991 (California Department of Fish and Game) and the Federal Endangered Species Act of 1973, as amended (16 U.S. Code 1531-1544.) The Program is on the leading edge of conservation, as it seeks to both guide development and conserve at-risk species with the oversight of both State and Federal agencies. Lands were identified for inclusion in the MSCP based on their value as habitat for at-risk plants or plant communities (Natural Community Conservation Planning, 2005). Since its inception in the mid-1990s the Program has protected over 100,000 acres, involving 15 jurisdictions and the U.S. Fish and Wildlife Service (USFWS) and California Department of Fish and Game (CDFG) in the conservation of 87 taxa. Surveys for covered species have been conducted, and management and monitoring have been implemented at some high priority sites. Each jurisdiction or agency manages and monitors their conservation areas independently, while collaborating regionally for long-term protection. The San Diego MSCP is on the forefront of conservation, in one of the most rapidly growing urban areas of the country. The planning effort that developed the MSCP was state-of-the-art, using expert knowledge, spatial habitat modeling, and principles of preserve design to identify and prioritize areas for protection. Land acquisition and protection are ahead of schedule for most jurisdictions. Surveys have verified the locations of many rare plant populations known from earlier collections, and they provide general information on population size and health useful for further conservation planning. Management plans have been written or are in development for most MSCP parcels under jurisdictional control. Several agencies are developing databases for implementation

  16. Reliability programs for nuclear power plants. Regulatory standard S-98 revision 1

    International Nuclear Information System (INIS)

    2005-07-01

    The purpose of this regulatory standard is to help assure, in accordance with the purpose of the Nuclear Safety and Control Act (NSCA), that a licensee who constructs or operates a nuclear power plant (NPP) develops and implements a reliability program that assures that the systems important to safety at the plant can and will meet their defined design and performance specifications at acceptable levels of reliability throughout the lifetime of the facility. This regulatory standard describes the requirements of a reliability program for a nuclear power plant. The licensee shall implement the requirements described in this regulatory standard when a condition of a licence or other legally enforceable instrument so requires.(author)

  17. Information management fiscal year 1996 site support program plan, WBS 6.4. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    In the recent past, information resource management (IRM) was a neatly separable component of the overall DOE mission, concerned primarily with procuring and implementing automatic data processing (ADP) systems. As the DOE missions have shifted from producing product to managing processes, those clear lines have blurred. Today, IRM is firmly embedded in all aspects of the DOE mission. BCS Richland, Inc., (BCSR) provides IRM for the Hanford Site. The main focus in executing this mission is to meet customer goals by providing high-quality, timely, and cost-effective electronic communication, computing, and information services. Information resources provide the US Department of Energy, Richland Operations Office (RL) and the Hanford Site contractors the ability to generate, store, access, and communicate information quickly, reliably, and cost effectively. BCSR plans, implements, and operates electronic communication, computing and information management systems that enable effective operation of the Hanford Site. Five strategic initiatives to encompass the vision provide guidance and focus to the information technology (IT) direction for developing the BCSR program plan. These strategic initiatives are the program vision and are as follows: primary focus; fast response; accessible information; world class information management infrastructure; powerful desktop. The business directions that guide the development of the BCSR Program Plan are: (1) emphasize providing cost-effective and value-added communication, computing, and information systems products and services to the Site missions; (2) strengthen the alignment of products and services with Site projects and programs and eliminate duplications Sitewide; (3) focus on the effective resolution of critical Site information management (IM) issues.

  18. Verification of Concurrent Programs. Part II. Temporal Proof Principles.

    Science.gov (United States)

    1981-09-01

    not modify any of the shared program variables. In order to ensure the correct synchronization between the processes we use three semaphore variables...direct, simple, and intuitive rides for the establishment of these properties. rhey usually replace long but repetitively similar chains of primitive ...modify the variables on which Q actually depends. A typical case is that of semaphores . We have the following property: The Semaphore Variable Rule

  19. Using Interdisciplinary Research Methods to Revise and Strengthen the NWS TsunamiReadyTM Community Recognition Program

    Science.gov (United States)

    Scott, C.; Gregg, C. E.; Ritchie, L.; Stephen, M.; Farnham, C.; Fraser, S. A.; Gill, D.; Horan, J.; Houghton, B. F.; Johnson, V.; Johnston, D.

    2013-12-01

    The National Tsunami Hazard Mitigation Program (NTHMP) partnered with the National Weather Service (NWS) in early 2000 to create the TsunamiReadyTM Community Recognition program. TsunamiReadyTM, modeled after the older NWS StormReadyTM program, is designed to help cities, towns, counties, universities and other large sites in coastal areas reduce the potential for disastrous tsunami-related consequences. To achieve TsunamiReadyTM recognition, communities must meet certain criteria aimed at better preparing a community for tsunami, including specific actions within the following categories: communications and coordination, tsunami warning reception, local warning dissemination, community preparedness, and administration. Using multidisciplinary research methods and strategies from Public Health; Psychology; Political, Social and Physical Sciences and Evaluation, our research team is working directly with a purposive sample of community stakeholders in collaboration and feedback focus group sessions. Invitation to participate is based on a variety of factors including but not limited to an individual's role as a formal or informal community leader (e.g., in business, government, civic organizations), or their organization or agency affiliation to emergency management and response. Community organizing and qualitative research methods are being used to elicit discussion regarding TsunamiReadyTM requirements and the division of requirements based on some aspect of tsunami hazard, vulnerability and risk, such as proximity to active or passive plate margins or subduction zone generated tsunamis versus earthquake-landslide generated tsunamis . The primary aim of this research is to use social science to revise and refine the NWS TsunamiReadyTM Guidelines in an effort to better prepare communities to reduce risk to tsunamis.

  20. HESCOMP. The Helicopter Sizing and Performance Computer Program. User’s Manual. Revision 2.

    Science.gov (United States)

    1979-10-01

    uruieGlwChr)Pr f7 GO TO4100 ja I IDS CXS!G-CXS!GL* (1 CXS!G;I.CXS!G ~~~~ IF.X.T I X. NE. 0) jrWRTEi6.q90u IF XOL2MT(I)- CXS!G/CTPSL XCT2ILq II CTPSL 660...1 AO F ( F7 ~ ~ ~ 1 -I-3weN C3 77 C e0uffM~m1~asa~Y ~ rC -13 cS., 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ G 7CI4I*11t~~l~ I TI.V’,ITt- Figure 4-62. PARA Function, Flow...7-255 L C4SA. a ACA ANA ACCA I r- I r4. .m Q. . 7.f kJim p41 oml Ni Nii ’e N~6 a. aQa OL a -0 c .. -7 4.;- C~ 4c>.Q a,1 ci ~ ~ % a cam p- F. . a a a

  1. STREAM II-V7: Revision for STREAM II-V6 to include outflow from all Savannah River Site tributaries

    Energy Technology Data Exchange (ETDEWEB)

    Maze, Grace M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2017-01-01

    STREAM II is the aqueous transport model of the Weather Information Display (WIND) emergency response system at Savannah River Site. It is used to calculate transport in the event of a chemical or radiological spill into the waterways on the Savannah River Site. Improvements were made to the code (STREAM II V7) to include flow from all site tributaries to the Savannah River total flow and utilize a 4 digit year input. The predicted downstream concentrations using V7 were generally on the same order of magnitude as V6 with slightly lower concentrations and quicker arrival times when all onsite stream flows are contributing to the Savannah River flow. The downstream arrival time at the Savannah River Water Plant ranges from no change to an increase of 8.77%, with minimum changes typically in March/April and maximum changes typically in October/November. The downstream concentrations are generally no more than 15% lower using V7 with the maximum percent change in January through April and minimum changes in June/July.

  2. R ampersand D plan for immobilization technologies: fissile materials disposition program. Revision 1.0

    International Nuclear Information System (INIS)

    Shaw, H.F.; Armantrout, G.A.

    1996-09-01

    In the aftermath of the Cold War, the US and Russia have agreed to large reductions in nuclear weapons. To aid in the selection of long- term fissile material management options, the Department of Energy's Fissile Materials Disposition Program (FMDP) is conducting studies of options for the storage and disposition of surplus plutonium (Pu). One set of alternatives for disposition involve immobilization. The immobilization alternatives provide for fixing surplus fissile materials in a host matrix in order to create a solid disposal form that is nuclear criticality-safe, proliferation-resistant and environmentally acceptable for long-term storage or disposal

  3. Energy extension service pilot program evaluation report: the first year. Volume II: pilot state reports

    Energy Technology Data Exchange (ETDEWEB)

    1979-09-01

    Volume II of the Energy Extension Service Evaluation presents a discussion of the operations of the ten EES pilot-state programs during the period from October 1, 1977 through September 30, 1978. Each of the ten pilot states - Alabama, Connecticut, Michigan, New Mexico, Pennsylvania, Tennessee, Texas, Washington, Wisconsin, and Wyoming - received a grant of approximately $1.1 million to develop and implement a 19-month program beginning on October 1, 1977. Volume II provides a case-study description of the operations of the pilot program in each state, with special attention given to the two programs selected in each state for more detailed study and survey research. Some survey data and analysis are presented for the emphasis programs.

  4. The EBR-II spent fuel treatment program

    International Nuclear Information System (INIS)

    Lineberry, M.J.; McFarlane, H.F.

    1995-01-01

    Argonne National Laboratory has refurbished and equipped an existing hot cell facility for demonstrating a high-temperature electrometallurgical process for treating spent nuclear fuel from the Experimental Breeder Reactor-11. Two waste forms will be produced and qualified for geologic disposal of the fission and activation products. Relatively pure uranium will be separated for storage. Following additional development, transuranium elements will be blended into one of the high-level waste streams. The spent fuel treatment program will help assess the viability of electrometallurgical technology as a spent fuel management option

  5. Human Health Countermeasures (HHC) Element Management Plan: Human Research Program. Revision B

    Science.gov (United States)

    Norsk, Peter; Baumann, David

    2012-01-01

    NASA s Human Research Program (HRP) is an applied research and technology program within the Human Exploration and Operations Mission Directorate (HEOMD) that addresses human health and performance risk mitigation strategies in support of exploration missions. The HRP research and technology development is focused on the highest priority risks to crew health and safety with the goal of ensuring mission success and maintaining long-term crew health. Crew health and performance standards, defined by the NASA Chief Health and Medical Officer (CHMO), set the acceptable risk level for exploration missions. The HRP conducts research to inform these standards as well as provide deliverables, such as countermeasures, that ensure standards can be met to maximize human performance and mission success. The Human Health Countermeasures (HHC) Element was formed as part of the HRP to develop a scientifically-based, integrated approach to understanding and mitigating the health risks associated with human spaceflight. These health risks have been organized into four research portfolios that group similar or related risks. A fifth portfolio exists for managing technology developments and infrastructure projects. The HHC Element portfolios consist of: a) Vision and Cardiovascular; b) Exercise and Performance; c) Multisystem; d) Bone; and e) Technology and Infrastructure. The HHC identifies gaps associated with the health risks and plans human physiology research that will result in knowledge required to more fully understand risks and will result in validated countermeasures to mitigate risks.

  6. Next Generation Nuclear Plant Materials Research and Development Program Plan, Revision 4

    Energy Technology Data Exchange (ETDEWEB)

    G.O. Hayner; R.L. Bratton; R.E. Mizia; W.E. Windes; W.R. Corwin; T.D. Burchell; C.E. Duty; Y. Katoh; J.W. Klett; T.E. McGreevy; R.K. Nanstad; W. Ren; P.L. Rittenhouse; L.L. Snead; R.W. Swindeman; D.F. Wlson

    2007-09-01

    DOE has selected the High Temperature Gas-cooled Reactor (HTGR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production. It will have an outlet gas temperature in the range of 950°C and a plant design service life of 60 years. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed reactor and use low-enriched uranium, TRISO-coated fuel. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Materials Research and Development (R&D) Program is responsible for performing R&D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. Some of the general and administrative aspects of the R&D Plan include: • Expand American Society of Mechanical Engineers (ASME) Codes and American Society for Testing and Materials (ASTM) Standards in support of the NGNP Materials R&D Program. • Define and develop inspection needs and the procedures for those inspections. • Support selected university materials related R&D activities that would be of direct benefit to the NGNP Project. • Support international materials related collaboration activities through the DOE sponsored Generation IV International Forum (GIF) Materials and Components (M&C) Project Management Board (PMB). • Support document review activities through the Materials Review Committee (MRC) or other suitable forum.

  7. The Soviet program for peaceful uses of nuclear explosions. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Nordyke, M.D.

    1996-10-01

    An extensive review is given of the US and Russian efforts on peaceful uses of nuclear explosions (PNE). The Soviet PNE program was many times larger than the US Plowshare program in terms of both the number of applications explored with field experiments and the extent to which they were introduced into industrial use. Several PNE applications, such as deep seismic sounding and oil stimulation, have been explored in depth and appear to have had a positive cost benefit at minimal public risk. Closure of runaway gas wells is another possible application where all other techniques fail. However, the fundamental problem with PNEs is the fact that, if they are to be economically significant, there must be widespread use of the technology, involving large numbers of sites, each of which presents a potential source of radioactivity to the environment and nearby communities. Russia now has more than 100 sites where significant high-level radioactivity has been buried. Experience over the last 20 years in US and in today`s Russia shows that it is virtually impossible to gain public acceptance of such applications of nuclear energy. In addition, PNEs also pose a difficult problem in the arms control area. Under a comprehensive test ban, any country conducting PNEs would, in appearance if not in fact, receive information useful for designing new nuclear weapons or maintaining an existing nuclear stockpile, information denied to the other parties to the treaty. 6 tabs, 10 figs.

  8. Seismic II over I Drop Test Program results and interpretation

    Energy Technology Data Exchange (ETDEWEB)

    Thomas, B.

    1993-03-01

    The consequences of non-seismically qualified (Category 2) objects falling and striking essential seismically qualified (Category 1) objects has always been a significant, yet analytically difficult problem, particularly in evaluating the potential damage to equipment that may result from earthquakes. Analytical solutions for impact problems are conservative and available for mostly simple configurations. In a nuclear facility, the {open_quotes}sources{close_quotes} and {open_quotes}targets{close_quotes} requiring evaluation are frequently irregular in shape and configuration, making calculations and computer modeling difficult. Few industry or regulatory rules are available on this topic even though it is a source of considerable construction upgrade costs. A drop test program was recently conducted to develop a more accurate understanding of the consequences of seismic interactions. The resulting data can be used as a means to improve the judgment of seismic qualification engineers performing interaction evaluations and to develop realistic design criteria for seismic interactions. Impact tests on various combinations of sources and targets commonly found in one Savannah River Site (SRS) nuclear facility were performed by dropping the sources from various heights onto the targets. This report summarizes results of the Drop Test Program. Force and acceleration time history data are presented as well as general observations on the overall ruggedness of various targets when subjected to impacts from different types of sources.

  9. Seismic II over I Drop Test Program results and interpretation

    Energy Technology Data Exchange (ETDEWEB)

    Thomas, B.

    1993-03-01

    The consequences of non-seismically qualified (Category 2) objects falling and striking essential seismically qualified (Category 1) objects has always been a significant, yet analytically difficult problem, particularly in evaluating the potential damage to equipment that may result from earthquakes. Analytical solutions for impact problems are conservative and available for mostly simple configurations. In a nuclear facility, the [open quotes]sources[close quotes] and [open quotes]targets[close quotes] requiring evaluation are frequently irregular in shape and configuration, making calculations and computer modeling difficult. Few industry or regulatory rules are available on this topic even though it is a source of considerable construction upgrade costs. A drop test program was recently conducted to develop a more accurate understanding of the consequences of seismic interactions. The resulting data can be used as a means to improve the judgment of seismic qualification engineers performing interaction evaluations and to develop realistic design criteria for seismic interactions. Impact tests on various combinations of sources and targets commonly found in one Savannah River Site (SRS) nuclear facility were performed by dropping the sources from various heights onto the targets. This report summarizes results of the Drop Test Program. Force and acceleration time history data are presented as well as general observations on the overall ruggedness of various targets when subjected to impacts from different types of sources.

  10. Seismic II over I Drop Test Program results and interpretation

    International Nuclear Information System (INIS)

    Thomas, B.

    1993-03-01

    The consequences of non-seismically qualified (Category 2) objects falling and striking essential seismically qualified (Category 1) objects has always been a significant, yet analytically difficult problem, particularly in evaluating the potential damage to equipment that may result from earthquakes. Analytical solutions for impact problems are conservative and available for mostly simple configurations. In a nuclear facility, the open-quotes sourcesclose quotes and open-quotes targetsclose quotes requiring evaluation are frequently irregular in shape and configuration, making calculations and computer modeling difficult. Few industry or regulatory rules are available on this topic even though it is a source of considerable construction upgrade costs. A drop test program was recently conducted to develop a more accurate understanding of the consequences of seismic interactions. The resulting data can be used as a means to improve the judgment of seismic qualification engineers performing interaction evaluations and to develop realistic design criteria for seismic interactions. Impact tests on various combinations of sources and targets commonly found in one Savannah River Site (SRS) nuclear facility were performed by dropping the sources from various heights onto the targets. This report summarizes results of the Drop Test Program. Force and acceleration time history data are presented as well as general observations on the overall ruggedness of various targets when subjected to impacts from different types of sources

  11. U.S. Department of Energy Region 6 Radiological Assistance Program response plan. Revision 2

    International Nuclear Information System (INIS)

    Jakubowski, F.M.

    1998-02-01

    Upon request, the DOE, through the Radiological Assistance Program (RAP), makes available and will provide radiological advice, monitoring, and assessment activities during radiological incidents where the release of radioactive materials is suspected or has occurred. Assistance will end when the need for such assistance is over, or if there are other resources available to adequately address the incident. The implementation of the RAP is usually accomplished through the recommendation of the DOE Regional Coordinating Office's (RCO) on duty Regional Response Coordinator (RRC) with the approval of the Regional Coordinating Office Director (RCOD). The DOE Idaho Operations Office (DOE-ID) is the designated RCO for DOE Region 6 RAP. The purpose of this document is: to describe the mechanism for responding to any organization or private citizen requesting assistance to radiological incidents; to coordinate radiological assistance among participating federal agencies, states, and tribes in DOE Region 6; and to describe the RAP Scaled Response concept of operations

  12. Human Research Program Unique Processes, Criteria, and Guidelines (UPCG). Revision C, July 28, 2011

    Science.gov (United States)

    Chin, Duane

    2011-01-01

    This document defines the processes, criteria, and guidelines exclusive to managing the Human Research Program (HRP). The intent of this document is to provide instruction to the reader in the form of processes, criteria, and guidelines. Of the three instructional categories, processes contain the most detail because of the need for a systematic series of actions directed to some end. In contrast, criteria have lesser detail than processes with the idea of creating a rule or principle structure for evaluating or testing something. Guidelines are a higher level indication of a course of action typically with the least amount of detail. The lack of detail in guidelines allows the reader flexibility when performing an action or actions.

  13. Permanent certification program for health information technology; revisions to ONC-Approved Accreditor processes. Final rule.

    Science.gov (United States)

    2011-11-25

    Under the authority granted to the National Coordinator for Health Information Technology by section 3001(c)(5) of the Public Health Service Act (PHSA) as added by the Health Information Technology for Economic and Clinical Health (HITECH) Act, this final rule establishes a process for addressing instances where the ONC-Approved Accreditor (ONC-AA) engages in improper conduct or does not perform its responsibilities under the permanent certification program. This rule also addresses the status of ONC-Authorized Certification Bodies (ONC-ACBs) in instances where there may be a change in the accreditation organization serving as the ONC-AA and clarifies the responsibilities of the new ONC-AA.

  14. Quality assurance program plan for the Site Physical and Electrical Calibration Services Lab. Revision 1

    International Nuclear Information System (INIS)

    Carpenter, C.A.

    1995-01-01

    This Quality Assurance Program Plan (QAPP) is organized to address WHC's implementation of quality assurance requirements as they are presented as interpretive guidance endorsed by the Department of Energy (DOE) Field Office, Richland DOE Order 5700.6C Quality Assurance. The quality assurance requirements presented in this plan will assure Measuring and Test Equipment (M and TE) are in conformance with prescribed technical requirements and that data provided by testing, inspection, or maintenance are valid. This QAPP covers all activities and work elements that are variously called QA, quality control, and quality engineering regardless of the organization performing the work. This QAPP identifies the QA requirements for planning, control, and documentation of operations, modifications, and maintenance of the WHC Site Physical and Electrical Calibration Services Laboratory. The primary function of the WHC Site Physical and Electrical Calibration Services Laboratory is providing calibration, standardization, or repair service of M and TE

  15. Solving a bi-objective vehicle routing problem under uncertainty by a revised multi-choice goal programming approach

    Directory of Open Access Journals (Sweden)

    Hossein Yousefi

    2017-06-01

    Full Text Available A vehicle routing problem with time windows (VRPTW is an important problem with many real applications in a transportation problem. The optimum set of routes with the minimum distance and vehicles used is determined to deliver goods from a central depot, using a vehicle with capacity constraint. In the real cases, there are other objective functions that should be considered. This paper considers not only the minimum distance and the number of vehicles used as the objective function, the customer’s satisfaction with the priority of customers is also considered. Additionally, it presents a new model for a bi-objective VRPTW solved by a revised multi-choice goal programming approach, in which the decision maker determines optimistic aspiration levels for each objective function. Two meta-heuristic methods, namely simulated annealing (SA and genetic algorithm (GA, are proposed to solve large-sized problems. Moreover, the experimental design is used to tune the parameters of the proposed algorithms. The presented model is verified by a real-world case study and a number of test problems. The computational results verify the efficiency of the proposed SA and GA.

  16. Heavy Section Steel Technology Program. Part II. Intermediate vessel testing

    International Nuclear Information System (INIS)

    Whitman, G.D.

    1975-01-01

    The testing of the intermediate pressure vessels is a major activity under the Heavy Section Steel Technology Program. A primary objective of these tests is to develop or verify methods of fracture prediction, through the testing of selected structures and materials, in order that a valid basis can be established for evaluating the serviceability and safety of light-water reactor pressure vessels. These vessel tests were planned with sufficiently specific objectives that substantial quantitative weight could be given to the results. Each set of testing conditions was chosen so as to provide specific data by which analytical methods of predicting flaw growth, and in some cases crack arrest, could be evaluated. Every practical effort was made to assure that results would be relevant to some aspect of real reactor pressure vessel performance through careful control of material properties, selection of test temperatures, and design of prepared flaws. 5 references

  17. Notification of tuberculosis cases in India: Moving ahead in Revised National Tuberculosis Control Program

    Directory of Open Access Journals (Sweden)

    Saurabh RamBihariLal Shrivastava

    2013-11-01

    Full Text Available Tuberculosis (TB is currently the leading cause of death from a curable infectious disease accounting for 8.7 million new cases and 1.4 million deaths in the year 2011. From the year 2012, TB is a notifiable disease in India which means that all cases of TB diagnosed by any means has to be reported to the public health authorities. This would help policy makers to make rational decisions with regard to strengthening of existing infrastructure and scaling-up of TB control activities in the country. Employment of multiple measures directed towards different stakeholders can be strategically implemented to intensify and fast-track the process of TB notification. In conclusion, the Indian Government's decision to specify TB as a notifiable disease is a historical and a much awaited step in the TB control activities. However to obtain the desired results, program managers along with the health care workers have to work in an integrated and collaborative manner so that the burden of TB can be reduced in years to come.

  18. PR-EDB: Power Reactor Embrittlement Data Base, Version 2. Revision 2, Program description

    Energy Technology Data Exchange (ETDEWEB)

    Stallmann, F.W.; Wang, J.A.; Kam, F.B.K.; Taylor, B.J. [Oak Ridge National Lab., TN (United States)

    1994-01-01

    Investigations of regulatory issues such as vessel integrity over plant life, vessel failure, and sufficiency of current codes Standard Review Plans (SRP`s) and Guides for license renewal can be greatly expedited by the use of a well-designed computerized data base. Also, such a data base is essential for the validation of embrittlement prediction models by researchers. The Power Reactor Embrittlement Data Base (PR-EDB) is such a comprehensive collection of data for US commercial nuclear reactors. The current version of the PR-EDB contains the Charpy test data that were irradiated in 252 capsules of 96 reactors and consists of 207 data points for heat-affected-zone (HAZ) materials (98 different HAZ), 227 data points for weld materials (105 different welds), 524 data points for base materials (136 different base materials), including 297 plate data points (85 different plates), 119 forging data points (31) different forging), and 108 correlation monitor materials data points (3 different plates). The data files are given in dBASE format and can be accessed with any computer using the DOS operating system. ``User-friendly`` utility programs are used to retrieve and select specific data, manipulate data, display data to the screen or printer, and to fit and plot Charpy impact data. The results of several studies investigated are presented in Appendix D.

  19. INTERLINE 5.0 -- An expanded railroad routing model: Program description, methodology, and revised user's manual

    International Nuclear Information System (INIS)

    Johnson, P.E.; Joy, D.S.; Clarke, D.B.; Jacobi, J.M.

    1993-03-01

    A rail routine model, INTERLINE, has been developed at the Oak Ridge National Laboratory to investigate potential routes for transporting radioactive materials. In Version 5.0, the INTERLINE routing algorithms have been enhanced to include the ability to predict alternative routes, barge routes, and population statistics for any route. The INTERLINE railroad network is essentially a computerized rail atlas describing the US railroad system. All rail lines, with the exception of industrial spurs, are included in the network. Inland waterways and deep water routes along with their interchange points with the US railroadsystem are also included. The network contains over 15,000 rail and barge segments (links) and over 13,000 stations, interchange points, ports, and other locations (nodes). The INTERLINE model has been converted to operate on an IBM-compatible personal computer. At least a 286 computer with a hard disk containing approximately 6 MB of free space is recommended. Enhanced program performance will be obtained by using arandom-access memory drive on a 386 or 486 computer

  20. Revised VESCAL: Vessel calibration data analysis program. Improvement of a model for non-linear parts of annular and slab tanks

    International Nuclear Information System (INIS)

    Yanagisawa, Hiroshi

    1995-05-01

    For the purpose of the nuclear material accountancy and control for NUCEF: the Nuclear Fuel Cycle Safety Engineering Research Facility, the vessel calibration data analysis program: VESCAL is revised, and a new model for non-linear parts of annular and slab tanks is added to the program. The new model has three unknown parameters, and liquid level is expressed as a square root function with respect to liquid volume. Using the new model, an accurate calibration function on the level and volume data for non-linear parts of annular and slab tanks can be obtained with the smaller number of unknown parameters, compared with a polynomial function model. As a result of benchmark tests for this revision, it was proved that numerical results computed with VESCAL well agreed with those by a statistical analysis program package which is widely used. In addition, the new model would be useful for carrying out data analyses on the vessel calibration at the other bulk handling facilities as well as at NUCEF. This paper describes summary of the program, computational methods and results of benchmark tests concerning this revision. (author)

  1. Updated Generation IV Reactors Integrated Materials Technology Program Plan, Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Corwin, William R [ORNL; Burchell, Timothy D [ORNL; Halsey, William [Lawrence Livermore National Laboratory (LLNL); Hayner, George [Idaho National Laboratory (INL); Katoh, Yutai [ORNL; Klett, James William [ORNL; McGreevy, Timothy E [ORNL; Nanstad, Randy K [ORNL; Ren, Weiju [ORNL; Snead, Lance Lewis [ORNL; Stoller, Roger E [ORNL; Wilson, Dane F [ORNL

    2005-12-01

    The Department of Energy's (DOE's) Generation IV Nuclear Energy Systems Program will address the research and development (R&D) necessary to support next-generation nuclear energy systems. Such R&D will be guided by the technology roadmap developed for the Generation IV International Forum (GIF) over two years with the participation of over 100 experts from the GIF countries. The roadmap evaluated over 100 future systems proposed by researchers around the world. The scope of the R&D described in the roadmap covers the six most promising Generation IV systems. The effort ended in December 2002 with the issue of the final Generation IV Technology Roadmap [1.1]. The six most promising systems identified for next generation nuclear energy are described within the roadmap. Two employ a thermal neutron spectrum with coolants and temperatures that enable hydrogen or electricity production with high efficiency (the Supercritical Water Reactor - SCWR and the Very High Temperature Reactor - VHTR). Three employ a fast neutron spectrum to enable more effective management of actinides through recycling of most components in the discharged fuel (the Gas-cooled Fast Reactor - GFR, the Lead-cooled Fast Reactor - LFR, and the Sodium-cooled Fast Reactor - SFR). The Molten Salt Reactor (MSR) employs a circulating liquid fuel mixture that offers considerable flexibility for recycling actinides, and may provide an alternative to accelerator-driven systems. A few major technologies have been recognized by DOE as necessary to enable the deployment of the next generation of advanced nuclear reactors, including the development and qualification of the structural materials needed to ensure their safe and reliable operation. Accordingly, DOE has identified materials as one of the focus areas for Gen IV technology development.

  2. Reference methodologies for radioactive controlled discharges an activity within the IAEA's Program Environmental Modelling for Radiation Safety II (EMRAS II)

    International Nuclear Information System (INIS)

    Stocki, T.J.; Bergman, L.; Tellería, D.M.; Proehl, G.; Amado, V.; Curti, A.; Bonchuk, I.; Boyer, P.; Mourlon, C.; Chyly, P.; Heling, R.; Sági, L.; Kliaus, V.; Krajewski, P.; Latouche, G.; Lauria, D.C.; Newsome, L.; Smith, J.

    2011-01-01

    In January 2009, the IAEA EMRAS II (Environmental Modelling for Radiation Safety II) program was launched. The goal of the program is to develop, compare and test models for the assessment of radiological impacts to the public and the environment due to radionuclides being released or already existing in the environment; to help countries build and harmonize their capabilities; and to model the movement of radionuclides in the environment. Within EMRAS II, nine working groups are active; this paper will focus on the activities of Working Group 1: Reference Methodologies for Controlling Discharges of Routine Releases. Within this working group environmental transfer and dose assessment models are tested under different scenarios by participating countries and the results compared. This process allows each participating country to identify characteristics of their models that need to be refined. The goal of this working group is to identify reference methodologies for the assessment of exposures to the public due to routine discharges of radionuclides to the terrestrial and aquatic environments. Several different models are being applied to estimate the transfer of radionuclides in the environment for various scenarios. The first phase of the project involves a scenario of nuclear power reactor with a coastal location which routinely (continuously) discharges 60Co, 85Kr, 131I, and 137Cs to the atmosphere and 60Co, 137Cs, and 90Sr to the marine environment. In this scenario many of the parameters and characteristics of the representative group were given to the modelers and cannot be altered. Various models have been used by the different participants in this inter-comparison (PC-CREAM, CROM, IMPACT, CLRP POSEIDON, SYMBIOSE and others). This first scenario is to enable a comparison of the radionuclide transport and dose modelling. These scenarios will facilitate the development of reference methodologies for controlled discharges. (authors)

  3. Medicare and Medicaid programs: Hospital Outpatient Prospective Payment and Ambulatory Surgical Center Payment Systems and Quality Reporting Programs; electronic reporting pilot; Inpatient Rehabilitation Facilities Quality Reporting Program; revision to Quality Improvement Organization regulations. Final rule with comment period.

    Science.gov (United States)

    2012-11-15

    This final rule with comment period revises the Medicare hospital outpatient prospective payment system (OPPS) and the Medicare ambulatory surgical center (ASC) payment system for CY 2013 to implement applicable statutory requirements and changes arising from our continuing experience with these systems. In this final rule with comment period, we describe the changes to the amounts and factors used to determine the payment rates for Medicare services paid under the OPPS and those paid under the ASC payment system. In addition, this final rule with comment period updates and refines the requirements for the Hospital Outpatient Quality Reporting (OQR) Program, the ASC Quality Reporting (ASCQR) Program, and the Inpatient Rehabilitation Facility (IRF) Quality Reporting Program. We are continuing the electronic reporting pilot for the Electronic Health Record (EHR) Incentive Program, and revising the various regulations governing Quality Improvement Organizations (QIOs), including the secure transmittal of electronic medical information, beneficiary complaint resolution and notification processes, and technical changes. The technical changes to the QIO regulations reflect CMS' commitment to the general principles of the President's Executive Order on Regulatory Reform, Executive Order 13563 (January 18, 2011).

  4. Mortality in severe trauma patients attended by emergency services in Navarre, Spain: validation of a new prediction model and comparison with the Revised Injury Severity Classification Score II.

    Science.gov (United States)

    Ali Ali, Bismil; Lefering, Rolf; Fortún Moral, Mariano; Belzunegui Otano, Tomás

    2018-01-01

    To validate the Mortality Prediction Model of Navarre (MPMN) to predict death after severe trauma and compare it to the Revised Injury Severity Classification Score II (RISCII). Retrospective analysis of a cohort of severe trauma patients (New Injury Severity Score >15) who were attended by emergency services in the Spanish autonomous community of Navarre between 2013 and 2015. The outcome variable was 30-day all-cause mortality. Risk was calculated with the MPMN and the RISCII. The performance of each model was assessed with the area under the receiver operating characteristic (ROC) curve and precision with respect to observed mortality. Calibration was assessed with the Hosmer-Lemeshow test. We included 516 patients. The mean (SD) age was 56 (23) years, and 363 (70%) were males. Ninety patients (17.4%) died within 30 days. The 30-day mortality rates predicted by the MPMN and RISCII were 16.4% and 15.4%, respectively. The areas under the ROC curves were 0.925 (95% CI, 0.902-0.952) for the MPMN and 0.941 (95% CI, 0.921-0.962) for the RISCII (P=0.269, DeLong test). Calibration statistics were 13.6 (P=.09) for the MPMN and 8.9 (P=.35) for the RISCII. Both the MPMN and the RISCII show good ability to discriminate risk and predict 30-day all-cause mortality in severe trauma patients.

  5. F-35 Lightning II Joint Strike Fighter (JSF) Program: Background, Status, and Issues

    National Research Council Canada - National Science Library

    Bolkcom, Christopher; Murch, Anthony

    2008-01-01

    The Defense Department's F-35 Lightning II Joint Strike Fighter (JSF) is one of three aircraft modernization programs in tactical aviation, the others being the Air Force F-22A fighter and the Navy F/A-18E/F fighter/attack plane...

  6. F-35 Lightning II Joint Strike Fighter "JSF" Program: Background, Status, and Issues

    National Research Council Canada - National Science Library

    Murch, Anthony; Bolkcom, Christopher

    2007-01-01

    The Defense Department's F-35 Lightning II Joint Strike Fighter (JSF) is one of three aircraft modernization programs in tactical aviation, the others being the Air Force F-22A fighter and the Navy F/A-18E/F fighter/attack plane...

  7. F-35 Lightning II Joint Strike Fighter (JSF) Program: Background, Status, and Issues

    National Research Council Canada - National Science Library

    Bolkcom, Christopher

    2009-01-01

    The Defense Department's F-35 Lightning II Joint Strike Fighter (JSF) is one of three aircraft modernization programs in tactical aviation, the others being the Air Force F-22A fighter and the Navy F/A-18E/F fighter/attack plane...

  8. Proceedings of the 1995 U.S. DOE hydrogen program review. Volume II

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    The 1995 US DOE Hydrogen Program Review was held April 18-21, 1995 in Coral Gables, FL. Volume II of the Proceedings contains 8 papers presented under the subject of hydrogen storage and 17 papers presented on hydrogen production. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

  9. LLUVIA-II: A program for two-dimensional, transient flow through partially saturated porous media

    International Nuclear Information System (INIS)

    Eaton, R.R.; Hopkins, P.L.

    1992-08-01

    LLUVIA-II is a program designed for the efficient solution of two- dimensional transient flow of liquid water through partially saturated, porous media. The code solves Richards equation using the method-of-lines procedure. This document describes the solution procedure employed, input data structure, output, and code verification

  10. Evaluating the Influence of the Revised Special Supplemental Nutrition Program for Women, Infants, and Children (WIC) Food Allocation Package on Healthy Food Availability, Accessibility, and Affordability in Texas.

    Science.gov (United States)

    Lu, Wenhua; McKyer, E Lisako J; Dowdy, Diane; Evans, Alexandra; Ory, Marcia; Hoelscher, Deanna M; Wang, Suojin; Miao, Jingang

    2016-02-01

    The Special Supplemental Nutrition Program for Women, Infants, and Children (WIC) was implemented to improve the health of pregnant women and children of low socioeconomic status. In 2009, the program was revised to provide a wider variety of healthy food choices (eg, fresh fruits, vegetables, and whole-grain items). The purpose of this study was to evaluate (1) the impact of the revised WIC Nutrition Program's food allocation package on the availability, accessibility, and affordability of healthy foods in WIC-authorized grocery stores in Texas; and (2) how the impact of the policy change differed by store types and between rural and urban regions. WIC-approved stores (n=105) across Texas were assessed using a validated instrument (88 items). Pre- (June-September 2009) and post-new WIC package implementation (June-September 2012) audits were conducted. Paired-sample t tests were conducted to compare the differences between pre- and post-implementation audits on shelf width and number of varieties (ie, availability), visibility (ie, accessibility), and inflation-adjusted price (ie, affordability). Across the 105 stores, post-implementation audits showed increased availability in terms of shelf space for most key healthy food options, including fruit (PFood visibility increased for fresh juices (Pfoods such as fruits (Pbread (Pbread (Pfood availability and visibility were observed in stores of different types and in different locations, although smaller or fewer effects were noted in small stores and stores in rural regions. Implementation of the revised WIC food package has generally improved availability and accessibility, but not affordability, of healthy foods in WIC-authorized stores in Texas. Future studies are needed to explore the impact of the revised program on healthy food option purchases and consumption patterns among Texas WIC participants. Copyright © 2016 Academy of Nutrition and Dietetics. Published by Elsevier Inc. All rights reserved.

  11. A revision of the Cormack and Lehane laryngoscopic grading system with special consideration to grade II laryngoscopic view

    Directory of Open Access Journals (Sweden)

    Hussain khan Z

    2007-10-01

    Full Text Available Background: The major responsibility of an anesthesiologist is to provide adequate respiration for the patient. The most vital element in providing functional respiration is the airway. No anesthetic is safe unless diligent efforts are devoted to maintaining an intact functional airway. Difficult intubation had been classified into four grades, according to the view obtainable at laryngoscopy by Cormack and Lehane in 1984. This grading system has been in use to evaluate and manage those patients with difficult airway by anesthesiologists. In clinical state, grades III and IV are quite rare, so the need for a modified Cormack and Lehane grading system was felt. The use of a modified Cormack-Lehane scoring system of laryngoscopic views during direct laryngoscopy, was previously examined in the Western population. Koh and his co-workers had examined this modified Cormack and Lehane grading system in Asian population in a study in Singapore General Hospital. The aim of this study was to investigate this scoring system in Iranian patients.Methods: In a cross sectional study, a modified version of the Cormack and Lehane grading system was evaluated in 300 patients requiring tracheal intubation. In the modified system, grade II (only part of the glottis is visible was divided into IIa (part of the cords is visible and IIb (only the arytenoids or the very posterior origin of the cords are visible. Difficult intubation was defined as requiring more than one laryngoscopy or the use of special equipments.Results: Sixty eight patients (22.7% were scored as grade IIa and 32 (7.7% as grade IIb. The prevalence of difficult intubation in grade IIb was significantly higher than patients in group IIa (47.8% vs. 2.9% respectively, Fisher's exact test, p= 0.001Conclusion: The modified grading system provides more information than the original Cormack and Lehane system."n 

  12. Impact of a community based implementation of REACH II program for caregivers of Alzheimer's patients.

    Directory of Open Access Journals (Sweden)

    Kristine Lykens

    Full Text Available BACKGROUND: In 2009 an estimated 5.3 million people in the United States were afflicted with Alzheimer's disease, a degenerative form of dementia. The impact of this disease is not limited to the patient but also has significant impact on the lives and health of their family caregivers. The Resources for Enhancing Alzheimer's Caregiver Health (REACH II program was developed and tested in clinical studies. The REACH II program is now being delivered by community agencies in several locations. This study examines the impact of the REACH II program on caregiver lives and health in a city in north Texas. STUDY DESIGN: Family caregivers of Alzheimer's patients were assessed using an instrument covering the multi-item domains of Caregiver Burden, Depression, Self-Care, and Social Support upon enrollment in the program and at the completion of the 6 month intervention. The domain scores were analyzed using a multivariate paired t-test and Bonferroni confidence interval for the differences in pre- and post-service domain scores. RESULTS: A total of 494 families were enrolled in the program during the period January 1, 2011 through June 30, 2012. Of these families 177 completed the 6 month program and have pre - and post service domain scores. The median age for the caregivers was 62 years. The domain scores for Depression and Caregiver Burden demonstrated statistically significant improvements upon program completion. CONCLUSION: The REACH II intervention was successfully implemented by a community agency with comparable impacts to those of the clinical trial warranting wider scale implementation.

  13. Report on the phase II R and D program of magneto-hydro-dynamics (MHD) electrical power generation. Prompt report by Electrotechnical Laboratory; Denji ryutai (MHD) hatsuden no dainiki kenkyu kaihatsu ni kansuru hokokusho. Densoken kenkyu sokuho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1989-07-28

    This report summarizes results of the phase II R and D program of MHD electrical power generation (FY 1976 - 1983), which has been now completed. The phase II R and D efforts were concentrated on development of the durable power generation channels, where the designs and manufacture of the Mark II system were started, and the elementary techniques were simultaneously studied for, e.g., phenomena occurring around the electrodes, seed condensation and its effects on the electrode phenomena, and electrode and insulator materials for the power generation channels. The power generation channel was tested for its durability for a total of 430 hours, after it was incorporated in the Mark II system. The MHD power generation can incorporate direct combustion of coal, and will hold a dominant position in coal-fired power generation, which is expected to grow in the future. For this reason, the basic research schedules were revised in March, 1983, and the Mark II system was operated by firing a mixed fuel of kerosene and finely divided coal in a kerosene combustor, in line with the revised project, to understand the basic power generation characteristics with the combustion gases containing coal slag. (NEDO)

  14. OR TEP-II: a FORTRAN Thermal-Ellipsoid Plot Program for crystal structure illustrations

    International Nuclear Information System (INIS)

    Johnson, C.K.

    1976-03-01

    A computer program is described for drawing crystal structure illustrations using a mechanical plotter. Ball-and-stick type illustrations of a quality suitable for publication are produced with either spheres or thermal-motion probability ellipsoids on the atomic sites. The program can produce stereoscopic pairs of illustrations which aid in the visualization of complex packing arrangements of atoms and thermal motion patterns. Interatomic distances, bond angles, and principal axes of thermal motion are also calculated to aid the structural study. The most recent version of the program, OR TEP-II, has a hidden-line-elimination feature to omit those portions of atoms or bonds behind other atoms or bonds

  15. Proceedings of the first analysis meeting on JUPITER-II Program

    Energy Technology Data Exchange (ETDEWEB)

    Shiradata, Keisho; Yamamoto, Masaaki [comps.

    1984-12-31

    The JUPITER-II Program is the Joint Physics Large Heterogeneous Core Critical Experiments Program between the U.S. Department of Energy (US DOE) and PNC, Japan. The experiments began in May 1982 and ended in April 1984, as a part of the ZPPR-13 program. The ZPPR-13 is a series of critical assemblies designed to study the fundamental neutronic behavior of large, radially-heterogeneous LMFBR cores. This report describes the results of analysis of ZPPR-13A and preliminary analysis of ZPPR-13B, and some topics of recent activities in fast reactor physics.

  16. Proceedings of the first analysis meeting on JUPITER-II Program

    Energy Technology Data Exchange (ETDEWEB)

    Shiradata, Keisho; Yamamoto, Masaaki [comps.

    1985-12-31

    The JUPITER-II Program is the Joint Physics Large Heterogeneous Core Critical Experiments Program between the U.S. Department of Energy (US DOE) and PNC, Japan. The experiments began in May 1982 and ended in April 1984, as a part of the ZPPR-13 program. The ZPPR-13 is a series of critical assemblies designed to study the fundamental neutronic behavior of large, radially-heterogeneous LMFBR cores. This report describes the results of analysis of ZPPR-13A and preliminary analysis of ZPPR-13B, and some topics of recent activities in fast reactor physics.

  17. OR TEP-II: a FORTRAN Thermal-Ellipsoid Plot Program for crystal structure illustrations

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, C.K.

    1976-03-01

    A computer program is described for drawing crystal structure illustrations using a mechanical plotter. Ball-and-stick type illustrations of a quality suitable for publication are produced with either spheres or thermal-motion probability ellipsoids on the atomic sites. The program can produce stereoscopic pairs of illustrations which aid in the visualization of complex packing arrangements of atoms and thermal motion patterns. Interatomic distances, bond angles, and principal axes of thermal motion are also calculated to aid the structural study. The most recent version of the program, OR TEP-II, has a hidden-line-elimination feature to omit those portions of atoms or bonds behind other atoms or bonds.

  18. Medicare Program; Revisions to Payment Policies Under the Physician Fee Schedule and Other Revisions to Part B for CY 2018; Medicare Shared Savings Program Requirements; and Medicare Diabetes Prevention Program. Final rule.

    Science.gov (United States)

    2017-11-15

    This major final rule addresses changes to the Medicare physician fee schedule (PFS) and other Medicare Part B payment policies such as changes to the Medicare Shared Savings Program, to ensure that our payment systems are updated to reflect changes in medical practice and the relative value of services, as well as changes in the statute. In addition, this final rule includes policies necessary to begin offering the expanded Medicare Diabetes Prevention Program model.

  19. Phase II Documentation Overview of Corrective Action Unit 98: Frenchman Flat, Nevada Test Site, Nye County, Nevada, Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Greg Ruskauff

    2010-04-01

    The U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) initiated the Underground Test Area (UGTA) Subproject to assess and evaluate radiologic groundwater contamination resulting from underground nuclear testing at the NTS. These activities are overseen by the Federal Facility Agreement and Consent Order (FFACO) (1996, as amended March 2010). For Frenchman Flat, the UGTA Subproject addresses media contaminated by the underground nuclear tests, which is limited to geologic formations within the saturated zone or 100 meters (m) or less above the water table. Transport in groundwater is judged to be the primary mechanism of migration for the subsurface contamination away from the Frenchman Flat underground nuclear tests. The intent of the UGTA Subproject is to assess the risk to the public from the groundwater contamination produced as a result of nuclear testing. The primary method used to assess this risk is the development of models of flow and contaminant transport to forecast the extent of potentially contaminated groundwater for the next 1,000 years, establish restrictions to groundwater usage, and implement a monitoring program to verify protectiveness. For the UGTA Subproject, contaminated groundwater is that which exceeds the radiological standards of the Safe Drinking Water Act (CFR, 2009) the State of Nevada’s groundwater quality standard to protect human health and the environment. Contaminant forecasts are expected to be uncertain, and groundwater monitoring will be used in combination with land-use control to build confidence in model results and reduce risk to the public. Modeling forecasts of contaminant transport will provide the basis for negotiating a compliance boundary for the Frenchman Flat Corrective Action Unit (CAU). This compliance boundary represents a regulatory-based distinction between groundwater contaminated or not contaminated by underground testing. Transport modeling simulations

  20. The Studsvik power transient programs Demo-Ramp II and Trans-Ramp I

    International Nuclear Information System (INIS)

    Bergenlid, U.; Lysell, G.; Mogard, H.; Roennberg, G.

    1984-01-01

    The Studsvik Demo-Ramp II och Trans-Ramp I are internationally sponsored research programs. The main objectives are similar in both programs: to study the effects on the PCI/SCC failure process of short time power transients, above the failure threshold where cladding failure (FP leakage) is expected to occur after a sufficient hold time. Demo-Ramp II is completed, whereas, at present, Trans-Ramp I is in progress. Test fuel rods of standard BWR design are used. The fuel rods have been base-irradiated in a power reactor (burn-up in the range 18 to 29 MWd/kg U) and subsequently ramp tested in the R2 reactor. Extensive examinations of the rods have been performed. In the Demo-Ramp II program a large number of incipient cladding cracks were observed to be formed more rapidly than expected, based on previous knowledge. It was possible to operate one rod for a very short time above the failure threshold without SCC crack formation. One objective of the Trans-Ramp I program is to define more closely the power-time region above the failure threshold where the rods remain intact after power transients. (author)

  1. Medicare program; revisions to payment policies under the physician fee schedule, clinical laboratory fee schedule & other revisions to Part B for CY 2014. Final rule with comment period.

    Science.gov (United States)

    2013-12-10

    This major final rule with comment period addresses changes to the physician fee schedule, clinical laboratory fee schedule, and other Medicare Part B payment policies to ensure that our payment systems are updated to reflect changes in medical practice and the relative value of services. This final rule with comment period also includes a discussion in the Supplementary Information regarding various programs. (See the Table of Contents for a listing of the specific issues addressed in the final rule with comment period.)

  2. Revising Translations

    DEFF Research Database (Denmark)

    Rasmussen, Kirsten Wølch; Schjoldager, Anne

    2011-01-01

    The paper explains the theoretical background and findings of an empirical study of revision policies, using Denmark as a case in point. After an overview of important definitions, types and parameters, the paper explains the methods and data gathered from a questionnaire survey and an interview...... survey. Results clearly show that most translation companies regard both unilingual and comparative revisions as essential components of professional quality assurance. Data indicate that revision is rarely fully comparative, as the preferred procedure seems to be a unilingual revision followed by a more...... or less comparative rereading. Though questionnaire data seem to indicate that translation companies use linguistic correctness and presentation as the only revision parameters, interview data reveal that textual and communicative aspects are also considered. Generally speaking, revision is not carried...

  3. Operational-safety advantages of LMFBR's: the EBR-II experience and testing program

    International Nuclear Information System (INIS)

    Sackett, J.I.; Lindsay, R.W.; Golden, G.H.

    1982-01-01

    LMFBR's contain many inherent characteristics that simplify control and improve operating safety and reliability. The EBR-II design is such that good advantage was taken of these characteristics, resulting in a vary favorable operating history and allowing for a program of off-normal testing to further demonstrate the safe response of LMFBR's to upsets. The experience already gained, and that expected from the future testing program, will contribute to further development of design and safety criteria for LMFBR's. Inherently safe characteristics are emphasized and include natural convective flow for decay heat removal, minimal need for emergency power and a large negative reactivity feedback coefficient. These characteristics at EBR-II allow for ready application of computer diagnosis and control to demonstrate their effectiveness in response to simulated plant accidents. This latter testing objective is an important part in improvements in the man-machine interface

  4. DOG -II input generator program for DOT3.5 code

    International Nuclear Information System (INIS)

    Hayashi, Katsumi; Handa, Hiroyuki; Yamada, Koubun; Kamogawa, Susumu; Takatsu, Hideyuki; Koizumi, Kouichi; Seki, Yasushi

    1992-01-01

    DOT3.5 is widely used for radiation transport analysis of fission reactors, fusion experimental facilities and particle accelerators. We developed the input generator program for DOT3.5 code in aim to prepare input data effectively. Formar program DOG was developed and used internally in Hitachi Engineering Company. In this new version DOG-II, limitation for R-Θ geometry was removed. All the input data is created by interactive method in front of color display without using DOT3.5 manual. Also the geometry related input are easily created without calculation of precise curved mesh point. By using DOG-II, reliable input data for DOT3.5 code is obtained easily and quickly

  5. Recommendations for Cycle II of National Water-Quality Assessment (NAWQA) Program

    Science.gov (United States)

    ,; Mallard, Gail E.; Armbruster, Jeffrey T.; Broshears, Robert E.; Evenson, Eric J.; Luoma, Samuel N.; Phillips, Patrick J.; Prince, Keith R.

    1999-01-01

    The Planning Team for the U.S. Geological Survey (USGS) National Water-Quality Assessment (NAWQA) Program defines a successful NAWQA Program as one that makes a balanced contribution to study-unit issues, national issues, and to the pursuit of scientific knowledge. Using this criterion, NAWQA has been a success. The program has provided important new knowledge and understanding of scientific processes, and insights into the occurrence and distribution of contaminants that have been key to local and national policy decisions. Most of the basic design characteristics of NAWQA's first decade (1991-2000), hereafter called cycle I) remain appropriate as the program enters its second decade (cycle II) in 2001. In cycle II, the program has the opportunity to build on its successful base and to evolve to take advantage of the knowledge generated in cycle I. In addition to this expected evolution, NAWQA must also make some changes to compensate for the fact that program funding has not kept pace with inflation. An important theme for the second cycle of NAWQA will be the integration of knowledge across scales and across disciplines. The question that drove the NAWQA design in the first cycle was "How is water quality related to land use?" Cycle II will build upon what was learned in cycle I and use land-use and water-quality gradients to identify and understand potential sources of various constituents and the processes affecting transport and fate of those constituents and their effects on receptors. The understanding we gain from applying this approach will be relevant to the interests of policymakers, regulatory agencies, and resource managers.

  6. Ocean Thermal Energy Converstion (OTEC) test facilities study program. Final report. Volume II. Part B

    Energy Technology Data Exchange (ETDEWEB)

    None

    1977-01-17

    Results are presented of an 8-month study to develop alternative non-site-specific OTEC facilities/platform requirements for an integrated OTEC test program which may include land and floating test facilities. Volume II--Appendixes is bound in three parts (A, B, and C) which together comprise a compendium of the most significant detailed data developed during the study. Part B provides an annotated test list and describes component tests and system tests.

  7. SCINFI II A program to calculate the standardization curve in liquid scintillation counting

    Energy Technology Data Exchange (ETDEWEB)

    Grau Carles, A.; Grau Malonda, A.

    1985-07-01

    A code, SCINFI II, written in BASIC, has been developed to compute the efficiency-quench standardization curve for any beta radionuclide. The free parameter method has been applied. The program requires the standardization curve for 3{sup H} and the polynomial or tabulated relating counting efficiency as figure of merit for both 3{sup H} and the problem radionuclide. The program is applied to the computation, of the counting efficiency for different values of quench when the problem is 14{sup C}. The results of four different computation methods are compared. (Author) 17 refs.

  8. SCINFI II A program to calculate the standardization curve in liquid scintillation counting

    International Nuclear Information System (INIS)

    Grau Carles, A.; Grau Malonda, A.

    1985-01-01

    A code, SCINFI II, written in BASIC, has been developed to compute the efficiency-quench standardization curve for any beta radionuclide. The free parameter method has been applied. The program requires the standardization curve for 3 H and the polynomial or tabulated relating counting efficiency as figure of merit for both 3 H and the problem radionuclide. The program is applied to the computation, of the counting efficiency for different values of quench when the problem is 14 C . The results of four different computation methods are compared. (Author) 17 refs

  9. State child health; revisions to the regulations implementing the State Children's Health Insurance Program. Interim final rule with comment period; revisions, delay of effective date, and technical amendments to final rule.

    Science.gov (United States)

    2001-06-25

    Title XXI authorizes the State Children's Health Insurance Program (SCHIP) to assist State efforts to initiate and expand the provision of child health assistance to uninsured, low-income children. On January 11, 2001 we published a final rule in the Federal Register to implement SCHIP that has not gone into effect. This interim final rule further delays the effective date, revises certain provisions and solicits public comment, and makes technical corrections and clarifications to the January 2001 final rule based on further review of the comments received and applicable law. Only the provisions set forth in this document have changed. All other provisions set forth in the January 2001 final rule will be implemented without change.

  10. Energy Extension Service Pilot Program: evaluation report after two years. Volume II. State reports

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-04-01

    This report, Vol. II, presents a discussion of the operations of the ten EES pilot state programs during the period from October 1, 1977 through September 30, 1979. Each of the ten pilot states - Alabama, Connecticut, Michigan, New Mexico, Pennsylvania, Tennessee, Texas, Washington, Wisconsin, and Wyoming - received a grant of approximately $1.1 million to develop and implement an 18-month program beginning on October 1, 1977. In September 1978, each State received an additional $370,000 for service-delivery programs for the extension of the pilot program, April 1979 through September 1979. A case-study description of the operations of the pilot program in each State is provided here, with special attention given to the two programs selected in each State for more-detailed study and survey research. Although the thrust of this volume is descriptive, some survey data and analyses are presented for the emphasis programs. Two telephone surveys of clients and a non-client sample were conducted, one at the end of the first year of the pilot program (October 1977 - September 1978) and one at the end of the second year (October 1978 - September 1979).

  11. 75 FR 16833 - Preliminary Revised 5-Year Outer Continental Shelf (OCS) Oil and Gas Leasing Program for 2007-2012

    Science.gov (United States)

    2010-04-02

    ... sensitivity analysis is expanded, it is important to remember that the Secretary's decisions are not based on... study will summarize what information is available, where knowledge gaps exist, and what research is... commenters to focus on the expanded relative environmental sensitivity analysis and the Secretary's revisions...

  12. Transition projects, Fiscal Year 1996: Multi-Year Program Plan (MYPP) for WBS 1.31, 7.1, and 6.13. Revision 1, Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Cartmell, D.B.

    1995-09-01

    Based on US Department of Energy (DOE), Richland Operations Office (RL) review, specific areas of Westinghouse Hanford Company (WHC), Transition Projects ``Draft`` Multi-Year Program Plan (MYPP) were revised in preparation for the RL approval ceremony on September 26, 1995. These changes were reviewed with the appropriate RL Project Manager. The changes have been incorporated to the MYPP electronic file, and hard copies replacing the ``Draft`` MYPP will be distributed after the formal signing. In addition to the comments received, a summary level schedule and outyear estimates for the K Basin deactivation beginning in FY 2001 have been included. The K Basin outyear waste data is nearing completion this week and will be incorporated. This exclusion was discussed with Mr. N.D. Moorer, RL, Facility Transition Program Support/Integration. The attached MYPP scope/schedule reflects the Integrated Target Case submitted in the April 1995 Activity Data Sheets (ADS) with the exception of B Plant and the Plutonium Finishing Plant (PFP). The 8 Plant assumption in FY 1997 reflects the planning case in the FY 1997 ADS with a shortfall of $5 million. PFP assumptions have been revised from the FY 1997 ADS based on the direction provided this past summer by DOE-Headquarters. This includes the acceleration of the polycube stabilization back to its originally planned completion date. Although the overall program repricing in FY 1996 allowed the scheduled acceleration to fall with the funding allocation, the FY 1997 total reflects a shortfall of $6 million.

  13. Transition projects, Fiscal Year 1996: Multi-Year Program Plan (MYPP) for WBS 1.31, 7.1, and 6.13. Revision 1, Volume 1

    International Nuclear Information System (INIS)

    Cartmell, D.B.

    1995-09-01

    Based on US Department of Energy (DOE), Richland Operations Office (RL) review, specific areas of Westinghouse Hanford Company (WHC), Transition Projects ''Draft'' Multi-Year Program Plan (MYPP) were revised in preparation for the RL approval ceremony on September 26, 1995. These changes were reviewed with the appropriate RL Project Manager. The changes have been incorporated to the MYPP electronic file, and hard copies replacing the ''Draft'' MYPP will be distributed after the formal signing. In addition to the comments received, a summary level schedule and outyear estimates for the K Basin deactivation beginning in FY 2001 have been included. The K Basin outyear waste data is nearing completion this week and will be incorporated. This exclusion was discussed with Mr. N.D. Moorer, RL, Facility Transition Program Support/Integration. The attached MYPP scope/schedule reflects the Integrated Target Case submitted in the April 1995 Activity Data Sheets (ADS) with the exception of B Plant and the Plutonium Finishing Plant (PFP). The 8 Plant assumption in FY 1997 reflects the planning case in the FY 1997 ADS with a shortfall of $5 million. PFP assumptions have been revised from the FY 1997 ADS based on the direction provided this past summer by DOE-Headquarters. This includes the acceleration of the polycube stabilization back to its originally planned completion date. Although the overall program repricing in FY 1996 allowed the scheduled acceleration to fall with the funding allocation, the FY 1997 total reflects a shortfall of $6 million

  14. The Impact of the 2009 Special Supplemental Nutrition Program for Women, Infants, and Children Food Package Revisions on Participants: A Systematic Review.

    Science.gov (United States)

    Schultz, Daniel Joseph; Byker Shanks, Carmen; Houghtaling, Bailey

    2015-11-01

    For the first time since 1980, the US Department of Agriculture Food and Nutrition Service Special Supplemental Nutrition Program for Women, Infants, and Children (WIC) food package policies were revised in 2009 to meet the Institute of Medicine's nutrition recommendations. These changes included increases in fruits, vegetables, whole grains, and low-fat dairy to improve nutrition and health of WIC participants. Our systematic review of the literature assessed the influence that the 2009 WIC food package revisions have had on dietary intake, healthy food and beverage availability, and breastfeeding participation. The systematic review followed Preferred Reporting Items for Systematic Reviews and Meta-Analyses recommendations. Four electronic databases were searched between April 1 and 30, 2014, for peer-reviewed research. Two reviewers screened the articles, extracted the data, and established inter-rater reliability by discussing and resolving discrepancies. Twenty articles were included that met our inclusion criteria. Nine of the studies analyzed changes in dietary intake, eight examined changes in healthy food and beverage availability, and three evaluated breastfeeding participation exclusively. The review demonstrated an improved dietary intake and an increase in the availability of healthier foods and beverages in authorized WIC stores. The revised food package was also associated with improved dietary intake of WIC participants. Mixed results were demonstrated in regard to improved breastfeeding outcomes. Further research is needed to assess the influence of WIC 2009 food package revisions on breastfeeding outcomes and to make conclusions about broad nutrition-related implications. Copyright © 2015 Academy of Nutrition and Dietetics. Published by Elsevier Inc. All rights reserved.

  15. Near-Term Electric Vehicle Program. Phase II: Mid-Term Summary Report.

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-08-01

    The Near Term Electric Vehicle (NTEV) Program is a constituent elements of the overall national Electric and Hybrid Vehicle Program that is being implemented by the Department of Energy in accordance with the requirements of the Electric and Hybrid Vehicle Research, Development, and Demonstration Act of 1976. Phase II of the NTEV Program is focused on the detailed design and development, of complete electric integrated test vehicles that incorporate current and near-term technology, and meet specified DOE objectives. The activities described in this Mid-Term Summary Report are being carried out by two contractor teams. The prime contractors for these contractor teams are the General Electric Company and the Garrett Corporation. This report is divided into two discrete parts. Part 1 describes the progress of the General Electric team and Part 2 describes the progress of the Garrett team.

  16. [Vision test program for ophthalmologists on Apple II, IIe and IIc computers].

    Science.gov (United States)

    Huber, C

    1985-03-01

    A microcomputer program for the Apple II family of computers on a monochrome and a color screen is described. The program draws most of the tests used by ophthalmologists, and is offered as an alternative to a projector system. One advantage of the electronic generation of drawings is that true random orientation of Pflueger's E is possible. Tests are included for visual acuity (Pflueger's E, Landolt rings, numbers and children's drawings). Colored tests include a duochrome test, simple color vision tests, a fixation help with a musical background, a cobalt blue test and a Worth figure. In the astigmatic dial a mobile pointer helps to determine the axis. New tests can be programmed by the user and exchanged on disks among collageues.

  17. EBRPOCO - a program to calculate detailed contributions of power reactivity components of EBR-II

    International Nuclear Information System (INIS)

    Meneghetti, D.; Kucera, D.A.

    1981-01-01

    The EBRPOCO program has been developed to facilitate the calculations of the power coefficients of reactivity of EBR-II loadings. The program enables contributions of various components of the power coefficient to be delineated axially for every subassembly. The program computes the reactivity contributions of the power coefficients resulting from: density reduction of sodium coolant due to temperature; displacement of sodium coolant by thermal expansions of cladding, structural rods, subassembly cans, and lower and upper axial reflectors; density reductions of these steel components due to temperature; displacement of bond-sodium (if present) in gaps by differential thermal expansions of fuel and cladding; density reduction of bond-sodium (if present) in gaps due to temperature; free axial expansion of fuel if unrestricted by cladding or restricted axial expansion of fuel determined by axial expansion of cladding. Isotopic spatial contributions to the Doppler component my also be obtained. (orig.) [de

  18. The revised Bethesda guidelines: extent of utilization in a university hospital medical center with a cancer genetics program

    Directory of Open Access Journals (Sweden)

    Mukherjee Aparna

    2010-11-01

    Full Text Available Abstract Background In 1996, the National Cancer Institute hosted an international workshop to develop criteria to identify patients with colorectal cancer who should be offered microsatellite instability (MSI testing due to an increased risk for Hereditary Nonpolyposis Colorectal Cancer (HNPCC. These criteria were further modified in 2004 and became known as the revised Bethesda Guidelines. Our study aimed to retrospectively evaluate the percentage of patients diagnosed with HNPCC tumors in 2004 who met revised Bethesda criteria for MSI testing, who were referred for genetic counseling within our institution. Methods All HNPCC tumors diagnosed in 2004 were identified by accessing CoPath, an internal database. Both the Tumor Registry and patients' electronic medical records were accessed to collect all relevant family history information. The list of patients who met at least one of the revised Bethesda criteria, who were candidates for MSI testing, was then cross-referenced with the database of patients referred for genetic counseling within our institution. Results A total of 380 HNPCC-associated tumors were diagnosed at our institution during 2004 of which 41 (10.7% met at least one of the revised Bethesda criteria. Eight (19.5% of these patients were referred for cancer genetic counseling of which 2 (25% were seen by a genetics professional. Ultimately, only 4.9% of patients eligible for MSI testing in 2004 were seen for genetic counseling. Conclusion This retrospective study identified a number of barriers, both internal and external, which hindered the identification of individuals with HNPCC, thus limiting the ability to appropriately manage these high risk families.

  19. Subseabed disposal program annual report, January-December 1979. Volume II. Appendices (principal investigator progress reports). Part 2 of 2

    International Nuclear Information System (INIS)

    Talbert, D.M.

    1981-04-01

    Volume II of the sixth annual report describing the progress and evaluating the status of the Subseabed Disposal Program contains the appendices referred to in Volume II, Summary and Status. Because of the length of Volume II, it has been split into two parts for publication purposes. Part 1 contains Appendices A-O; Part 2 contains Appendices P-FF. Separate abstracts have been prepared for each appendix for inclusion in the Energy Data Base

  20. The relative influence of secondary versus primary prevention using the national cholesterol education program adult treatment panel II guidelines

    NARCIS (Netherlands)

    Goldman, L; Coxson, P; Hunink, MGM; Goldman, PA; Tosteson, ANA; Mittleman, M; Williams, L; Weinstein, MC

    OBJECTIVES This study was undertaken to project the population-wide effect of full implementation of the Adult Treatment Panel (ATP) II guidelines of the National Cholesterol Education Program (NCEP). BACKGROUND The ATP II has proposed guidelines for cholesterol reduction, but the long-term

  1. Quality-assurance study of the special-purpose finite-element program SPECTROM: II. Plasticity problems

    International Nuclear Information System (INIS)

    Callahan, G.D.; Fossum, A.F.

    1982-11-01

    General plasticity theory and solution techniques as are currently employed in RE/SPEC's finite element plasticity code SPECTROM-II are presented. Various yield functions are discussed and their differences are illustrated using example problems. Comparison of the results of SPECTROM-II with analytical solutions, numerical solutions, and the general purpose finite element program MARC-CDC show excellent agreement

  2. Impact of the revised Special Supplemental Nutrition Program for Women, Infants, and Children (WIC) food package policy on fruit and vegetable prices.

    Science.gov (United States)

    Zenk, Shannon N; Powell, Lisa M; Odoms-Young, Angela M; Krauss, Ramona; Fitzgibbon, Marian L; Block, Daniel; Campbell, Richard T

    2014-02-01

    Obesity is generally inversely related to income among women in the United States. Less access to healthy foods is one way lower income can influence dietary behaviors and body weight. Federal food assistance programs, such as the Special Supplemental Nutrition Program for Women, Infants, and Children (WIC), are an important source of healthy food for low-income populations. In 2009, as part of a nationwide policy revision, WIC added a fruit and vegetable (F/V) voucher to WIC food packages. This quasi-experimental study determined whether F/V prices at stores authorized to accept WIC (ie, WIC vendors) decreased after the policy revision in seven Illinois counties. It also examined cross-sectional F/V price variations by store type and neighborhood characteristics. Two pre-policy observations were conducted in 2008 and 2009; one post-policy observation was conducted in 2010. Small pre- to post-policy reductions in some F/V prices were found, particularly for canned fruit and frozen vegetables at small stores. Compared with chain supermarkets, mass merchandise stores had lower prices for fresh F/V and frozen F/V and small stores and non-chain supermarkets had higher canned and frozen F/V prices, but lower fresh F/V prices. Limited price differences were found across neighborhoods, although canned vegetables were more expensive in neighborhoods with higher concentrations of either Hispanics or blacks and fresh F/V prices were lower in neighborhoods with more Hispanics. Results suggest the WIC policy revision contributed to modest reductions in F/V prices. WIC participants' purchasing power can differ depending on the type and neighborhood of the WIC vendor used. Copyright © 2014 Academy of Nutrition and Dietetics. Published by Elsevier Inc. All rights reserved.

  3. Impact of the Revised Special Supplemental Nutrition Program for Women, Infants, and Children (WIC) Food Package Policy on Fruit and Vegetable Prices

    Science.gov (United States)

    Zenk, Shannon N.; Powell, Lisa M.; Odoms-Young, Angela M.; Krauss, Ramona; Fitzgibbon, Marian L.; Block, Daniel; Campbell, Richard T.

    2014-01-01

    Obesity is generally inversely related to income among women in the United States. Less access to healthy foods is one way lower income can influence dietary behaviors and body weight. Federal food assistance programs, such as the Special Supplemental Nutrition Program for Women, Infants, and Children (WIC), are an important source of healthy food for low-income populations. In 2009, as part of a nationwide policy revision, WIC added a fruit and vegetable (F/V) voucher to WIC food packages. This quasi-experimental study determined whether F/V prices at stores authorized to accept WIC (ie, WIC vendors) decreased after the policy revision in seven Illinois counties. It also examined cross-sectional F/V price variations by store type and neighborhood characteristics. Two pre-policy observations were conducted in 2008 and 2009; one post-policy observation was conducted in 2010. Small pre- to post-policy reductions in some F/V prices were found, particularly for canned fruit and frozen vegetables at small stores. Compared with chain supermarkets, mass merchandise stores had lower prices for fresh F/V and frozen F/V and small stores and non-chain supermarkets had higher canned and frozen F/V prices, but lower fresh F/V prices. Limited price differences were found across neighborhoods, although canned vegetables were more expensive in neighborhoods with higher concentrations of either Hispanics or blacks and fresh F/V prices were lower in neighborhoods with more Hispanics. Results suggest the WIC policy revision contributed to modest reductions in F/V prices. WIC participants’ purchasing power can differ depending on the type and neighborhood of the WIC vendor used. PMID:24183996

  4. High energy physics studies. Progress report. Part I. Experimental program. Part II. Theoretical program

    International Nuclear Information System (INIS)

    Romanowski, T.A.; Tanaka, K.; Wada, W.W.

    1978-01-01

    Experimental Program: assembly of an experiment as Fermilab E-531 to measure decay lifetimes, with tagged emulsion of charmed particles produced by high energy neutrinos was finished, and data taking now is in progress. An experiment to measure prompt neutrino production at Fermilab, E-613, was approved and detailed design of it is continuing. Search for parity violation in scattering of polarized protons, an experiment E-446-ZGS at ANL, was performed with the sensitivity of 10 -6 for detection of that process and yielded null results. Another run with improved sensitivity of 10 -7 is in preparation. Data analysis of the neutrino experiment E-310 at Fermilab will continue. Trimuon events, a new discovery, were identified in those data. Analysis of data on meson production from experiments performed at the ZGS--ANL, E-397, E-420 and E-428, with charged and neutral spectrometer will continue. A new relatively broad resonance (T approx. 70 MeV) with quantum numbers IJ/sup P/ = 00 -1 was discovered in the data from E-397. Analysis of beta decay of polarized Σ - hyperons is in progress. Participation in the design of the experimental areas for the Isabelle colliding proton beam accelerator will continue. Theoretical Program: topics of current interest in particle theory which will be investigated in the coming year are: the instanton-anti-instanton QCD gauge fields, discrete symmetries which may determine quark masses in the SU(2) x U(1) model, calculation of charmed meson production in e + e - collisions and formation of gluon jets, Higgs boson production in pp collisions, calculation of Higgs boson mass in terms of vector boson mass, study of Lagrangians with gauge and Higgs scalar fields, investigation of Faddeev--Popov determinants as related to quantum chromodynamics, a study of quantum flavor dynamics and anomalies in the axial vector Ward identity and a study of super symmetry as a part of a realistic model of leptonic interactions

  5. VERIFIKASI PAKET PROGRAM MVP-II DAN SRAC2006 PADA KASUS TERAS REAKTOR VERA BENCHMARK.

    Directory of Open Access Journals (Sweden)

    Jati Susilo

    2015-03-01

    Full Text Available Dalam penelitian ini dilakukan verifikasi perhitungan benchmark VERA pada kasus Zero Power Physical Test (ZPPT teras reaktor Watts Bar 1. Reaktor tersebut merupakan jenis PWR kelas 1000 MWe yang didesain oleh Westinghouse, tersusun dari 193 perangkat bahan bakar 17×17 dengan 3 jenis pengkayaan UO2 yaitu 2,1wt%, 2,619wt% dan 3,1wt%. Perhitungan nilai k-eff dan distribusi faktor daya dilakukan pada siklus operasi pertama teras dengan kondisi beginning of cycle (BOC dan hot zero power (HZP. Posisi batang kendali dibedakan menjadi uncontrolled (semua batang kendali berada di luar teras, dan controlled (batang kendali Bank D didalam teras. Paket program komputer yang digunakan dalam perhitungan adalah MVP-II dan SRAC2006 modul CITATION dengan data pustaka tampang lintang ENDF/B-VII.0. Hasil perhitungan menunjukkan bahwa perbedaan nilai k-eff teras pada kondisi controlled dan uncontrolled antara referensi dengan MVP-II (-0,07% dan -0,014% dan SRAC2006 (0,92% dan 0,99% sangat kecil atau masih dibawah 1%. Perbedaan faktor daya maksimum teras pada kondisi controlled dan uncontrolled dengan referensi dengan MVP-II adalah 0,38% dan 1,53%, sedangkan dengan SRAC2006 adalah 1,13% dan -2,45%. Dapat dikatakan bahwa kedua paket program komputer menunjukkan hasil perhitungan yang sesuai dengan nilai referensi. Dalam hal penentuan kekritisan teras, maka hasil perhitungan MVP-II lebih konservatif dibandingkan dengan SRAC2006. Kata kunci : MVP-II, SRAC2006, PWR, VERA   In this research, verification calculation for VERA core physics benchmark on the Zero Power Physical Test (ZPPT of the nuclear reactor Watts Bar 1. The reactor is a 1000 MWe class of PWR designed by Westinghouse, arranged from 193 unit of 17×17 fuel assembly consisting 3 type enrichment of UO2 that are 2.1wt%, 2.619wt% and 3.1wt%. Core power factor distribution and k-eff calculation has been done for the first cycle operation of the core at beginning of cycle (BOC and hot zero power (HZP. In this

  6. The neutron utilization and promotion program of TRR-II research reactor project in Taiwan

    International Nuclear Information System (INIS)

    Gone, J.K.; Huang, Y.H.

    2001-01-01

    The objective of the Taiwan research reactor system improvement and utilization promotion project is to reconstruct the old Taiwan research reactor (TRR), which was operated by the Institute of Nuclear Energy Research (INER) between 1973 and 1988, into a multi-purpose medium flux research reactor (TRR-II). The project started in 1998, and the new reactor is scheduled to have its first critical in June of 2006. The estimated maximum unperturbed thermal neutron flux (E 14 n/cm 2 sec, and it is about one order of magnitude higher than other operating research reactors in Taiwan. The new reactor will equip with secondary neutron sources to provide neutrons with different energies, which will be an essential tool for advanced material researches in Taiwan. One of the major tasks of TRR-II project is to promote domestic utilization of neutrons generated at TRR-II. The traditional uses of neutrons in fuel/material research, trace element analysis, and isotope production has been carried out at INER for many years. On the other hand, it is obvious that promotions of neutron spectrometric technique will be a major challenge for the project team. The limited neutron flux from operating research reactors had discouraged domestic users in developing neutron spectrometric technique for many years, and only few researchers in Taiwan are experienced in using spectrometers. It is important for the project team to encourage domestic researchers to use neutron spectrometers provided by TRR-II as a tool for their future researches in various fields. This paper describes the current status of TRR-II neutron utilization and promotion program. The current status and future plans for important issues such as staff recruiting, personnel training, international collaboration, and promotion strategy will be described. (orig.)

  7. Extension of the RPV irradiation surveillance program of NPP GKN II by T0 approach

    International Nuclear Information System (INIS)

    Barthelmes, J.; Keim, E.; Hein, H.; Koenig, G.

    2015-01-01

    The nuclear power plant (NPP) Neckarwestheim II (GKN II) started operation in 1989 and was designed for 40 years of operation. During the plant life time the reactor pressure vessel (RPV) integrity is a main aspect for nuclear safety since the RPV is exposed to neutron irradiation affecting the mechanical material properties, in particular toughness. In this context the ductile to brittle transition reference temperature of the RPV materials can be determined either indirectly according to the RT(NDT) concept by means of comparative examinations of irradiated and unirradiated notched-bar impact specimens or directly according to the Master Curve concept by means of examination of irradiated fracture mechanic specimens and determination of an alternative reference temperature RT(T0). With the implementation and evaluation of the first irradiation surveillance program consisting of three sets, one unirradiated reference set (set 1) and two irradiated sets (set 2 and 3), the RPV safety could be proven for the assessment fluence (AF) of 8*10 18 cm -2 (E > 1 MeV) using the RT(NDT) concept. Against the background of a possible long term operation and the state-of-the-art of science and technology in 1998 the NPP GKN II initiated a supplemental irradiation surveillance program with two irradiation sets (set 4 and 5) containing fracture mechanic specimens for complementary proof of safety according to the Master Curve concept. The results of the first irradiated set 4 are presented and assessed by means of the reference temperatures according to the Master Curve concept and compared to the results of the irradiation sets 1 to 3 of the conventional irradiation surveillance program. As an important outcome the existing RPV integrity assessment could be ensured by the Master Curve results. The applied approach adapts to the state-of-the-art of science and technology and is best practice to ensure the safe operation of RPV supplementary. (authors)

  8. VASCOMP II. The V/STOL Aircraft Sizing and Performance Computer Program. Volume VI. User’s Manual. Revision 3

    Science.gov (United States)

    1980-05-01

    absorbers) 1.2 Doors, Cowl Flaps, and Work Platforms dj Minimum doors 0 Standard 1.0 Radial engine cowl flaps 1.1 Split and hinged engine cowl 1.2 Hinged...cowl with work platform 1.3 - High wing 1.2 - Low wing 1.1 These factors should be assessed on basis of size of cowl versus total nacelle. 4-170 ( 0D 0 V...V41L U 11. 𔄁N .7N %rf700 rC LAO ( LA,’ 4 LA LLA LAC ’.1’ .oNf a NW r) N rn NW rN W)i NW) NW)n NW)n NI" fli cW) )~ 1 N N N . N.? w- -j ... N.? WIx

  9. Rigid Polyurethane Foam (RPF) Technology for Countermines (Sea) Program Phase II

    Energy Technology Data Exchange (ETDEWEB)

    WOODFIN,RONALD L.; FAUCETT,DAVID L.; HANCE,BRADLEY G.; LATHAM,AMY E.; SCHMIDT,C.O.

    1999-10-01

    This Phase II report documents the results of one subtask initiated under the joint Department of Energy (DOE)/Department of Defense (DoD) Memorandum of Understanding (MOU) for Countermine Warfare. The development of Rigid Polyurethane Foams for neutralization of mines and barriers in amphibious assault was the objective of the tasking. This phase of the program concentrated on formation of RPF in water, explosive mine simulations, and development of foam and fabric pontoons. Field experimentation was done primarily at the Energetic Materials Research and Testing Center (EMRTC) of the New Mexico Institute of Mining and Technology, Socorro, NM between February 1996 and September 1998.

  10. Validation of Multibody Program to Optimize Simulated Trajectories II Parachute Simulation with Interacting Forces

    Science.gov (United States)

    Raiszadeh, Behzad; Queen, Eric M.; Hotchko, Nathaniel J.

    2009-01-01

    A capability to simulate trajectories of multiple interacting rigid bodies has been developed, tested and validated. This capability uses the Program to Optimize Simulated Trajectories II (POST 2). The standard version of POST 2 allows trajectory simulation of multiple bodies without force interaction. In the current implementation, the force interaction between the parachute and the suspended bodies has been modeled using flexible lines, allowing accurate trajectory simulation of the individual bodies in flight. The POST 2 multibody capability is intended to be general purpose and applicable to any parachute entry trajectory simulation. This research paper explains the motivation for multibody parachute simulation, discusses implementation methods, and presents validation of this capability.

  11. Full-scale Mark II CRT program: dynamic response evaluation test of pressure transducers

    International Nuclear Information System (INIS)

    Kukita, Yutaka; Namatame, Ken; Takeshita, Isao; Shiba, Masayoshi

    1982-12-01

    A dynamic response evaluation test of pressure transducers was conducted in support of the JAERI Full-Scale Mark II CRT (Containment Response Test) Program. The test results indicated that certain of the cavity-type transducers used in the early blowdown test had undesirable response characteristics. The transducer mounting scheme was modified to avoid trapping of air bubbles in the pressure transmission tubing attached to the transducers. The dynamic response of the modified transducers was acceptable within the frequency range of 200 Hz. (author)

  12. Near-term electric-vehicle program. Phase II. Mid-term review summary report

    Energy Technology Data Exchange (ETDEWEB)

    1978-07-27

    The general objective of the Near-Term Electric Vehicle Program is to confirm that, in fact, the complete spectrum of requirements placed on the automobile (e.g., safety, producibility, utility, etc.) can still be satisfied if electric power train concepts are incorporated in lieu of contemporary power train concepts, and that the resultant set of vehicle characteristics are mutually compatible, technologically achievable, and economically achievable. The focus of the approach to meeting this general objective involves the design, development, and fabrication of complete electric vehicles incorporating, where necessary, extensive technological advancements. A mid-term summary is presented of Phase II which is a continuation of the preliminary design study conducted in Phase I of the program. Information is included on vehicle performance and performance simulation models; battery subsystems; control equipment; power systems; vehicle design and components for suspension, steering, and braking; scale model testing; structural analysis; and vehicle dynamics analysis. (LCL)

  13. Full-scale mark II CRT program data report no. 7

    International Nuclear Information System (INIS)

    Kukita, Yutaka; Namatame, Ken; Yamamoto, Nobuo; Takeshita, Isao; Shiba, Masayoshi

    1980-03-01

    The Full-Scale Mark II CRT (Containment Response Test) Program was initiated in 1977 to provide a data base for evaluation of the LOCA hydrodynamic loads in the BWR Mark II pressure suppression system. The test facility is 1/18 in volume and has a wetwell which is a full-scale replica of one 20 0 -sector of that of a reference Mark II. This report documents test data obtained from TEST 3102, which is a large (200 mm) water break test performed on June 29, 1979. The test was performed for a supernominal break area (approx. 160% of the scaled break area for a postulated double-ended break in the recirculation line) to obtain vent steam mass fluxes ranging up to the maximum design value of the actual plants. Before the initiation of the test more than 90% of the drywell air was replaced by steam and transferred into wetwell airspace to reduce the air content in the vent flow during the test. Because of this pre-test treatment (so-called prepurging) the test data obtained for high- and intermediate-steam-flux condensation oscillations are believed to be to a high degree on conservative side. (author)

  14. Pictorial Representation of Illness and Self Measure Revised II (PRISM-RII) - a novel method to assess perceived burden of illness in diabetes patients

    NARCIS (Netherlands)

    Klis, S.; Vingerhoets, A.J.M.M.; de, W.M.; Zandbelt, N.; Snoek, F.J.

    2008-01-01

    Background: The Pictorial Representation of Illness and Self Measure (PRISM) has been introduced as a visual measure of suffering. We explored the validity of a revised version, the PRISM-RII, in diabetes patients as part of the annual review. Methods: Participants were 308 adult outpatients with

  15. The positive effects of the revised milk and cheese allowances in the special supplemental nutrition program for women, infants, and children.

    Science.gov (United States)

    Andreyeva, Tatiana; Luedicke, Joerg; Henderson, Kathryn E; Schwartz, Marlene B

    2014-04-01

    In 2009, the Special Supplemental Nutrition Program for Women, Infants, and Children (WIC) implemented revisions to the WIC food packages. Milk and cheese allowances were reduced, and whole milk was disallowed for participants older than 23 months. Using a pre-post research design and scanner data from a New England supermarket chain on purchases of WIC households, this article assesses how the new WIC packages affected milk and cheese purchases and saturated fat intake among WIC households in Connecticut and Massachusetts. Milk and cheese volume purchased by 515 WIC households in Connecticut was compared before and after the WIC revisions (2009-2010) using generalized estimating equation models. Analysis for Massachusetts was descriptive. After implementation of the new WIC packages in Connecticut, whole-milk share declined from about 60% to 25% in WIC milk purchases, but remained flat at about 50% for purchases with non-WIC funds. Total milk volume fell by 14.2% (P<0.001), whole milk by half (P<0.001), and WIC-eligible cheese by 37.2% (P<0.001). Restrictions on whole milk shifted WIC purchases to reduced-fat milk in Connecticut and low-fat milk in Massachusetts, where reduced-fat milk is not permitted by WIC. The amounts of saturated fat from purchased milk and cheese declined by 85 g/month per WIC household in Connecticut and 107 g/month in Massachusetts. The 2009 WIC revisions led to a substantial decrease in purchases of whole milk and cheese among WIC families in New England. The related reduction in saturated fat intake could have important public health implications. Copyright © 2014 Academy of Nutrition and Dietetics. Published by Elsevier Inc. All rights reserved.

  16. A Multiple-star Combined Solution Program - Application to the Population II Binary μ Cas

    Science.gov (United States)

    Gudehus, D. H.

    2001-05-01

    A multiple-star combined-solution computer program which can simultaneously fit astrometric, speckle, and spectroscopic data, and solve for the orbital parameters, parallax, proper motion, and masses has been written and is now publicly available. Some features of the program are the ability to scale the weights at run time, hold selected parameters constant, handle up to five spectroscopic subcomponents for the primary and the secondary each, account for the light travel time across the system, account for apsidal motion, plot the results, and write the residuals in position to a standard file for further analysis. The spectroscopic subcomponent data can be represented by reflex velocities and/or by independent measurements. A companion editing program which can manage the data files is included in the package. The program has been applied to the Population II binary μ Cas to derive improved masses and an estimate of the primordial helium abundance. The source code, executables, sample data files, and documentation for OpenVMS and Unix, including Linux, are available at http://www.chara.gsu.edu/\\rlap\\ \\ gudehus/binary.html.

  17. Ageing management program of wires for Atucha II Nuclear Power Plant

    International Nuclear Information System (INIS)

    Zorrilla, J.; Antonaccio, E.; Luraschi, C.; Simionato, E.; Nieto, H.

    2012-01-01

    Electrical cables constitute one of the most important components of NPP in terms o maintenance, safety and availability of the plant. Due to their large extension (thousands of kilometers) it is impossible to fully replace them and aging management becomes essential for long term operation of NPP. Since Atucha II is under construction there was a good opportunity to establish and implement a holistic cable aging management program from the beginning according to the state of the art in this field. The scope of this program involves safety related cables, including EQ cables and non EQ cables as well. Due to the diversity of the installed cables is impossible to address an aging management program of every single specimen. However it is possible to establish 'cables families' of similar aging behavior based on insulation and jacket material, manufacture, etc Several aging management strategies were set for the different 'cables families'. These strategies include cables deposit in plant, elaboration of procedures of visual and tactile inspection, NDE techniques, etc Currently the aging management program is being implemented covering topic such as: Cable screening and grouping. Review of EQ documentation and conventional qualification information referring to the installed cables. Establishment of base line of condition monitoring techniques. Calibration and set up of test parameters for NDE techniques. Aging mechanism characterization and determination of. Design construction and installation of cable deposit in plant (author)

  18. Battle Staff Training System II: Computer-Based Instruction Supporting the Force XXI Training Program

    National Research Council Canada - National Science Library

    Wampler, Richard

    1998-01-01

    This report documents the methodology and lessons learned in the development of the Innovative Tools and Techniques for Brigade and Below Staff Training II - Battle Staff Training System II (ITTBBST-BSTS II...

  19. Subseabed disposal program annual report, January-December 1979. Volume II. Appendices (principal investigator progress reports). Part 1 of 2

    International Nuclear Information System (INIS)

    Talbert, D.M.

    1981-04-01

    Volume II of the sixth annual report describing the progress and evaluating the status of the Subseabed Disposal Program contains the appendices referred to in Volume I, Summary and Status. Because of the length of Volume II, it has been split into two parts for publication purposes. Part 1 contains Appendices A-O; Part 2 contains Appendices P-FF. Separate abstracts have been prepared of each Appendix for inclusion in the Energy Data Base

  20. Subseabed disposal program annual report, January-December 1980. Volume II. Appendices (principal investigator progress reports). Part 1

    Energy Technology Data Exchange (ETDEWEB)

    Hinga, K.R. (ed.)

    1981-07-01

    Volume II of the sixth annual report describing the progress and evaluating the status of the Subseabed Disposal Program contains the appendices referred to in Volume I, Summary and Status. Because of the length of Volume II, it has been split into two parts for publication purposes. Part 1 contains Appendices A-Q; Part 2 contains Appendices R-MM. Separate abstracts have been prepared for each appendix for inclusion in the Energy Data Base.

  1. Subseabed disposal program annual report, January-December 1980. Volume II. Appendices (principal investigator progress reports). Part 1

    International Nuclear Information System (INIS)

    Hinga, K.R.

    1981-07-01

    Volume II of the sixth annual report describing the progress and evaluating the status of the Subseabed Disposal Program contains the appendices referred to in Volume I, Summary and Status. Because of the length of Volume II, it has been split into two parts for publication purposes. Part 1 contains Appendices A-Q; Part 2 contains Appendices R-MM. Separate abstracts have been prepared for each appendix for inclusion in the Energy Data Base

  2. Whole-core damage analysis of EBR-II driver fuel elements following SHRT program

    International Nuclear Information System (INIS)

    Chang, L.K.; Koenig, J.F.; Porter, D.L.

    1987-01-01

    In the Shutdown Heat Removal Testing (SHRT) program in EBR-II, fuel element cladding temperatures of some driver subassemblies were predicted to exceed temperatures at which cladding breach may occur. A whole-core thermal analysis of driver subassemblies was performed to determine the cladding temperatures of fuel elemnts, and these temperatures were used for fuel element damage calculation. The accumulated cladding damage of fuel element was found to be very small and fuel element failure resulting from SHRT transients is unlikely. No element breach was noted during the SHRT transients. The reactor was immediately restarted after the most severe SHRT transient had been completed and no driver fuel breach has been noted to date. (orig.)

  3. The EBR-II materials-surveillance program. 4: Results of SURV-4 and SURV-6

    International Nuclear Information System (INIS)

    Ruther, W.E.; Hayner, G.O.; Carlson, B.G.; Ebersole, E.R.; Allen, T.R.

    1998-01-01

    In March of 1965, a set of surveillance (SURV) samples was placed in the EBR-II reactor to determine the effect of irradiation, thermal aging, and sodium corrosion on reactor materials. Eight subassemblies were placed into row 12 positions of EBR-II to determine the effect of irradiation at 370 C. Two subassemblies were placed into the primary sodium basket to determine the effect of thermal aging at 370 C. For both the irradiated and thermally aged samples, one half of all samples were exposed to primary system sodium while one half were sealed in capsules with a helium atmosphere. Fifteen different structural materials were tested in the SURV program. In addition to the fifteen types of metal samples, graphite blocks were irradiated in the SURV subassemblies to determine the effect of irradiation on the graphite neutron shield. In this report, the properties of these materials irradiated at 370 C to a total fluence of 2.2 x 10 22 n/cm 2 (over 2,994 days) are compared with those of similar specimens thermally aged at 370 C for 2,994 days in the storage basket of the reactor. The properties analyzed were weight, density, microstructure, hardness, tensile and yield strength, impact strength, and creep

  4. Further Evidence on the Effect of Acquisition Policy and Process on Cost Growth of Major Defense Acquisition Programs (Revised)

    Science.gov (United States)

    2016-08-01

    average cost growth is not typical. Figure B-1. Histogram of Quantity Normalized APUC Growth from MS II/B Baseline B. Business Rules Almost all of...did not in all cases follow the business rules used in P-5126 and this paper. There were several MDAPs from the 1960s and 1970s for which we had two...periods used in the main text. Standard errors were estimated using the Stata bootstrap procedure with 20 replications. The results are presented

  5. Integrated Data Collection Analysis (IDCA) Program - RDX Type II Class 5 Standard, Data Set 1

    Energy Technology Data Exchange (ETDEWEB)

    Sandstrom, Mary M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Brown, Geoffrey W. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Preston, Daniel N. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Pollard, Colin J. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Warner, Kirstin F. [Naval Surface Warfare Center (NSWC), Indian Head, MD (United States). Indian Head Division; Sorenson, Daniel N. [Naval Surface Warfare Center (NSWC), Indian Head, MD (United States). Indian Head Division; Remmers, Daniel L. [Naval Surface Warfare Center (NSWC), Indian Head, MD (United States). Indian Head Division; Moran, Jesse S. [Naval Surface Warfare Center (NSWC), Indian Head, MD (United States). Indian Head Division; Shelley, Timothy J. [Air Force Research Lab. (AFRL), Tyndall AFB, FL (United States); Reyes, Jose A. [Applied Research Associates, Inc., Tyndall AFB, FL (United States); Hsu, Peter C. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Whipple, Richard E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Reynolds, John G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2011-04-11

    This document describes the results of the first reference sample material—RDX Type II Class 5—examined in the proficiency study for small-scale safety and thermal (SSST) testing of explosive materials for the Integrated Data Collection Analysis (IDCA) Program. The IDCA program is conducting proficiency testing on homemade explosives (HMEs). The reference sample materials are being studied to establish the accuracy of traditional explosives safety testing for each performing laboratory. These results will be used for comparison to results from testing HMEs. This effort, funded by the Department of Homeland Security (DHS), ultimately will put the issues of safe handling of these materials in perspective with standard military explosives. The results of the study will add SSST testing results for a broad suite of different HMEs to the literature, potentially suggest new guidelines and methods for HME testing, and possibly establish what are the needed accuracies in SSST testing to develop safe handling practices. Described here are the results for impact, friction, electrostatic discharge, and scanning calorimetry analysis of a reference sample of RDX Type II Class 5. The results from each participating testing laboratory are compared using identical test material and preparation methods wherever possible. Note, however, the test procedures differ among the laboratories. These results are then compared to historical data from various sources. The performers involved are Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Air Force Research Laboratory/ RXQL (AFRL), Indian Head Division, Naval Surface Warfare Center, (IHD-NSWC), and Sandia National Laboratories (SNL). These tests are conducted as a proficiency study in order to establish some consistency in test protocols, procedures, and experiments and to understand how to compare results when test protocols are not identical.

  6. The EBR-II materials-surveillance program. 5: Results of SURV-5

    International Nuclear Information System (INIS)

    Ruther, W.E.; Staffon, J.D.; Carlson, B.G.; Allen, T.R.

    1998-01-01

    In March of 1965, a set of surveillance (SURV) samples was placed in the EBR-II reactor to determine the effect of irradiation, thermal aging, and sodium corrosion on reactor materials. Eight subassemblies were placed into row 12 positions of EBR-II to determine the effect of irradiation at 370 C. Two subassemblies were placed into the primary sodium basket to determine the effect of thermal aging at 370 C. One half of all samples were exposed to primary system sodium while one half were sealed in capsules with a helium atmosphere. Fifteen different structural materials were tested in the SURV program. In this work, the properties of these materials irradiated at 370 C to a total fluence of 3.2 x 10 22 n/cm 2 were determined. These materials are the fifth set of irradiated subassemblies to be examined as part of the SURV program (SURV-5). The properties analyzed were weight, density, microstructure, hardness, tensile and yield strength, and fracture resistance. Of all the alloys examined in SURV-5, only Berylco-25 showed any significant weight loss. Stainless steel (both 304 and 347) had the largest density decrease, although the density decrease from irradiation for all alloys was less than 0.4 percent. The microstructure of both Berylco-25 and the aluminum-bronze alloy was altered significantly. Iron- and nickel-base alloys showed little change in microstructure. Austenitic steels (304 and 347) harden with irradiation. The hardness of Inconel X750 did not change significantly with irradiation. The ultimate tensile strength of Inconel X750, 304 stainless steel, 420 stainless steel and welded 304 changed little due to a fluence increase from 2.2 x 10 22 n/cm 2 (the maximum fluence of the SURV-4 samples) to 3.2 x 10 22 n/cm 2

  7. Research on radionuclide migration under subsurface geochemical conditions. JAERI/AECL Phase II Collaborative Program Year 1 (joint research)

    International Nuclear Information System (INIS)

    1998-11-01

    A radionuclide migration experiment program for fractured rocks was performed under the JAERI/AECL Phase-II Collaborative Program on research and development in radioactive waste management. The program started in the fiscal year 1993, as a five-year program consists of Quarried block radionuclide migration program, Speciation of long-lived radionuclides in groundwater, Isotopic hydrogeology and Groundwater flow model development. During the first year of the program (Program Year 1: March 18, 1994 - September 30, 1994), a plan was developed to take out granite blocks containing part of natural water-bearing fracture from the wall of the experimental gallery at the depth of 240 m, and literature reviews were done in the area of the speciation of long-lived radionuclides in groundwater, isotopic hydrogeology and the groundwater flow model development to proceed further work for the Program Year 2. (author)

  8. Nevada Test Site Radiological Control Manual. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2010-02-09

    This document supersedes DOE/NV/25946--801, “Nevada Test Site Radiological Control Manual,” Revision 0 issued in October 2009. Brief Description of Revision: A minor revision to correct oversights made during revision to incorporate the 10 CFR 835 Update; and for use as a reference document for Tenant Organization Radiological Protection Programs.

  9. 75 FR 80037 - Poultry Programs; Notice of Request for an Extension and Revision of a Currently Approved...

    Science.gov (United States)

    2010-12-21

    ... DEPARTMENT OF AGRICULTURE Agricultural Marketing Service [Doc. No. AMS-PY-10-0098] Poultry... David Bowden, Jr., Chief, Standards, Promotion, & Technology Branch; Poultry Programs, AMS, U.S.... FOR FURTHER INFORMATION CONTACT: Sara Lutton, Standards, Promotion, & Technology Branch; Poultry...

  10. 76 FR 72005 - NUREG-1556, Volume 2, Revision 1, “Consolidated Guidance About Materials Licenses Program...

    Science.gov (United States)

    2011-11-21

    ... Herrera, Division of Materials Safety and State Agreements, Office of Federal and State Materials and Environmental Management Programs, telephone (301) 415-7138, email: Tomas.Herrera@nrc.gov . NRC's Public Web...

  11. Lawrence Livermore National Laboratory (LLNL) Oxide Material Representation in the Material Identification and Surveillance (MIS) Program, Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Riley, D C; Dodson, K

    2004-06-30

    The Materials Identification and Surveillance (MIS) program was established within the 94-1 R&D Program to confirm the suitability of plutonium-bearing materials for stabilization, packaging, and long-term storage under DOE-STD-3013-2000. Oxide materials from different sites were chemically and physically characterized. The adequacy of the stabilization process parameters of temperature and duration at temperature (950 C and 2 hours) for eliminating chemical reactivity and reducing the moisture content to less than 0.5 weight percent were validated. Studies also include surveillance monitoring to determine the behavior of the oxides and packaging materials under storage conditions. Materials selected for this program were assumed to be representative of the overall inventory for DOE sites. The Quality Assurance section of the DOE-STD-3013-2000 required that each site be responsible for assuring that oxides packaged according to this standard are represented by items in the MIS characterization program. The purpose of this document is to define the path for determining if an individual item is ''represented'' in the MIS Program and to show that oxides being packaged at Lawrence Livermore National Laboratory (LLNL) are considered represented in the MIS program. The methodology outlined in the MIS Representation Document (LA-14016-MS) for demonstrating representation requires concurrence of the MIS working Group (MIS-WG). The signature page on this document provides for the MIS-WG concurrence.

  12. Nociones de la programacion de lenguas extranjeras; Ensayo metodologico (II) (Notions on Programed Instruction in Foreign Languages; Methodological Essay II)

    Science.gov (United States)

    Feldman, David

    1975-01-01

    This paper discusses the prerequisites to programed language instruction, the role of the native language and the level of skill, and then explains materials and machines needed for such a program. Particular attention is given to phonetics. (Text is in Spanish.) (CK)

  13. Independent oversight review of the Department of Energy Quality Assurance Program for suspect/counterfeit parts. Revision 1

    International Nuclear Information System (INIS)

    1996-05-01

    To address the potential threat that suspect/counterfeit parts could pose to DOE workers and the public, the Office of the Deputy Assistant Secretary for Oversight initiated a number of activities beginning in mid-1995. Oversight placed increased emphasis on the field's quality assurance-suspect/counterfeit parts programs during safety management evaluations, in keeping with the Office of Environment, Safety and Health (EH) oversight responsibilities, which include oversight of the Department's quality assurance (QA) programs. In addition, Oversight reviewed relevant policy documents and occurrence reports to determine the nature and magnitude of the problem within the Department. The results of that review, contained in an Office of Oversight report, Independent Oversight Analysis of Suspect/Counterfeit Parts Within the Department of Energy (November 1995), indicate a lack of consistency and comprehensiveness in the Department's QA-suspect/counterfeit parts program. A detailed analysis of the causes and impacts of the problem was recommended. In response, this review was initiated to determine the effectiveness of the Department's QA program for suspect/counterfeit parts. This study goes beyond merely assessing and reporting the status of the program, however. It is the authors intention to highlight the complex issues associated with suspect/counterfeit parts in the Department today and to present approaches that DOE managers might consider to address these issues

  14. Independent oversight review of the Department of Energy Quality Assurance Program for suspect/counterfeit parts. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-05-01

    To address the potential threat that suspect/counterfeit parts could pose to DOE workers and the public, the Office of the Deputy Assistant Secretary for Oversight initiated a number of activities beginning in mid-1995. Oversight placed increased emphasis on the field`s quality assurance-suspect/counterfeit parts programs during safety management evaluations, in keeping with the Office of Environment, Safety and Health (EH) oversight responsibilities, which include oversight of the Department`s quality assurance (QA) programs. In addition, Oversight reviewed relevant policy documents and occurrence reports to determine the nature and magnitude of the problem within the Department. The results of that review, contained in an Office of Oversight report, Independent Oversight Analysis of Suspect/Counterfeit Parts Within the Department of Energy (November 1995), indicate a lack of consistency and comprehensiveness in the Department`s QA-suspect/counterfeit parts program. A detailed analysis of the causes and impacts of the problem was recommended. In response, this review was initiated to determine the effectiveness of the Department`s QA program for suspect/counterfeit parts. This study goes beyond merely assessing and reporting the status of the program, however. It is the authors intention to highlight the complex issues associated with suspect/counterfeit parts in the Department today and to present approaches that DOE managers might consider to address these issues.

  15. Toxicological benchmarks for screening contaminants of potential concern for effects on sediment-associated biota: 1994 Revision. Environmental Restoration Program

    International Nuclear Information System (INIS)

    Hull, R.N.; Suter, G.W. II

    1994-06-01

    Because a hazardous waste site may contain hundreds of chemicals, it is important to screen contaminants of potential concern for the ecological risk assessment. Often this screening is done as part of a Screening Assessment, the purpose of which is to evaluate the available data, identify data gaps, and screen contaminants of potential concern. Screening may be accomplished by using a set of toxicological benchmarks. These benchmarks are helpful in determining whether contaminants warrant further assessment or are at a level that requires no further attention. If a chemical concentration or the reported detection limit exceeds a proposed lower benchmark, more analysis is needed to determine the hazards posed by that chemical. If, however, the chemical concentration falls below the lower benchmark value, the chemical may be eliminated from further study. This report briefly describes three categories of approaches to the development of sediment quality benchmarks. These approaches are based on analytical chemistry, toxicity test and field survey data. A fourth integrative approach incorporates all three types of data. The equilibrium partitioning approach is recommended for screening nonpolar organic contaminants of concern in sediments. For inorganics, the National Oceanic and Atmospheric Administration has developed benchmarks that may be used for screening. There are supplemental benchmarks from the province of Ontario, the state of Wisconsin, and US Environmental Protection Agency Region V. Pore water analysis is recommended for polar organic compounds; comparisons are then made against water quality benchmarks. This report is an update of a prior report. It contains revised ER-L and ER-M values, the five EPA proposed sediment quality criteria, and benchmarks calculated for several nonionic organic chemicals using equilibrium partitioning

  16. Environmental Guidance Program Reference Book: Marine Protection, Research, and Sanctuaries Act and Marine Mammal Protection Act. Revision 3

    Energy Technology Data Exchange (ETDEWEB)

    1988-01-31

    Two laws governing activities in the marine environment are considered in this Reference Book. The Marine Protection, Research, and Sanctuaries Act (MPRSA, P.L. 92-532) regulates ocean dumping of waste, provides for a research program on ocean dumping, and provides for the designation and regulation of marine sanctuaries. The Marine Mammal Protection Act (MMPA, P.L. 92-522) establishes a federal program to protect and manage marine mammals. The Fishery Conservation and Management Act (FCMA, P.L. 94-265) establishes a program to regulate marine fisheries resources and commercial marine fishermen. Because the Department of Energy (DOE) is not engaged in any activities that could be classified as fishing under FCMA, this Act and its regulations have no implications for the DOE; therefore, no further consideration of this Act is given within this Reference Book. The requirements of the MPRSA and the MMPA are discussed in terms of their implications for the DOE.

  17. 76 FR 42771 - Medicare Program; Payment Policies Under the Physician Fee Schedule and Other Revisions to Part B...

    Science.gov (United States)

    2011-07-19

    ... Payment Window. Pam West, (410) 786-2302, for issues related to the technical corrections. Rebecca Cole or... artery bypass graft CAD--Coronary artery disease CAH--Critical Access Hospital CAHEA--Committee on Allied... Program CBSA--Core-Based Statistical Area CDC--Centers for Disease Control and Prevention CEM--Cardiac...

  18. 77 FR 17086 - Section 8 Housing Choice Vouchers: Revised Implementation of the HUD-VA Supportive Housing Program

    Science.gov (United States)

    2012-03-23

    ... Housing g. Mobility and Portability of HUD-VASH Vouchers h. Case Management Requirements i. Turnover of... veterans with case management and clinical services provided by the VA through its community medical... services sites and Community-Based Outpatient Clinics (CBOCs) across the nation. The HUD- VASH program is a...

  19. Tank Waste Remediation System fiscal year 1996 multi-year program plan WBS 1.1. Revision 1, Volume 1

    International Nuclear Information System (INIS)

    1995-09-01

    The 1995 Hanford Mission Plan specifically addresses the tank waste issue and clarifies the link with other initiatives, such as improving management practices and the Hanford Site Waste Minimization and Pollution Prevention Awareness Program Plan (DOE/RL-91-31). This document captures the results of decision making regarding the application of systems engineering at the Hanford Site, external involvement policy, and site end-state goals. Section 3.5 of the Hanford Mission Plan on Decisions and Directives provides an integrating discussion of the actions of the National Environmental Policy Act (NEPA), and DOE policy, guidance, and decisions associated with binding agreements such as the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement). Two significant components of the Hanford Mission Plan 1994 planning basis are (1) the decisions regarding the disposition of onsite material inventory, and the key programs and interfaces to accomplish this; and (2) the Program Interface Issues section, which identified issues that stretch across program boundaries

  20. 77 FR 23228 - Notice of Submission for OMB Review; Small Business Innovation Research (SBIR) Program-Phase II...

    Science.gov (United States)

    2012-04-18

    ... business concerns to submit a Phase II application for the Small Business Innovation Research (SBIR) Program (CFDA 84.133). This is in response to Public Law 106-554, the ``Small Business Reauthorization Act... DEPARTMENT OF EDUCATION Notice of Submission for OMB Review; Small Business Innovation Research...

  1. Tank Waste Remediation System fiscal year 1996 multi-year program plan WBS 1.1. Revision 1, Appendix A

    International Nuclear Information System (INIS)

    1995-09-01

    This document is a compilation of data relating to the Tank Waste Remediation System Multi-Year Program. Topics discussed include: management systems; waste volume, transfer and evaporation management; transition of 200 East and West areas; ferricyanide, volatile organic vapor, and flammable gas management; waste characterization; retrieval from SSTs and DSTs; heat management; interim storage; low-level and high-level radioactive waste management; and tank farm closure

  2. Second program of materials irradiation within VISA-2 Project, Parts I-II, Part II; Drugi program ozracivanja materijala po projektu VISA-2, I-II Deo, II Deo

    Energy Technology Data Exchange (ETDEWEB)

    Pavicevic, M; Smokovic, Z [Institute of Nuclear Sciences Boris Kidric, Odeljenje za reaktorsku eksperimentalnu tehniku, Vinca, Beograd (Serbia and Montenegro)

    1965-03-15

    This second program of irradiating the materials in special VISA-2 experimental channels includes irradiation of 8 capsules with French graphite, magnesium and aluminium oxides, zircaloy, leak tight capsules with Zirconium and steel samples; capsules with domestic graphite, iron, domestic steel and molybdenum samples. This volume of the report includes design specification and engineering drawings of VISA-2 different irradiation capsules to be used and of the devices needed for completing the task.

  3. Phase II Corrective Action Investigation Plan for Corrective Action Units 101 and 102: Central and Western Pahute Mesa, Nevada Test Site, Nye County, Nevada, Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Jeff Wurtz

    2009-07-01

    This Phase II CAIP describes new work needed to potentially reduce uncertainty and achieve increased confidence in modeling results. This work includes data collection and data analysis to refine model assumptions, improve conceptual models of flow and transport in a complex hydrogeologic setting, and reduce parametric and structural uncertainty. The work was prioritized based on the potential to reduce model uncertainty and achieve an acceptable level of confidence in the model predictions for flow and transport, leading to model acceptance by NDEP and completion of the Phase II CAI stage of the UGTA strategy.

  4. Revision of documents guide to obtain the renovation of licence of the nuclear power plant of Laguna Verde, Units I and II

    International Nuclear Information System (INIS)

    Jarvio C, G.; Fernandez S, G.

    2008-01-01

    Unquestionably the renovation of license of the nuclear power plants , it this converting in a promising option to be able to gather in sure, reliable form and economic those requests about future energy in the countries with facilities of this type. This work it analyzes four documents guide and their application for the determination of the renovation of it licenses in nuclear plants that will serve of base for their aplication in the Nuclear Power Plant of Laguna Verde Units I and 2. The four documents in question are: the one Inform Generic of Learned Lessons on the Aging (NUREG - 1801), the Standard Revision Plan for the Renovation of License (NUREG - 1800), the Regulatory Guide for Renovation of License (GR-1.188), and the NEI 95-10, developed by the Institute of Nuclear Energy that is an Industrial Guide to Implement the Requirements of the 1OCFR Part 54-the Rule of Renovation of It licenses. (Author)

  5. Performance-based improvement of the leakage rate test program for the reactor containment of HTTR. Adoption of revised test programs containing 'Type A, Type B and Type C tests'

    International Nuclear Information System (INIS)

    Kondo, Masaaki; Emori, Koichi; Sekita, Kenji; Furusawa, Takayuki; Hayakawa, Masato; Kozawa, Takayuki; Aono, Tetsuya; Kuroha, Misao; Ouchi, Hiroshi; Kimishima, Satoru

    2008-10-01

    The reactor containment of HTTR is periodically tested to confirm leak-tight integrity by conducting overall integrated leakage rate tests, so-called 'Type A tests,' in accordance with a standard testing method provided in Japan Electric Association Code (JEAC) 4203. 'Type A test' is identified as a basic one for measuring whole leakage rates for reactor containments, it takes, however, much of cost and time of preparation, implementation and restoration of itself. Therefore, in order to upgrade the maintenance technology of HTTR, the containment leakage rate test program for HTTR was revised by adopting efficient and economical alternatives including Type B and Type C tests' which intend to measure leakage rates for containment penetrations and isolation valves, respectively. In JEAC4203-2004, following requirements are specified for adopting an alternative program: upward trend of the overall integrated leakage rate due to aging affection should not be recognized; performance criterion for combined leakage rate, that is a summation of local leakage rates evaluated by Type B and Type C tests and converted to whole leakage rates, should be established; the criterion of the combined leakage rate should be satisfied as well as of the overall integrated leakage rate; correlation between the overall integrated and combined leakage rates should be recognized. Considering the historical performances, policies of conforming to the forgoing requirements and of carrying out the revised test program were developed, which were accepted by the regulatory agency. This report presents an outline of the leakage rate tests for the reactor containment of HTTR, identifies practical issues of conventional Type A tests, and describes the conforming and implementing policies mentioned above. (author)

  6. Specification and R and D Program on Magnet Alignment Tolerances for NSLS-II

    International Nuclear Information System (INIS)

    Kramer, S.L.; Jain, A.K.

    2009-01-01

    The NSLS-II light source is a proposed 3 GeV storage ring, with the potential for ultra-low emittance. Despite the reduced emittance goal for the bare lattice, the closed orbit amplification factors are on average >55 in both planes, for random quadrupole alignment errors. The high chromaticity will also require strong sextupoles and the low 3 GeV energy will require large dynamic and momentum aperture to insure adequate lifetime. This will require tight alignment tolerances (∼ 30(micro)m) on the multipole magnets during installation. By specifying tight alignment tolerances of the magnets on the support girders, the random alignment tolerances of the girders in the tunnel can be significantly relaxed. Using beam based alignment to find the golden orbit through the quadrupole centers, the closed orbit offsets in the multipole magnets will then be reduced to essentially the alignment errors of the magnets, restoring much of the dynamic aperture and lifetime of the bare lattice. Our R and D program to achieve these tight alignment tolerances of the magnets on the girders using a vibrating wire technique, will be discussed and initial results presented.

  7. Financial Accounting: Classifications and Standard Terminology for Local and State School Systems. State Educational Records and Reports Series: Handbook II, Revised.

    Science.gov (United States)

    Roberts, Charles T., Comp.; Lichtenberger, Allan R., Comp.

    This handbook has been prepared as a vehicle or mechanism for program cost accounting and as a guide to standard school accounting terminology for use in all types of local and intermediate education agencies. In addition to classification descriptions, program accounting definitions, and proration of cost procedures, some units of measure and…

  8. Evaluation of geophysical techniques for identifying fractures in program wells in Deaf Smith County, Texas: Revision 1, Topical report

    International Nuclear Information System (INIS)

    Gillespie, R.P.; Siminitz, P.C.

    1987-08-01

    Quantitative information about the presence and orientation of fractures is essential for the understanding of the geomechanical and geohydrological behavior of rocks. This report evaluates various borehole geophysical techniques for characterizing fractures in three Civilian Radioactive Waste Management (CRWM) Program test wells in the Palo Duro Basin in Deaf Smith County, Texas. Emphasis has been placed on the Schlumberger Fracture Identification Log (FIL) which detects vertical fractures and provides data for calculation of orientation. Depths of FIL anomalies were compared to available core. It was found that the application of FIL results to characterize fracture frequency or orientation is inappropriate at this time. The uncertainties associated with the FIL information render the information unreliable. No geophysical logging tool appears to unequivocally determine the location and orientation of fractures in a borehole. Geologic mapping of the exploratory shafts will ultimately provide the best data on fracture frequency and orientation at the proposed repository site. 22 refs., 6 figs., 3 tabs

  9. Identification of 5g and 6g terms and revised ionization energies in the Yb II 4f14nl isoelectronic sequence

    International Nuclear Information System (INIS)

    Sugar, J.; Kaufman, V.

    1979-01-01

    The 5f-5g transitions in Lu III through Os VIII and the 5f-6g transitions in Hf IV through W VI were identified and used to redetermine the ionization energies of Yb II, Lu III, W VI, Re VII, and Os VIII. Complete line-lists and energy levels are given for the one-electron spectra Hf IV, W VI and Os VIII

  10. Identification of 5g and 6g terms and revised ionization energies in the Yb II 4f/sup 14/nl isoelectronic sequence

    Energy Technology Data Exchange (ETDEWEB)

    Sugar, J.; Kaufman, V.

    1979-01-01

    The 5f-5g transitions in Lu III through Os VIII and the 5f-6g transitions in Hf IV through W VI were identified and used to redetermine the ionization energies of Yb II, Lu III, W VI, Re VII, and Os VIII. Complete line-lists and energy levels are given for the one-electron spectra Hf IV, W VI and Os VIII.

  11. Tuberculosis related stigma and its effect on the delay for sputum examination under the Revised National Tuberculosis Control Program in India.

    Science.gov (United States)

    Chakrabartty, Arupkumar; Basu, Pampa; Ali, Kazi Monjur; Sarkar, Aditi Kishore; Ghosh, Debidas

    2018-04-01

    One major barrier to achieve goal of tuberculosis (TB) control program globally, is the stigma attached to the disease. Perceived stigma can delay sputum test in time. Delay will lead to spread of infection in the community. There is no scientific information available in India exactly looking into the association between delay in sputum examination and stigma. We conducted a study in rural West Bengal among persons with cough for 2 weeks or more to assess their level of stigma, its influence on delay for sputum test and identify factors those shape the level of stigma. A community based cross sectional survey was conducted from February to June 2015 in West Bengal, India. We interviewed 135 persons of 15-60 years. Data were collected using a pretested structured questionnaire. Chi-square and logistic regression analysis were done using SPSS 23.0 statistical software. Among the 'lower stigma' group (score 4-24), 'delay' (14-25 days) is found among 46.2% respondents and 'much delay' (26-120 days) among 53.8%. Among the 'higher stigma' (score 25-36) group, 'delay' is found among 20.5% respondents and 'much delay' among 79.5%. Persons with lower stigma are 0.17 times likely to delay than persons with higher stigma [adjusted odds ratio (AOR): 0.17 (0.044-0.668), p=0.011)]. Important influencers of stigma are caste [AOR: 5.90 (1.66-20.90), p=0.006], number of family members [AOR: 3.46 (1.08-11.06), p=0.009] and residence in urban or rural [AOR: 3.97 (1.03-15.27), p=0.045]. Revised National Tuberculosis Control Program in India should de-stigmatize the community giving priorities to lower castes, big families and rural areas. Copyright © 2017 Tuberculosis Association of India. Published by Elsevier B.V. All rights reserved.

  12. Early Site Permit Demonstration Program: Siting Guide, Site selection and evaluation criteria for an early site permit application. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    1993-03-24

    In August 1991, the Joint Contractors came to agreement with Sandia National Laboratories (SNL) and the Department of Energy (DOE) on a workscope for the cost-shared Early Site Permit Demonstration Program. One task within the scope was the development of a guide for site selection criteria and procedures. A generic Siting Guide his been prepared that is a roadmap and tool for applicants to use developing detailed siting plans for their specific region of the country. The guide presents three fundamental principles that, if used, ensure a high degree of success for an ESP applicant. First, the site selection process should take into consideration environmentally diverse site locations within a given region of interest. Second, the process should contain appropriate opportunities for input from the public. Third, the process should be applied so that it is clearly reasonable to an impartial observer, based on appropriately selected criteria, including criteria which demonstrate that the site can host an advanced light water reactor (ALWR). The Siting Guide provides for a systematic, comprehensive site selection process in which three basic types of criteria (exclusionary, avoidance, and suitability) are presented via a four-step procedure. It provides a check list of the criteria for each one of these steps. Criteria are applied qualitatively, as well as presented numerically, within the guide. The applicant should use the generic guide as an exhaustive checklist, customizing the guide to his individual situation.

  13. Fractional Programming for Communication Systems—Part II: Uplink Scheduling via Matching

    Science.gov (United States)

    Shen, Kaiming; Yu, Wei

    2018-05-01

    This two-part paper develops novel methodologies for using fractional programming (FP) techniques to design and optimize communication systems. Part I of this paper proposes a new quadratic transform for FP and treats its application for continuous optimization problems. In this Part II of the paper, we study discrete problems, such as those involving user scheduling, which are considerably more difficult to solve. Unlike the continuous problems, discrete or mixed discrete-continuous problems normally cannot be recast as convex problems. In contrast to the common heuristic of relaxing the discrete variables, this work reformulates the original problem in an FP form amenable to distributed combinatorial optimization. The paper illustrates this methodology by tackling the important and challenging problem of uplink coordinated multi-cell user scheduling in wireless cellular systems. Uplink scheduling is more challenging than downlink scheduling, because uplink user scheduling decisions significantly affect the interference pattern in nearby cells. Further, the discrete scheduling variable needs to be optimized jointly with continuous variables such as transmit power levels and beamformers. The main idea of the proposed FP approach is to decouple the interaction among the interfering links, thereby permitting a distributed and joint optimization of the discrete and continuous variables with provable convergence. The paper shows that the well-known weighted minimum mean-square-error (WMMSE) algorithm can also be derived from a particular use of FP; but our proposed FP-based method significantly outperforms WMMSE when discrete user scheduling variables are involved, both in term of run-time efficiency and optimizing results.

  14. A REVISION OF THE PLIOCENE NATICIDS OF NORTHERN AND CENTRAL ITALY. II. THE SUBFAMILY NATICINAE: ADDITIONS TO COCHLIS, TANEA AND TECTONATICA

    Directory of Open Access Journals (Sweden)

    LUCA PEDRIALI

    2008-03-01

    Full Text Available The present paper is the second in a series devoted to the revision of the Pliocene naticids of Northern and Central Italy. It concludes the section covering the calcareous operculum-bearing Naticinae and expands to 18 the total number of species and subspecies of this subfamily recovered so far from the Pliocene deposits of Italy. Of the six taxa considered in this study, two (epigloafuniculata and fredianii fully match the characters of the genus Cochlis Röding, 1798, one (koeneni is assigned to the genus Tanea Marwick, 1931, the rest (astensis, prietoi and tectula belong to the genus Tectonatica Sacco, 1890. All the six taxa considered in this paper are described and commented in the systematic account. One, Cochlis fredianii, is proposed as new. In the chapter treating the generic assignment of the studied taxa, the range of Tanea, hitherto used to allocate several Indo-Pacific species, is extended to the Mediterranean Basin as well, and the relations between Tectonatica and Cryptonatica Dall, 1892 are discussed. This study further demonstrates that the morphological characters of the teleoconch are of low significance in species recognition. In fact, should the characters be ranked, the operculum comes first and is the primary element, sufficient to distinguish each species. The protoconch and the color pattern are the second and third relevant attributes that can be used diagnostically for several taxa, but not always. The other shell features appear to be useful tools in separating species only occasionally. Some species lack distinctive shell characters and do require operculate specimens in order to be confidently 

  15. Mark II containment program load evaluation and acceptance criteria; Generic Technical Activity A-8

    International Nuclear Information System (INIS)

    Anderson, C.J.

    1981-08-01

    The report provides a discussion of LOCA-related suppression pool hydrodynamic loads in boiling water reactor (BWR) facilities with the Mark II pressure-suppression containment design. This report concludes NRC Generic Technical Activity A-8, 'Mark II Containment Pool Dynamic Loads,' which has been designated an 'Unresolved Safety Issue' pursuant to Section 210 of the Energy Reorganization Act of 1974

  16. A report on intercomparison studies of computer programs which respectively model: i) radionuclide migration ii) equilibrium chemistry of groundwater

    International Nuclear Information System (INIS)

    Broyd, T.W.; McD Grant, M.; Cross, J.E.

    1985-01-01

    This report describes two intercomparison studies of computer programs which respectively model: i) radionuclide migration ii) equilibrium chemistry of groundwaters. These studies have been performed by running a series of test cases with each program and comparing the various results obtained. The work forms a part of the CEC MIRAGE project (MIgration of RAdionuclides in the GEosphere) and has been jointly funded by the CEC and the United Kingdom Department of the Environment. Presentations of the material contained herein were given at plenary meetings of the MIRAGE project in Brussels in March, 1984 (migration) and March, 1985 (equilibrium chemistry) respectively

  17. A user`s guide to LUGSAN II. A computer program to calculate and archive lug and sway brace loads for aircraft-carried stores

    Energy Technology Data Exchange (ETDEWEB)

    Dunn, W.N. [Sandia National Labs., Albuquerque, NM (United States). Mechanical and Thermal Environments Dept.

    1998-03-01

    LUG and Sway brace ANalysis (LUGSAN) II is an analysis and database computer program that is designed to calculate store lug and sway brace loads for aircraft captive carriage. LUGSAN II combines the rigid body dynamics code, SWAY85, with a Macintosh Hypercard database to function both as an analysis and archival system. This report describes the LUGSAN II application program, which operates on the Macintosh System (Hypercard 2.2 or later) and includes function descriptions, layout examples, and sample sessions. Although this report is primarily a user`s manual, a brief overview of the LUGSAN II computer code is included with suggested resources for programmers.

  18. Technical summary of Groundwater Quality Protection Program at Savannah River Plant. Volume II. Radioactive waste

    International Nuclear Information System (INIS)

    Stone, J.A.; Christensen, E.J.

    1983-12-01

    This report (Volume II) presents representative monitoring data for radioactivity in groundwater at SRP. Four major groups of radioactive waste disposal sites and three minor sites are described. Much of the geohydrological and and other background information given in Volume I is applicable to these sites and is incorporated by reference. Several of the sites that contain mixed chemical and radioactive wastes are discussed in both Volumes I and II. Bulk unirradiated uranium is considered primarily a chemical waste which is addressed in Volume I, but generally not in Volume II

  19. A study of the patients suffering from tuberculosis and tuberculosis-diabetes comorbidity in Revised National Tuberculosis Control Program Centers of Northern Madhya Pradesh, India

    Directory of Open Access Journals (Sweden)

    Anil Kumar Agarwal

    2017-01-01

    Full Text Available Background: Diabetes mellitus (DM is recognized as an important risk factor to tuberculosis (TB. India has high TB burden, along with rising DM prevalence. Aim: This study was conducted to document the coexistence of DM and TB in persons with established TB under the Revised National Tuberculosis Control Program. Type of Study: This was a cross-sectional, descriptive observational study conducted at selected Directly Observed Therapy center in Gwalior North Central India. Materials and Methods: A total of 550 patients with confirmed diagnosis of TB and on treatment were recruited. The study participants were screened for DM and diagnoses were made on the basis of the World Health Organization criteria. Clinical parameters were compared between persons with DM and those without DM. Results: DM/TB co-morbidity was noted in 85 individuals and these made up 15.4% of the study population. The mean age was higher in DM patients with TB (43.4 ± 15.4 vs. 33.1 ± 16.2 years, P = 0.000; the mean duration of symptoms of TB with DM was more (124 ± 16.4 vs. 107.49 ± 10.3 days. Multinomial logistic regression analysis showed that increasing age, positive family history of diabetes, sedentary occupation, and presence of pulmonary TB were significantly associated with diabetes among TB patients. Conclusions: Diabetes is an important co-morbid feature to be sought in patients with TB. This study re-echo the need to raise awareness on screening for DM in persons with TB.

  20. Participants' comments on changes in the revised special supplemental nutrition program for women, infants, and children food packages: the Maryland food preference study.

    Science.gov (United States)

    Black, Maureen M; Hurley, Kristen M; Oberlander, Sarah E; Hager, Erin R; McGill, Adrienne E; White, Nneka T; Quigg, Anna M

    2009-01-01

    The Institute of Medicine recommended changes in the Special Supplemental Nutrition Program for Women, Infants, and Children (WIC) food packages to help families from diverse populations establish more healthful dietary patterns. A cross-sectional study conducted during summer 2007 included interviews and focus groups with 223 WIC participants throughout Maryland. The objectives were to examine participants' responses to food package changes, to identify racial/ethnic differences, and to assess costs. All participants (100%) consumed fruits and vegetables. They preferred fresh for taste, but many endorsed canned and frozen for convenience and cost. Most women (56%) and children (69%) consumed whole milk and did not want reduced-fat milk. Few participants (13%) consumed soy products and most were uninterested in future consumption. Participants endorsed whole-wheat bread as more healthful and reported that they (59%) and their children (51%) would increase consumption if provided by WIC. Non-Hispanic participants preferred peanut butter over beans, Hispanic participants reported that they (44%) and their children (57%) would consume more beans (substituting for peanut butter) if provided by WIC. There were few differences in preferences between African-American and white participants. Hispanics differed from non-Hispanics in preference for beans and dislike of frozen and canned vegetables, suggesting the importance of choices. The proposed food packages were cost-neutral, except when extensive substitutions with soy products were allowed. By providing fruits and vegetables, reduced-fat options, and increased opportunities for nutrition education, the revised food packages may reduce the risk of obesity among low-income women, infants, and children.

  1. Collection of Baseline Studies of the Food for Peace Title II Development Food Assistance Programs

    Data.gov (United States)

    US Agency for International Development — USAID's Office of Food for Peace (FFP) awards funding to private voluntary organizations (PVOs) to design and implement multi-year Title II development food...

  2. Corrective Action Decision Document/Corrective Action Plan for Corrective Action Unit 413: Clean Slate II Plutonium Dispersion (TTR) Tonopah Test Range, Nevada. Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    Matthews, Patrick [Navarro, Las Vegas, NV (United States)

    2017-05-01

    This Corrective Action Decision Document/Corrective Action Plan provides the rationale and supporting information for the selection and implementation of corrective actions at Corrective Action Unit (CAU) 413, Clean Slate II Plutonium Dispersion (TTR). CAU 413 is located on the Tonopah Test Range and includes one corrective action site, TA-23-02CS. CAU 413 consists of the release of radionuclides to the surface and shallow subsurface from the Clean Slate II (CSII) storage–transportation test conducted on May 31, 1963. The CSII test was a non-nuclear detonation of a nuclear device located inside a concrete bunker covered with 2 feet of soil. To facilitate site investigation and the evaluation of data quality objectives decisions, the releases at CAU 413 were divided into seven study groups: 1 Undisturbed Areas 2 Disturbed Areas 3 Sedimentation Areas 4 Former Staging Area 5 Buried Debris 6 Potential Source Material 7 Soil Mounds Corrective action investigation (CAI) activities, as set forth in the CAU 413 Corrective Action Investigation Plan, were performed from June 2015 through May 2016. Radionuclides detected in samples collected during the CAI were used to estimate total effective dose using the Construction Worker exposure scenario. Corrective action was required for areas where total effective dose exceeded, or was assumed to exceed, the radiological final action level (FAL) of 25 millirem per year. The results of the CAI and the assumptions made in the data quality objectives resulted in the following conclusions: The FAL is exceeded in surface soil in SG1, Undisturbed Areas; The FAL is assumed to be exceeded in SG5, Buried Debris, where contaminated debris and soil were buried after the CSII test; The FAL is not exceeded at SG2, SG3, SG4, SG6, or SG7. Because the FAL is exceeded at CAU 413, corrective action is required and corrective action alternatives (CAAs) must be evaluated. For CAU 413, three CAAs were evaluated: no further action, clean closure, and

  3. Validation of the Tensoval Duo Control II blood pressure monitor for clinic use and self-measurement according to the British Hypertension Society protocol and the European Society of Hypertension International Protocol Revision 2010.

    Science.gov (United States)

    de Greeff, Annemarie; Shennan, Andrew H

    2013-06-01

    The Tensoval Duo Control II is an automated upper arm device that uses a combination of oscillometric and auscultatory technology to determine blood pressure noninvasively. The accuracy of this device was assessed according to the British Hypertension Society (BHS) protocol and the European Society of Hypertension International Protocol revision 2010 (ESH-IP2) in an adult population. Ethical approval was obtained. Eighty-five and 33 adult individuals, respectively, were recruited to fulfil the requirements of each protocol. Trained observers took nine sequential same-arm measurements alternating between a mercury sphygmomanometer and the device. The device had to achieve at least a B grade for both systolic and diastolic pressures to pass the BHS protocol and had to fulfil the criteria of all three phases of the ESH-IP2 protocol to receive recommendation. The device achieved an A/A grading for the BHS protocol and passed all three phases of the ESH-IP2 protocol. The mean difference±SD for the BHS/ESH protocols, respectively, was -1.8±6.5/-0.7±5.7 mmHg for systolic pressure and 1.9±5.1/2.4±4.5 mmHg for diastolic pressure. The device maintained its A/A grading throughout the low-pressure, medium-pressure and high-pressure ranges. The Tensoval Duo Control II device is recommended for clinical and home use according to both the BHS and the ESH-IP2 standard.

  4. DOE program guide for universities and other research groups. Part I. DOE Research and Development Programs; Part II. DOE Procurement and Assistance Policies/Procedures

    Energy Technology Data Exchange (ETDEWEB)

    1980-03-01

    This guide addresses the DOE responsibility for fostering advanced research and development of all energy resources, both current and potential. It is intended to provide, in a single publication, all the fundamental information needed by an institution to develop a potential working relationship with DOE. Part I describes DOE research and development programs and facilities, and identifies areas of additional research needs and potential areas for new research opportunities. It also summarizes budget data and identifies the DOE program information contacts for each program. Part II provides researchers and research administrators with an introduction to the DOE administrative policies and procedures for submission and evaluation of proposals and the administration of resulting grants, cooperative agreements, and research contracts. (RWR)

  5. Program Hybrid/GDH. Revision

    International Nuclear Information System (INIS)

    Blann, M.; Bisplinghoff, J.

    1975-10-01

    This code is the most recent in a series of codes for doing a-priori pre-equilibrium decay calculations. It has been written to permit the user to exercise many options at time of execution. It will, for example, permit calculation with either Hybrid model or the geometry dependent Hybrid model (GDH). Intranuclear transition rates can be calculated using either a nucleon-nucleon scattering approach (improved over earlier results) or based on the imaginary optical potential. Transition rates based on exciton lifetimes can be selected (as suggested in the Hybrid model formulation) or an average lifetime for each n-exciton configuration may be selected

  6. Renewable Fuel Pathways II Final Rule to Identify Additional Fuel Pathways under Renewable Fuel Standard Program

    Science.gov (United States)

    This final rule describes EPA’s evaluation of biofuels derived from biogas fuel pathways under the RFS program and other minor amendments related to survey requirements associated with ULSD program and misfueling mitigation regulations for E15.

  7. North Dakota Senior High Industrial Arts Program of Studies--Level II. Research Series No. 80.

    Science.gov (United States)

    North Dakota State Board for Vocational Education, Bismarck. Research Coordinating Unit.

    This industrial arts program of a studies guide is the product of a research project designed to (1) ascertain programs and curricula trends of senior high school industrial arts in the fifty states, (2) develop a philosophical rationale for senior high schools in North Dakota secondary schools, and (3) develop a master plan and program of study…

  8. Corrective Action Investigation Plan for Corrective Action Unit 413: Clean Slate II Plutonium Dispersion (TTR) Tonopah Test Range, Nevada, Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Matthews, Patrick; Burmeister, Mark; Gallo, Patricia

    2016-04-21

    Corrective Action Unit (CAU) 413 is located on the Tonopah Test Range, which is approximately 130 miles northwest of Las Vegas, Nevada, and approximately 40 miles southeast of Tonopah, Nevada. The CAU 413 site consists of the release of radionuclides to the surface and shallow subsurface from the conduct of the Clean Slate II (CSII) storage–transportation test conducted on May 31, 1963. CAU 413 includes one corrective action site (CAS), TA-23-02CS (Pu Contaminated Soil). The known releases at CAU 413 are the result of the atmospheric deposition of contamination from the 1963 CSII test. The CSII test was a non-nuclear detonation of a nuclear device located inside a reinforced concrete bunker covered with 2 feet of soil. This test dispersed radionuclides, primarily plutonium, on the ground surface. The presence and nature of contamination at CAU 413 will be evaluated based on information collected from a corrective action investigation (CAI). The investigation is based on the data quality objectives (DQOs) developed on June 17, 2015, by representatives of the Nevada Division of Environmental Protection; the U.S. Air Force; and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 413. The CAI will include radiological surveys, geophysical surveys, collection and analyses of soil samples, and assessment of investigation results. The collection of soil samples will be accomplished using both probabilistic and judgmental sampling approaches. To facilitate site investigation and the evaluation of DQO decisions, the releases at CAU 413 have been divided into seven study groups.

  9. CD4(+) type II NKT cells mediate ICOS and programmed death-1-dependent regulation of type 1 diabetes.

    Science.gov (United States)

    Kadri, Nadir; Korpos, Eva; Gupta, Shashank; Briet, Claire; Löfbom, Linda; Yagita, Hideo; Lehuen, Agnes; Boitard, Christian; Holmberg, Dan; Sorokin, Lydia; Cardell, Susanna L

    2012-04-01

    Type 1 diabetes (T1D) is a chronic autoimmune disease that results from T cell-mediated destruction of pancreatic β cells. CD1d-restricted NKT lymphocytes have the ability to regulate immunity, including autoimmunity. We previously demonstrated that CD1d-restricted type II NKT cells, which carry diverse TCRs, prevented T1D in the NOD mouse model for the human disease. In this study, we show that CD4(+) 24αβ type II NKT cells, but not CD4/CD8 double-negative NKT cells, were sufficient to downregulate diabetogenic CD4(+) BDC2.5 NOD T cells in adoptive transfer experiments. CD4(+) 24αβ NKT cells exhibited a memory phenotype including high ICOS expression, increased cytokine production, and limited display of NK cell markers, compared with double-negative 24αβ NKT cells. Blocking of ICOS or the programmed death-1/programmed death ligand 1 pathway was shown to abolish the regulation that occurred in the pancreas draining lymph nodes. To our knowledge, these results provide for the first time cellular and molecular information on how type II CD1d-restricted NKT cells regulate T1D.

  10. Full-Scale Mark II CRT program data report no. 10 (TEST 1203)

    International Nuclear Information System (INIS)

    Kukita, Yutaka; Takeshita, Isao; Yamamoto, Nobuo; Namatame, Ken; Shiba, Masayoshi

    1981-03-01

    Recorded data for TEST 1203 conducted on the Full-Scale Mark II CRT (Containment Response Test) Facility are presented. The test 1203 is the third test run of a series of steam discharge pool swell test. It is one of the tests where break diameter was varied parametrically, i.e., TEST 1201 (200 mm), TEST 1202 (240 mm) and TEST 1203 (220 mm). The test was successfully conducted. A drywell initial pressurization rate of 188 kPa/s was obtained, which is approximately equal to what is postulated for a hypothetical DBA (Design Basis Accident) LOCA in the BWR Mark II containment. (author)

  11. Electrodril system field test program. Phase II: Task C-1-deep drilling system demonstration. Final report for Phase II: Task C-1

    Energy Technology Data Exchange (ETDEWEB)

    Taylor, P D

    1981-04-01

    The Electrodril Deep Drilling System field test demonstrations were aborted in July 1979, due to connector problems. Subsequent post test analyses concluded that the field replacable connectors were the probable cause of the problems encountered. The designs for both the male and female connectors, together with their manufacturing processes, were subsequently modified, as was the acceptance test procedures. A total of nine male and nine female connectors were manufactured and delivered during the 2nd Quarter 1980. Exhaustive testing was then conducted on each connector as a precursor to formal qualification testing conducted during the month of October 1980, at the Brown Oil Tool test facility located in Houston, Texas. With this report, requirements under Phase II, Task C-1 are satisfied. The report documents the results of the connector qualification test program which was successfully completed October 28, 1980. In general, it was concluded that connector qualification had been achieved and plans are now in progress to resume the field test demonstration program so that Electrodril System performance predictions and economic viability can be evaluated.

  12. COXPRO-II: a computer program for calculating radiation and conduction heat transfer in irradiated fuel assemblies

    International Nuclear Information System (INIS)

    Rhodes, C.A.

    1984-12-01

    This report describes the computer program COXPRO-II, which was written for performing thermal analyses of irradiated fuel assemblies in a gaseous environment with no forced cooling. The heat transfer modes within the fuel pin bundle are radiation exchange among fuel pin surfaces and conduction by the stagnant gas. The array of parallel cylindrical fuel pins may be enclosed by a metal wrapper or shroud. Heat is dissipated from the outer surface of the fuel pin assembly by radiation and convection. Both equilateral triangle and square fuel pin arrays can be analyzed. Steady-state and unsteady-state conditions are included. Temperatures predicted by the COXPRO-II code have been validated by comparing them with experimental measurements. Temperature predictions compare favorably to temperature measurements in pressurized water reactor (PWR) and liquid-metal fast breeder reactor (LMFBR) simulated, electrically heated fuel assemblies. Also, temperature comparisons are made on an actual irradiated Fast-Flux Test Facility (FFTF) LMFBR fuel assembly

  13. Geothermal direct heat program: roundup technical conference proceedings. Volume II. Bibliography of publications. State-coupled geothermal resource assessment program

    Energy Technology Data Exchange (ETDEWEB)

    Ruscetta, C.A. (ed.)

    1982-07-01

    Lists of publications are presented for the Geothermal Resource Assessment Program for the Utah Earth Science Laboratory and the following states: Alaska, Arizona, California, Colorado, Hawaii, Idaho, Kansas, Montana, Nebraska, Nevada, New Mexico, New York, North Dakota, Oregon, Texas, Utah, and Washington.

  14. Programming Models for Three-Dimensional Hydrodynamics on the CM-5 (Part II)

    International Nuclear Information System (INIS)

    Amala, P.A.K.; Rodrigue, G.H.

    1994-01-01

    This is a two-part presentation of a timing study on the Thinking Machines CORP. CM-5 computer. Part II is given in this study and represents domain-decomposition and message-passing models. Part I described computational problems using a SIMD model and connection machine FORTRAN (CMF)

  15. Visions into Voices: Impact II Catalog of Teacher-Developed Programs 1992-1993.

    Science.gov (United States)

    New York City Board of Education, Brooklyn. Div. of Instruction and Professional Development.

    IMPACT II is a nationwide educational nonprofit organization that supports innovative teachers who exemplify professionalism, independence, and creativity within the public school systems. The model has been adopted in many areas, including New York (New York). This catalog contains profiles of 33 projects that represent innovative…

  16. Evaluation of Educational Programs for Young Children: The Minnesota Round Table on Early Childhood Education II.

    Science.gov (United States)

    Weinberg, Richard A., Ed.; Moore, Shirley G., Ed.

    This is a collection of papers based on presentations made by participants in the Minnesota Round Table II sponsored by the University of Minnesota and the Child Development Associate Consortium in 1974. Included are an introduction to the conference (Richard A. Weinberg and Shirley G. Moore) and the following articles: (1) Planning Evaluation…

  17. Subseabed Disposal Program Plan. Volume II. FY80 budget and subtask work plans

    International Nuclear Information System (INIS)

    1980-01-01

    This volume of the Subseabed Disposal Program Plan presents a breakdown of the master program structure by major activity. Each activity is described and accompanied by a specific cost plan schedule and a milestone plan. The costs have been compiled in the Cost Plan Schedules attached to each Subtask Work Plan. The FY 1980 budget for the Subseabed Disposal Program is summarized at the second level of the Work Breakdown Structure. The milestone plans for FY 80 are presented. The milestones can be changed only with the concurrence of the Sandia Subseabed Program Manager

  18. 25 CFR 276.14 - Budget revision.

    Science.gov (United States)

    2010-04-01

    ... changes include: (1) The use of grantee funds in furtherance of program objectives over and above the... the objective of the grant-supported program. (2) The revision indicates the need for additional... programs, functions, and activities when budgeted separately for a grant, except that the Bureau shall...

  19. The impact of written information and counseling (WOMAN-PRO II Program) on symptom outcomes in women with vulvar neoplasia: A multicenter randomized controlled phase II study.

    Science.gov (United States)

    Raphaelis, Silvia; Mayer, Hanna; Ott, Stefan; Mueller, Michael D; Steiner, Enikö; Joura, Elmar; Senn, Beate

    2017-07-01

    To determine whether written information and/or counseling based on the WOMAN-PRO II Program decreases symptom prevalence in women with vulvar neoplasia by a clinically relevant degree, and to explore the differences between the 2 interventions in symptom prevalence, symptom distress prevalence, and symptom experience. A multicenter randomized controlled parallel-group phase II trial with 2 interventions provided to patients after the initial diagnosis was performed in Austria and Switzerland. Women randomized to written information received a predefined set of leaflets concerning wound care and available healthcare services. Women allocated to counseling were additionally provided with 5 consultations by an Advanced Practice Nurse (APN) between the initial diagnosis and 6months post-surgery that focused on symptom management, utilization of healthcare services, and health-related decision-making. Symptom outcomes were simultaneously measured 5 times to the counseling time points. A total of 49 women with vulvar neoplasia participated in the study. Symptom prevalence decreased in women with counseling by a clinically relevant degree, but not in women with written information. Sporadically, significant differences between the 2 interventions could be observed in individual items, but not in the total scales or subscales of the symptom outcomes. The results indicate that counseling may reduce symptom prevalence in women with vulvar neoplasia by a clinically relevant extent. The observed group differences between the 2 interventions slightly favor counseling over written information. The results justify testing the benefit of counseling thoroughly in a comparative phase III trial. Copyright © 2017 Elsevier Inc. All rights reserved.

  20. Revising the Depreciation and Investment Credit Lessons for Farm Management and Supervised Occupational Experience for Use in Missouri Programs of Vocational Agriculture. Final Report.

    Science.gov (United States)

    Rohrbach, Norman; And Others

    This project developed four lessons that reflect the 1981 tax laws as they relate to the use of investment credit and depreciation in farm accounting systems. Project staff reviewed tax laws and related materials and identified four lessons in farm management and supervised occupational experience that needed revision. Materials were then…

  1. Mark II containment 1/6-scale pressure suppression test program: data report no. 2

    International Nuclear Information System (INIS)

    Kukita, Yutaka; Okazaki, Motoaki; Namatame, Ken; Shiba, Masayoshi

    1979-08-01

    This report documents experimental data from the first test phase of the Mark II Containment 1/6-Scale Pressure Suppression Test. The 1/6-Scale Test was initiated in December, 1976, to investigate the thermohydraulic responses of a BWR Mark II pressure suppression system to a postulated loss-of-coolant accident (LOCA), by means of scale model experiments. From January to June, 1977, a series of tests were performed for the Japanese BWR Owners' Group. These tests consisted of eight air-blowdown pool swell tests, three steam-blowdown pool swell tests, and twelve steam condensation tests. The dynamic responses of pressure and pool water level during the blowdown, pressure oscillation and chugging phenomena associated with unsteady condensation of steam were measured. (author)

  2. Visual examination program of the TRIGA Mark II reactor Vienna with the nuclear underwater telescope

    International Nuclear Information System (INIS)

    Boeck, H.; Hammer, J.; Varga, K.

    1985-12-01

    The visual inspection programm carried out during a three month shut-period at the TRIGA Mark II reactor Vienna is described. Optical inspection of all welds inside the reactor tank was carried out with an underwater telescope developed by the Central Research Institute of Physics, Budapest, Hungary. It is shown that even after 23 years of reactor operation all tank internals were found to be in good condition and minor defects can be easily repaired by remote handling tools. (Author)

  3. Full-Scale Mark II CRT program data report No. 11 (TEST 1204)

    International Nuclear Information System (INIS)

    Kukita, Yutaka; Takeshita, Isao; Yamamoto, Nobuo; Namatame, Ken; Shiba, Masayoshi

    1981-03-01

    Recorded data for TEST 1204 conducted on the Full-Scale Mark II CRT (Containment Response Test) Facility are presented. The TEST 1204 is the fourth test run of a series of steam discharge pool swell tests. The test conditions are similar to those of the TEST 1203 except for lower initial pool temperature. The test was successful and the maximum level of pool surface was fairly lower than in the TEST 1203 due to the lower pool temperature. (author)

  4. A program for the a priori evaluation of detection limits in instrumental neutron activation analysis using a SLOWPOKE II reactor

    International Nuclear Information System (INIS)

    Galinier, J.L.; Zikovsky, L.

    1982-01-01

    A program that permits the a priori calculation of detection limits in monoelemental matrices, adapted to instrumental neutron activation analysis using a SLOWPOKE II reactor, is described. A simplified model of the gamma spectra is proposed. Products of (n,p) and (n,α) reactions induced by the fast components of the neutron flux that accompanies the thermal flux at the level of internal irradiation sites in the reactor have been included in the list of interfering radionuclides. The program calculates in a systematic way the detection limits of 66 elements in an equal number of matrices using 153 intermediary radionuclides. Experimental checks carried out with silicon (for short lifetimes) and aluminum and magnesium (for intermediate lifetimes) show satisfactory agreement with the calculations. These results show in particular the importance of the contribution of the (n,p) and (n,α) reactions in the a priori evaluation of detection limits with a SLOWPOKE type reactor [fr

  5. The Implementation of Blended Learning Using Android-Based Tutorial Video in Computer Programming Course II

    Science.gov (United States)

    Huda, C.; Hudha, M. N.; Ain, N.; Nandiyanto, A. B. D.; Abdullah, A. G.; Widiaty, I.

    2018-01-01

    Computer programming course is theoretical. Sufficient practice is necessary to facilitate conceptual understanding and encouraging creativity in designing computer programs/animation. The development of tutorial video in an Android-based blended learning is needed for students’ guide. Using Android-based instructional material, students can independently learn anywhere and anytime. The tutorial video can facilitate students’ understanding about concepts, materials, and procedures of programming/animation making in detail. This study employed a Research and Development method adapting Thiagarajan’s 4D model. The developed Android-based instructional material and tutorial video were validated by experts in instructional media and experts in physics education. The expert validation results showed that the Android-based material was comprehensive and very feasible. The tutorial video was deemed feasible as it received average score of 92.9%. It was also revealed that students’ conceptual understanding, skills, and creativity in designing computer program/animation improved significantly.

  6. Diffusion of an effective tobacco prevention program. Part II: Evaluation of the adoption phase.

    Science.gov (United States)

    Parcel, G S; O'Hara-Tompkins, N M; Harrist, R B; Basen-Engquist, K M; McCormick, L K; Gottlieb, N H; Eriksen, M P

    1995-09-01

    This paper presents the results of theory-based intervention strategies to increase the adoption of a tobacco prevention program. The adoption intervention followed a series of dissemination intervention strategies targeted at 128 school districts in Texas. Informed by Social Cognitive Theory, the intervention provided opportunities for districts to learn about and model themselves after 'successful' school districts that had adopted the program, and to see the potential for social reinforcement through the knowledge that the program had the potential to have an important influence on students' lives. The proportion of districts in the Intervention condition that adopted the program was significantly greater than in the Comparison condition (P teacher attitudes toward the innovation and organizational considerations of administrators. Recommendations for the development of effective strategies for the diffusion of innovations are presented.

  7. Computer program for regional assessment of lung perfusion defect. Part II - verification of the algorithm

    International Nuclear Information System (INIS)

    Stefaniak, B.

    2002-01-01

    As described earlier, a dedicated computer program was developed for quantitative evaluation of regional lung perfusion defects, visualized by pulmonary scintigraphy. The correctness of the basic assumptions accepted to construct the algorithms and of the all program functions needed to be checked, before application of the program into the clinical routine. The aim of this study was to verified the program using various software instruments and physical models. Evaluation of the proposed method was performed using software procedures, physical lung phantom, and selected lung image.The reproducibility of lung regions, defined by the program was found excellent. No significant distortion of registered data was observed after ROI transformation into the circle and retransformation into the original shape. The obtained results comprised parametric presentation of activity defects as well as a set of numerical indices which defined extent and intensity of decreased counts density. Among these indices PD2 and DM* were proved the most suitable for the above purposes. The obtained results indicate that the algorithms used for the program construction were correct and suitable for the aim of the study. The above algorithms enable function under study to be presented graphically with true imaging of activity distribution, as well as numerical indices, defining extent and intensity of activity defects to calculated. (author)

  8. THE FEASIBILITY OF VILLAGE FOREST PROGRAM IN TANJUNG AUR II VILLAGE, PINO RAYA SUBDISTRICT, SOUTH BENGKULU REGENCY

    Directory of Open Access Journals (Sweden)

    Desmantoro

    2016-08-01

    Full Text Available A feasibility study toward the prerequisite conditions is required for the successful implementation of the Village Forest program in Tanjung Aur II Village. This study aims to: 1 identify bio-geophysical conditions of the work area; 2 analyze the conditions of sosioeconomic-cultural society/institutional; 3 analyze the support of stakeholders; and 4 formulate appropriate implementation strategies. The study was using survey method and qualitative studies with multiple analysis techniques. The results showed that: 1 the biogeophysical conditions was eligible and suitable to be proposed as village forest working area; 2 conditions of socio-economic-cultural communities enable to form village forest management institution, through collaboration between state forest encroachers and the villager representatives; 3 stakeholders were ready to provide support facilitation and assistance according to their capacity and capabilities. Key stakeholder were among others BPDAS Ketahun, Dishut Provinsi Bengkulu, Dishut ESDM Bengkulu Selatan, NGOs Ulayat, and officials of the Village; 4 the implementation strategy of village forest program that suitable for Tanjung Aur II was a competitive strategy or diversification (S-T strategy, with the main priority of the strategy, among others by seeking and asking for support from relevant stakeholders or other parties who had capacity and capability to undertake facilitation and assistance.

  9. Loosening After Acetabular Revision

    DEFF Research Database (Denmark)

    Beckmann, Nicholas A.; Weiss, Stefan; Klotz, Matthias C.M.

    2014-01-01

    The best method of revision acetabular arthroplasty remains unclear. Consequently, we reviewed the literature on the treatment of revision acetabular arthroplasty using revision rings (1541 cases; mean follow-up (FU) 5.7 years) and Trabecular Metal, or TM, implants (1959 cases; mean FU 3.7 years...

  10. Full-scale mark II CRT program data report, No. 9

    International Nuclear Information System (INIS)

    Takeshita, Isao; Yamamoto, Nobuo; Kukita, Yutaka; Namatame, Ken; Shiba, Masayoshi

    1980-07-01

    Recorded data for TEST 1202 conducted on the Full-Scale Mark II CRT (Containment Responce Test) Facility are presented. The TEST 1202 is a test under the condition of steam discharge with a large break diameter (240 mm) and the second one of the steam discharge pool swell test series. It is also one of the parametric tests with different break diameters, i.e. TEST 1201 (200 mm), TEST 1202 (240 mm) and TEST 1203 (220 mm). The test was successful and a value of 225 kPa/s was obtained as the initial pressurization rate in the drywell. (author)

  11. Full-Scale Mark II CRT program data report no. 12 (TEST 1205)

    International Nuclear Information System (INIS)

    Takeshita, Isao; Kukita, Yutaka; Yamamoto, Nubuo; Namatame, Ken; Shiba, Masayoshi

    1981-03-01

    Recorded data for TEST 1205 conducted on the Full-Scale Mark II CRT (Containment Response Test) Facility are presented. The TEST 1205 is the fifth test run of a series of steam discharge pool swell tests. The test conditions are similar to those of the TEST 1203 except that the vacuum breaker was locked close. The test was successful and the comparison of the TEST 1205 and the TEST 1203 results shows that the vacuum breaker may have some effects to reduce the wetwell airspace pressurization, and thus to reduce the upward force to diaphram floor during a pool swell. (author)

  12. The revision of the master's curiculm at Osaka Kyoiku University

    OpenAIRE

    赤松, 喜久; 伊藤, 敏雄

    2007-01-01

    The background covering the revision of the master's curriculum and a point concerning this revision in a teacher-training program at Osaka Kyoiku University are explained in this paper. Furthermore, future problems are organized and evaluated. The paper will help us to consider the revision of the curriculum expected as part of the master's course in a teacher's program. The number of required subjects is minimal so that a student may take more optional subjects to meet various needs. New su...

  13. Microcomputer based program for predicting heat transfer under reactor accident conditions. Volume II

    International Nuclear Information System (INIS)

    Cheng, S.C.; Groeneveld, D.C.; Leung, L.K.H.; Wong, Y.L.; Nguyen, C.

    1987-07-01

    A microcomputer based program called Heat Transfer Prediction Software (HTPS) has been developed. It calculates the heat transfer for tube and bundle geometries for steady state and transient conditions. This program is capable of providing the best estimated of the hot pin temperatures during slow transients for 37- and 28-element CANDU type fuel bundles. The program is designed for an IBM-PC AT/XT (or IBM-PC compatible computer) equipped with a Math Co-processor. The following input parameters are required: pressure, mass flux, hydraulic diameter, and quality. For the steady state case, the critical heat flux (CHF), the critical heat flux temperature, the minimum film boiling temperature, and the minimum film boiling heat flux are the primary outputs. With either the surface heat flux or wall temperature specified, the program determines the heat transfer regime and calculates the surface heat flux, wall temperature and heat transfer coefficient. For the slow transient case, the pressure, mass flux, quality, and volumetric heat generation rate are the time dependent input parameters are required to calculate the hot pin sheath temperatures and surface heat fluxes. A simple routine for generating properties has been developed for light water to support the above program. It contains correlations that have been verified for pressures ranging from 0.6kPa to 30 MPa, and temperatures up to 1100 degrees Celcius. The thermodynamic and transport properties that can be generated from this routine are: density, specific volume, enthalpy, specific heat capacity, conductivity, viscosity, surface tension and Prandtle number for saturated liquid, saturated vapour, subcooled liquid of superheated vapour. A software for predicting flow regime has also been developed. It determines the flow pattern at specific flow conditions, and provides a correction factor for calculating the CHF during partially stratified horizontal flow. The technical bases for the program and its structure

  14. Health risk reduction programs in employer-sponsored health plans: Part II-law and ethics.

    Science.gov (United States)

    Rothstein, Mark A; Harrell, Heather L

    2009-08-01

    We sought to examine the legal and ethical implications of workplace health risk reduction programs (HRRPs) using health risk assessments, individually focused risk reduction, and financial incentives to promote compliance. We conducted a literature review, analyzed relevant statutes and regulations, and considered the effects of these programs on employee health privacy. A variety of laws regulate HRRPs, and there is little evidence that employer-sponsored HRRPs violate these provisions; infringement on individual health privacy is more difficult to assess. Although current laws permit a wide range of employer health promotion activities, HRRPs also may entail largely unquantifiable costs to employee privacy and related interests.

  15. The Argonne Radiological Impact Program (ARIP). Part II. MONITOR: A Program and Data Base for Retrieval and Utilization of Pollutant Monitoring Data

    Energy Technology Data Exchange (ETDEWEB)

    Eckerman, Keith F.; Stowe, Ralph F.; Frigerio, Norman A.

    1977-02-01

    The Argonne Radiological Impact Program (ARIP) is an ongoing project of the Laboratory's Division of Environmental Impact Studies that aims at developing methodologies for assessing the carcinogenic hazards associated with nuclear power development. The project's first report (ANL/ES-26, Part I), published in September.l973, discussed models of radiation carcinogenesis and the contribution of U .. S. background radiation levels to hazardous dose rates. The current report (Part II) treats the storage and access of available data on radiation and radioactivity levels in the u. S. A compute-r code. (the MONITOR program) is prf!sented, which can serve as a ready-access data. bank for all monitoring data acquired over the past two decades. The MONITOR program currently stores data on monitoring locations, types of monitoring efforts, and types of monitoring data. reported in Radiation Data and Reports by the various state and federal ne-tworks; expansion of this data base to include nuclear power facilities in operation or on order is ongoing ·. The MONITOR code retrieves information within a search radius, or rectangl.e ,. circumscribed by parameters of latitude and longitude, and l:.ists or maps the data_as: requested. The code, with examples, is given in full in the report ..

  16. Optimization of temperature-programmed GC separations. II. Off-line simplex optimization and column selection

    NARCIS (Netherlands)

    Snijders, H.M.J.; Janssen, J.G.M.; Cramers, C.A.M.G.; Sandra, P; Bertsch, W.; Sandra, P.; Devos, G.

    1996-01-01

    In this work a method is described which allows off-line optimization of temperature programmed GC separations. Recently, we described a new numerical method to predict off-line retention times and peak widths of a mixture containing components with known identities in capillary GC. In the present

  17. National Waste Terminal Storage Program: configuration management plan. Volume II. Plan description

    International Nuclear Information System (INIS)

    1977-05-01

    Purpose of the Configuration Management Plan is to provide the management discipline through which the integrity and continuity of program cost and schedule trade-off decisions which are made concerning the site selections and facilities performance, producibility, operability and supportability are recorded, communicated, and controlled by the Office of Waste Isolation

  18. National Waste Terminal Storage Program: planning and control plan. Volume II. Plan description

    International Nuclear Information System (INIS)

    1977-05-01

    Objective of the NWTS program planning and control plan is to provide the information necessary for timely and effective OWI management decisions. Purpose is to describe the concepts and techniques that will be utilized by OWI to establish structured, completely planned and controlled technical, cost, and schedule NWTS baselines from which performance or progress can be accurately measured

  19. Core II Materials for Rural Agriculture Programs. Units E-H.

    Science.gov (United States)

    Biondo, Ron; And Others

    This curriculum guide includes teaching packets for 21 problem areas to be included in a core curriculum for 10th grade students enrolled in a rural agricultural program. Covered in the four units included in this volume are crop science (harvesting farm crops and growing small grains); soil science and conservation of natural resources…

  20. Water Treatment Plant Operation. Volume II. A Field Study Training Program.

    Science.gov (United States)

    California State Univ., Sacramento. School of Engineering.

    The purpose of this water treatment field study training program is to: (1) develop new qualified water treatment plant operators; (2) expand the abilities of existing operators, permitting better service both to employers and public; and (3) prepare operators for civil service and certification examinations (examinations administered by…

  1. Seabed Disposal Program. Annual report, January--December 1976. Part II

    International Nuclear Information System (INIS)

    Talbert, D.M.

    1977-08-01

    During the first two years of the program, studies were made of the water column extending from the seabed to the surface in mid-gyre regions. It was concluded that this water column is unsuitable for consideration as the disposal medium. Studies were shifted to characterization of the mid-plate, mid-gyre sediments, natural processes in the sediments, and how these natural processes are altered or impacted by the presence of high-level radioactive wastes. These activities continued in the third year of the Program and include (1) development of a number of analytical models as part of the overall systems analysis effort; (2) an extensive program to evaluate the sorption properties of the sediments with respect to single species ions and the competition provided by other waste constituents; (3) an assessment of thermal problems associated with the radiogenic heat produced by the waste and its impact upon the physical and chemical properties of the sediments; (4) continued studies to characterize the sediments; (5) development of capabilities to investigate waste canister emplacement techniques; (6) corrosion studies to evaluate potential canister materials; (7) biological investigations in support of assessment studies addressing accident scenarios and environmental impact; and (8) development of an international program of scientific investigations and information exchange. At the end of the third year, available data indicate that studies should be continued on the concept of disposal in the seabed

  2. Defense Small Business Innovation Research Program (SBIR). Abstracts of Phase II Awards. 1985.

    Science.gov (United States)

    1985-01-01

    OFFICE: AFBMOiPMX THE INTEGR ATE-DRILL-LOADLSHUOT (IDLS) C’ NCv " , A CONTINUOUS DRILL 04 ’e SMALL BUSINESS INNOVATION RESEARCH (SBIR) PROGRAM - PHASE 2...WORK WAS TO DEMONSTRATE THAT THE COMPONENTS OF THE -.’ WBGI INDEX ( WEB BULB, DRY BULB AND BLACK GLOBE TEMPERATURE) CAN BE DE- RIVED FROM SATELLITE DATA

  3. A mentor-protégé program for new faculty, Part II: Stories of mentors.

    Science.gov (United States)

    Wilson, Carol B; Brannan, Jane; White, Anne

    2010-12-01

    Mentorship has been identified as an influential factor in retaining new nursing faculty. A mentor-protégé program for novice faculty was implemented to promote development of the protégés in their role as nurse educators. A qualitative research study conducted to illuminate the meaning of experiences of mentors led to the emergence of four patterns: The Significance of the Mentor-Protégé Relationship, Communication as Important Between Mentor and Protégé, The Mentor-Protégé Program-Protégé's Perspectives, and The Mentoring Role as Expert Educator. The data from the study support the significance of providing mentorship to novice or new nurse educators. The data suggest that mentors benefit from participation in a mentor-protégé program as much as the protégés. Similar programs are needed in nursing if we are to mentor and encourage faculty to begin and remain in the role of educators to combat the future nurse educator shortage. Copyright 2010, SLACK Incorporated.

  4. National Waste Terminal Storage Program: critical element management concept. Volume II. Concept description

    International Nuclear Information System (INIS)

    1977-05-01

    The objective of the CEM Concept is to describe techniques for systematically identifying, evaluating, and influencing those technical, social, economic, political and institutional factors (i.e., events, trends and conditions) that are perceived as being probable uncertainties to the attainment of planned program objectives

  5. Progress on the degraded piping program - Phase II. Battelle Columbus Division

    International Nuclear Information System (INIS)

    Wilkowski, Gery; Ahmad, J.; Barnes, C.; Brust, F.; Guerrieri, D.; Kramer, G.; Landow, M.; Marschall, C.; Nakagaki, M.; Papaspyropoulos; Scott, P.

    1988-01-01

    The overall objective of the Degraded Piping Program is to verify and improve simple estimation schemes to predict the fracture behavior of circumferentially cracked pipe. The program is limited to quasi-static fracture and cracks in straight pipe. There are a variety of materials, flaw geometries, pipe sizes, and loading conditions evaluated. The Degraded Piping Program,which has been extended for one more year, will supply results that provide a basis for regulatory decisions regard applications for leak-before-break (LBB) and In-service flaw assessment. The significance of our results are summarized relative to how they may affect regulatory technical needs. The scope of the work in The Degraded Piping Program includes both analytical and experimental efforts. The experimental efforts have concentrated on testing circumferentially cracked pipe at 550 F (288 C) under si-static loading. Many of the tasks within this program were undertaken with the objective of determining if any detailed efforts were needed. This is true for both the analytical and experimental efforts. i e of the tasks have been slightly expanded during the course of the gram, while others were found to be of lesser concern and further efforts in those areas were not pursued. The results of this summary include the efforts of the third year. These efforts have contributed considerably to the understanding of the application of elastic-plastic fracture mechanics to nuclear piping systems. Rather than listing the significant technical contributions, these contributions are summarized below in relation to their application to LBB analyses, in-service flaw assessment criteria, and (3) material characterization and unusual behavior of nuclear piping materials at light water reactor (LWR) temperatures

  6. Production Systems as a Programming Language for Artificial Intelligence Applications. Volume II.

    Science.gov (United States)

    1976-12-01

    CUETR1PLE(’ PiM -1,CI,’XX,’XX); This means: "if letter-I is R, then emit cue P and image DUNNO." Note that the LHS test is in two parts, testing the...Il) (IZ 110(31116 (rpEto PI-il (IMM POP$ (CIETPIRLE Mi-i NX XX XXI rvzt ! ni. ti-s ’SriII Otte ISs. ri-S ’S11f FIPE’ USING1 (SlIMEtl LI-I Li-I LI-I...MAi0OfWSENOAVl. *0 l’G(PM) I TACE IN=u P20 06 Otte ’ aMATOWLSVXMOOIOPP) Grp IATONSIM~vgvINV lm.IWMWO) InSAWEQWOI10l a MNT( fI )1s(D7yVSVI) MAIO41S1Ittly 113.111~f

  7. Multicenter phase II study of an opioid-based pain control program for head and neck cancer patients receiving chemoradiotherapy

    International Nuclear Information System (INIS)

    Zenda, Sadamoto; Matsuura, Kazuto; Tachibana, Hiroyuki; Homma, Akihiro; Kirita, Tadaaki; Monden, Nobuya; Iwae, Shigemichi; Ota, Yojiro; Akimoto, Tetsuo; Otsuru, Hiroshi; Tahara, Makoto; Kato, Kengo; Asai, Masao

    2011-01-01

    Background: The aim of this multi-center phase II study was to clarify the clinical benefit of an opioid-based pain control program for head and neck cancer patients during chemoradiotherapy. Patients and methods: Head and neck cancer patients who were to receive definitive or postoperative chemoradiotherapy were enrolled. The opioid-based pain control program consisted of a three-step ladder, with basic regimens of: Step 1: acetaminophen at 500–1000 mg three times a day. Step 2: fast-acting morphine at 5 mg three times a day before meals for a single day. Step 3: long-acting morphine administered around-the-clock, with a starting dosage of 20 mg/day and no upper limit set in principle. The primary endpoint of this study was compliance with radiotherapy. Results: A total of 101 patients from 10 institutions were registered between February 2008 and May 2009 and included in the analysis. The major combination chemotherapy regimen was cisplatin alone (76%). The rate of completion of radiotherapy was 99% and the rate of unplanned breaks in radiotherapy was 13% (13/101, 90% confidence interval: 9.9–16.5%). Median maximum quantity of morphine used per day was 35 mg (range 0–150 mg). Conclusions: Use of a systematic pain control program may improve compliance with CRT.

  8. Refining and end use study of coal liquids II - linear programming analysis

    Energy Technology Data Exchange (ETDEWEB)

    Lowe, C.; Tam, S.

    1995-12-31

    A DOE-funded study is underway to determine the optimum refinery processing schemes for producing transportation fuels that will meet CAAA regulations from direct and indirect coal liquids. The study consists of three major parts: pilot plant testing of critical upgrading processes, linear programming analysis of different processing schemes, and engine emission testing of final products. Currently, fractions of a direct coal liquid produced form bituminous coal are being tested in sequence of pilot plant upgrading processes. This work is discussed in a separate paper. The linear programming model, which is the subject of this paper, has been completed for the petroleum refinery and is being modified to handle coal liquids based on the pilot plant test results. Preliminary coal liquid evaluation studies indicate that, if a refinery expansion scenario is adopted, then the marginal value of the coal liquid (over the base petroleum crude) is $3-4/bbl.

  9. Test program element II blanket and shield thermal-hydraulic and thermomechanical testing, experimental facility survey

    International Nuclear Information System (INIS)

    Ware, A.G.; Longhurst, G.R.

    1981-12-01

    This report presents results of a survey conducted by EG and G Idaho to determine facilities available to conduct thermal-hydraulic and thermomechanical testing for the Department of Energy Office of Fusion Energy First Wall/Blanket/Shield Engineering Test Program. In response to EG and G queries, twelve organizations (in addition to EG and G and General Atomic) expressed interest in providing experimental facilities. A variety of methods of supplying heat is available

  10. MIDAS phase II. A program for the modal analysis of structures

    International Nuclear Information System (INIS)

    Durrans, R.F.

    1980-10-01

    The application of Modal Analysis to the experimental characterisation of structures is described. A program MIDAS (Modal Identification for the Dynamic Analysis of Structures) has been developed at B.N.L. to perform this function and this report presents a full description of its use. The structures within the coolant circuits of nuclear reactors must be designed to withstand large flow and acoustic forces. (U.K.)

  11. Test program element II blanket and shield thermal-hydraulic and thermomechanical testing, experimental facility survey

    Energy Technology Data Exchange (ETDEWEB)

    Ware, A.G.; Longhurst, G.R.

    1981-12-01

    This report presents results of a survey conducted by EG and G Idaho to determine facilities available to conduct thermal-hydraulic and thermomechanical testing for the Department of Energy Office of Fusion Energy First Wall/Blanket/Shield Engineering Test Program. In response to EG and G queries, twelve organizations (in addition to EG and G and General Atomic) expressed interest in providing experimental facilities. A variety of methods of supplying heat is available.

  12. The Oral History Program: II. Personal views of health sciences librarianship and the Medical Library Association.

    Science.gov (United States)

    McKenzie, D; Pifalo, V

    1998-07-01

    The Medical Library Association Oral History Program uses accepted oral history techniques to collect and preserve interviews with members. The original taped interviews and transcripts are kept in the Medical Library Association archives and made available for research purposes; edited copies of the interviews are distributed through the National Network of Libraries of Medicine, and members are encouraged to borrow and read the histories. Summaries of forty-three interviews provide personal views on health sciences librarianship and the Medical Library Association.

  13. Enforcement/certification program for appliance efficiency standards. Task II, report

    Energy Technology Data Exchange (ETDEWEB)

    1979-09-28

    The research and analysis program at Vitro Labs. in support of the appliance certification and enforcement program provides Vitro's recommended approach to appliance certification and enforcement (C/E). The approach established the C/E program framework, general criteria, and procedures for assuring a specified level of energy-efficiency performance for 13 categories of consumer products (furnaces, humidifiers, dehumidifiers, dishwashers, television, clothes washers, freezers, air conditioners, stoves, refrigerators, water heaters). Section 2 summarizes the recommended approach. Section 3 contains detailed evaluations and comparisons for four independent alternative approaches considered (minimal government intevention, strong certification control, strong enforcement audit, and mixed certification/enforcement). The fifth C/E approach (strong remedy/deterrent) involves the remedies available to the government should non-compliance be discovered and could affect the choice among the approaches, but this approach has not been evaluated. Section 4 summarizes the analysis methodology used to select the recommended approach. Additional information is provided in 6 appendices.

  14. Analytical Services Fiscal Year 1996 Multi-year Program Plan Fiscal Year Work Plan WBS 1.5.1, Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    This document contains the Fiscal Year 1996 Work Plan and Multi-Year Program Plan for the Analytical Services Program at the Hanford Reservation in Richland, Washington. The Analytical Services Program provides vital support to the Hanford Site mission and provides technically sound, defensible, cost effective, high quality analytical chemistry data for the site programs. This report describes the goals and strategies for continuance of the Analytical Services Program through fiscal year 1996 and beyond.

  15. Analytical Services Fiscal Year 1996 Multi-year Program Plan Fiscal Year Work Plan WBS 1.5.1, Revision 1

    International Nuclear Information System (INIS)

    1995-09-01

    This document contains the Fiscal Year 1996 Work Plan and Multi-Year Program Plan for the Analytical Services Program at the Hanford Reservation in Richland, Washington. The Analytical Services Program provides vital support to the Hanford Site mission and provides technically sound, defensible, cost effective, high quality analytical chemistry data for the site programs. This report describes the goals and strategies for continuance of the Analytical Services Program through fiscal year 1996 and beyond

  16. Migrant Education Administrative Handbook. Revised April 1973.

    Science.gov (United States)

    North Carolina State Dept. of Public Instruction, Raleigh. Div. of Compensatory Education.

    The revised handbook provides specific references to the legislation and the National Migrant Program Guidelines, while setting forth the administrative procedures required for migrant projects in North Carolina. Specific topics of discussion in migrant program administration cover Public Law 89-750, state and local educational agency…

  17. Computer Program for Calculation of Complex Chemical Equilibrium Compositions and Applications II. Users Manual and Program Description. 2; Users Manual and Program Description

    Science.gov (United States)

    McBride, Bonnie J.; Gordon, Sanford

    1996-01-01

    This users manual is the second part of a two-part report describing the NASA Lewis CEA (Chemical Equilibrium with Applications) program. The program obtains chemical equilibrium compositions of complex mixtures with applications to several types of problems. The topics presented in this manual are: (1) details for preparing input data sets; (2) a description of output tables for various types of problems; (3) the overall modular organization of the program with information on how to make modifications; (4) a description of the function of each subroutine; (5) error messages and their significance; and (6) a number of examples that illustrate various types of problems handled by CEA and that cover many of the options available in both input and output. Seven appendixes give information on the thermodynamic and thermal transport data used in CEA; some information on common variables used in or generated by the equilibrium module; and output tables for 14 example problems. The CEA program was written in ANSI standard FORTRAN 77. CEA should work on any system with sufficient storage. There are about 6300 lines in the source code, which uses about 225 kilobytes of memory. The compiled program takes about 975 kilobytes.

  18. Area 3, SRC-II coal slurry preheater studies report for the technical data analysis program

    Energy Technology Data Exchange (ETDEWEB)

    1984-08-01

    This report reviews the raw data gathered from the Preheater B test runs at Ft. Lewis, and also the Preheater B results presented in the Solvent Refined Coal (SRC) Process Final Report, Volumes 1 and 2 of Slurry Preheater Design, SRC-II Process and the Ft. Lewis Slurry Preheater Data Analysis, 1 1/2 Inch Coil by Gulf Science and Technology Corporation of Pittsburgh, Pennsylvania. attempts were made to correlate several variables not previously considered with slurry viscosity and thermal conductivity. Only partial success was realized. However, in the process of attempting to correlate these variables an understanding of why some variables could not be correlated was achieved. An attempt was also made, using multiple linear regression, to correlate coal slurry viscosity and thermal conductivity with several independent variables among which were temperature, coal concentration, total solids, coal type, slurry residence time, shear rate, and unit size. The final correlations included some, but not all, of these independent variables. This report is not a stand alone document and should be considered a supplement to work already done. It should be read in conjunction with the reports referenced above.

  19. Lake Erie Water Level Study. Appendix A. Regulation. Volume II. Coordinated Basic Data and Computer Programs.

    Science.gov (United States)

    1981-07-01

    F- fta fm~p- ri- a V.- On ;a~V~ I’ .C1A 1" ~ P 0%AJfVtN Q I1’t I O a0 4 . 0 * a C C COO a * a ma. 93 *a Ob fu -E tvvP- fl NurvI M I-Al N Ir-N fuII...NU N4 -4ftfNA fmd .-. - -9 0 0 0r IL 0 w wow 00~ 0Nm(U a 0P.-CM@W aO 0 1.4- 41- &0 M Im -4 & - 40 0 P-0 om fc I- 20o w wwef -4 . aaW4 MMM a-MI- n0 4...O zq~ f-’ W 9 A o a i. po j -4 N NfUfJ .-. AD uw s )LA~L; 4DW L NANI f & ftA DNN W LL) mij 3 z I- -9 9 a -j -z~u nV1 0 ~ OPP~~.N fj- , MD0* n’DCL t cc

  20. PREREM: an interactive data preprocessing code for INREM II. Part I: user's manual. Part II: code structure

    Energy Technology Data Exchange (ETDEWEB)

    Ryan, M.T.; Fields, D.E.

    1981-05-01

    PREREM is an interactive computer code developed as a data preprocessor for the INREM-II (Killough, Dunning, and Pleasant, 1978a) internal dose program. PREREM is intended to provide easy access to current and self-consistent nuclear decay and radionuclide-specific metabolic data sets. Provision is made for revision of metabolic data, and the code is intended for both production and research applications. Documentation for the code is in two parts. Part I is a user's manual which emphasizes interpretation of program prompts and choice of user input. Part II stresses internal structure and flow of program control and is intended to assist the researcher who wishes to revise or modify the code or add to its capabilities. PREREM is written for execution on a Digital Equipment Corporation PDP-10 System and much of the code will require revision before it can be run on other machines. The source program length is 950 lines (116 blocks) and computer core required for execution is 212 K bytes. The user must also have sufficient file space for metabolic and S-factor data sets. Further, 64 100 K byte blocks of computer storage space are required for the nuclear decay data file. Computer storage space must also be available for any output files produced during the PREREM execution. 9 refs., 8 tabs.

  1. Subseabed disposal program annual report, January-December 1978. Volume II. Principal investigator progress reports

    International Nuclear Information System (INIS)

    1979-10-01

    The topics covered in this report include: geologic siting considerations for the disposal of radioactive wastes into submarine geologic formations; geologic assessment of the MPG-1 regions Central North Pacific; site mapping; geotechnical aspects of subsurface seabed disposal; heat transfer, thermal and fluid physics in the deep ocean sediments; mechanical response predictive capability; sediment-seawater interaction at 300 0 C, 500 bars; stability of actinides in chloride media; cannister corrosion studies; nuclide sorption and migration; development of apparatus and measurement of thermal conductivity of seabed illite and smectite at temperatures to 500 0 C at simulated depths to 15,000 ft (9000 psi); in-situ heat transfer experiments; preliminary seabed disposal transport modeling studies; radionuclide migration studies; radionuclide distributions in deep ocean cores; benthic biological studies; deep sea microbial studies; activity rates of abyssal communities; Deep-towed RUM III (Sandia Seabed working platform): a third-generation remote underwater manipulator; long coring facility program; transportation; legal, political, and institutional implications of the Seabed Program for radioactive waste disposal

  2. SIMMER-II: A computer program for LMFBR disrupted core analysis

    Energy Technology Data Exchange (ETDEWEB)

    Bohl, W.R.; Luck, L.B.

    1990-06-01

    SIMMER-2 (Version 12) is a computer program to predict the coupled neutronic and fluid-dynamics behavior of liquid-metal fast reactors during core-disruptive accident transients. The modeling philosophy is based on the use of general, but approximate, physics to represent interactions of accident phenomena and regimes rather than a detailed representation of specialized situations. Reactor neutronic behavior is predicted by solving space (r,z), energy, and time-dependent neutron conservation equations (discrete ordinates transport or diffusion). The neutronics and the fluid dynamics are coupled via temperature- and background-dependent cross sections and the reactor power distribution. The fluid-dynamics calculation solves multicomponent, multiphase, multifield equations for mass, momentum, and energy conservation in (r,z) or (x,y) geometry. A structure field with nine density and five energy components; a liquid field with eight density and six energy components; and a vapor field with six density and on energy component are coupled by exchange functions representing a modified-dispersed flow regime with a zero-dimensional intra-cell structure model.

  3. National Waste Terminal Storage Program: information management plan. Volume II. Plan description

    International Nuclear Information System (INIS)

    1977-05-01

    A comprehensive information management plan to provide for the systematic processing of large amounts of internally prepared and externally acquired documentation that will accrue to the Office of Waste Isolation (OWI) during the next decade is outlined. The Information Management Plan of the National Waste Terminal Storage (NWTS) Program is based on time proven procedures developed by government and industry for the requirements determination, acquisition, and the administration of documentation. The NWTS Information Management Plan is designed to establish the basis for the planning, development, implemenation, operation and maintenance of the NWTS Information Management System. This plan will help assure that documentation meets required quality standards and that each organization's needs are reflected when soliciting documentation from subcontractors. An example would be the Quality Assurance documentation requirement necessary to comply with eventual NRC licensing regulations. The provisions of the NWTS Information Management Plan will apply to all documentation from OWI contractors, subcontractors, and suppliers, and to OWI organizations for documentation prepared periodically for external dissemination

  4. The properties of chromium electrodeposited with programmed currents. Part II. Reversing current

    Directory of Open Access Journals (Sweden)

    TANJA M. KOSTIC

    2000-01-01

    Full Text Available The electrodeposition of chromium in programmed reversing current (RC, was investigated in the regime of high cathodic current density (77 A dm-2 and anodic current density (55 A dm-2. The ratio of the cathodic and anodic time (60 : 1 was used. Chromium was deposed on a steel substrate from a chromic-sulphuric acid solution, during one hour. Anode and cathode were suited in a system of parallel plates. Basic properties of deposits, like thickness, morphology, microhardness, brightness were examined. Surface distribution of the deposits was obtained from the measurements of the thicknesses of the deposits (between 32 and 67 µm. A ferromagnetic non-destructive method was used in the measurements. Based on the results, graphic models of deposit surface distribution were made. Two ranges of the thickness could be seen on the model (range 1 - average thickness 35.1 µm and range 2 - average thickness 57.81 µm. These results were statisticaly analysed by colums, rows and by the whole surface. For the whole specimens, the average thickness was 45.39 µm with a coefficient of variation of 0.2582. The basic properties of the deposits did not change with a variation of the thickness. Because of this, the coatings deposited with the reversing current could be much more considered reliable in wear and corrosion protection systems than ones deposited by direct current.

  5. SIMMER-II: A computer program for LMFBR disrupted core analysis

    International Nuclear Information System (INIS)

    Bohl, W.R.; Luck, L.B.

    1990-06-01

    SIMMER-2 (Version 12) is a computer program to predict the coupled neutronic and fluid-dynamics behavior of liquid-metal fast reactors during core-disruptive accident transients. The modeling philosophy is based on the use of general, but approximate, physics to represent interactions of accident phenomena and regimes rather than a detailed representation of specialized situations. Reactor neutronic behavior is predicted by solving space (r,z), energy, and time-dependent neutron conservation equations (discrete ordinates transport or diffusion). The neutronics and the fluid dynamics are coupled via temperature- and background-dependent cross sections and the reactor power distribution. The fluid-dynamics calculation solves multicomponent, multiphase, multifield equations for mass, momentum, and energy conservation in (r,z) or (x,y) geometry. A structure field with nine density and five energy components; a liquid field with eight density and six energy components; and a vapor field with six density and on energy component are coupled by exchange functions representing a modified-dispersed flow regime with a zero-dimensional intra-cell structure model

  6. Automatic Program Development

    DEFF Research Database (Denmark)

    Automatic Program Development is a tribute to Robert Paige (1947-1999), our accomplished and respected colleague, and moreover our good friend, whose untimely passing was a loss to our academic and research community. We have collected the revised, updated versions of the papers published in his...... honor in the Higher-Order and Symbolic Computation Journal in the years 2003 and 2005. Among them there are two papers by Bob: (i) a retrospective view of his research lines, and (ii) a proposal for future studies in the area of the automatic program derivation. The book also includes some papers...... by members of the IFIP Working Group 2.1 of which Bob was an active member. All papers are related to some of the research interests of Bob and, in particular, to the transformational development of programs and their algorithmic derivation from formal specifications. Automatic Program Development offers...

  7. Aqueous Transport Code Revisions Using Geographic Information Systems

    International Nuclear Information System (INIS)

    Chen, K.F.

    2003-01-01

    STREAM II, developed at the Savannah River Site (SRS) for execution on a personal computer, is an emergency response code that predicts downstream pollutant concentrations for releases from the SRS area to the Savannah River for emergency response management decision making. The STREAM II code consists of pre-processor, calculation, and post-processor modules. The pre-processor module provides a graphical user interface (GUI) for inputting the initial release data. The GUI passes the user specified data to the calculation module that calculates the pollutant concentrations at downstream locations and the transport times. The calculation module of the STREAM II adopts the transport module of the WASP5 code. WASP5 is a US Environmental Protection Agency water quality analysis program that simulates pollutant transport and fate through surface water using a finite difference method to solve the transport equation. The calculated downstream pollutant concentrations and travel times a re passed to the post-processor for display on the computer screen in graphical and tabular forms. To minimize the user's effort in the emergency situation, the required input parameters are limited to the time and date of release, type of release, location of release, amount and duration of release, and the calculation units. The user, however, could only select one of the seventeen predetermined locations. Hence, STREAM II could not be used for situations in which release locations differ from the seventeen predetermined locations. To eliminate this limitation, STREAM II has been revised to allow users to select the release location anywhere along the specified SRS main streams or the Savannah River by mouse-selection from a map displayed on the computer monitor. The required modifications to STREAM II using geographic information systems (GIS) software is discussed in this paper

  8. RCRA and operational monitoring (ROM): Multi-year program plan and fiscal year 96 work plan. WBS 1.5.3, Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    The RCRA & Operational Monitoring (ROM) Program Office manages the Hanford Site direct funded Resource Conservation and Recovery Act (RCRA) and Operational Monitoring under Work Breakdown Structure (WBS) 1.01.05.03. The ROM Program Office is included in Hanford Technical Services, a part of Projects & Site Services of Westinghouse Hanford Company (WHC). The 1996 Multi-Year Program Plan (MYPP) includes the Fiscal Year Work Plan (FYWP). The Multi-Year Program Plan takes its direction from the Westinghouse Planning Baseline Integration Organization. The MYPP provides both the near term, enhanced details and the long term, projected details for the Program Office to use as baseline Cost, Scope and Schedule. Change Control administered during the fiscal year is against the baseline provided by near term details of this document. The MYPP process has been developed by WHC to meet its internal planning and integration needs and complies with the requirements of the US Department of Energy, Richland Operations Office (RL) Long Range Planning Process Directive (RLID 5000.2). Westinghouse Hanford Company (WHC) has developed the multi-year planning process for programs to establish the technical, schedule and cost baselines for program and support activities under WHC`s scope of responsibility. The baseline information is developed by both WHC indirect funded support services organization, and direct funded programs in WHC. WHC Planning and Integration utilizes the information presented in the program specific MYPP and the Program Master Baseline Schedule (PMBS) to develop the Site-Wide Integrated Schedule.

  9. RCRA and operational monitoring (ROM): Multi-year program plan and fiscal year 96 work plan. WBS 1.5.3, Revision 1

    International Nuclear Information System (INIS)

    1995-09-01

    The RCRA ampersand Operational Monitoring (ROM) Program Office manages the Hanford Site direct funded Resource Conservation and Recovery Act (RCRA) and Operational Monitoring under Work Breakdown Structure (WBS) 1.01.05.03. The ROM Program Office is included in Hanford Technical Services, a part of Projects ampersand Site Services of Westinghouse Hanford Company (WHC). The 1996 Multi-Year Program Plan (MYPP) includes the Fiscal Year Work Plan (FYWP). The Multi-Year Program Plan takes its direction from the Westinghouse Planning Baseline Integration Organization. The MYPP provides both the near term, enhanced details and the long term, projected details for the Program Office to use as baseline Cost, Scope and Schedule. Change Control administered during the fiscal year is against the baseline provided by near term details of this document. The MYPP process has been developed by WHC to meet its internal planning and integration needs and complies with the requirements of the US Department of Energy, Richland Operations Office (RL) Long Range Planning Process Directive (RLID 5000.2). Westinghouse Hanford Company (WHC) has developed the multi-year planning process for programs to establish the technical, schedule and cost baselines for program and support activities under WHC's scope of responsibility. The baseline information is developed by both WHC indirect funded support services organization, and direct funded programs in WHC. WHC Planning and Integration utilizes the information presented in the program specific MYPP and the Program Master Baseline Schedule (PMBS) to develop the Site-Wide Integrated Schedule

  10. Comments on the future activities of the RERTR program - part II

    Energy Technology Data Exchange (ETDEWEB)

    Krull, W. [GKSS Research Centre Geesthacht GmbH (Germany)

    1997-08-01

    At the last RERTR meeting an historical overview was given and the status and consequences of enrichment reduction were discussed. At that time and somewhat more today many doubts are raised that enrichment reduction, as a tool for reducing the proliferation risk, is being done in the most efficient and convincing manner. The informations presented in this report were taken from IAEA, US-DOE, US-GAO publications and from proceedings of the RERTR meetings. The data presented should be compared only on a relative basis. It was not the intention for many reasons to present quantitative exact values as some figures used for developing the conclusions are being confidential. Others are available in the above mentioned publications and proceedings. But nevertheless conclusions drawn and recommendations developed are believed to be worth to be taken into account by research reactor operators, their funding organizations and administrators when they are faced with decisions about the future of their facilities. All of the international effort on reducing the enrichment on research and test reactors has their only justification from the INFCE (International Nuclear Fuel Cycle Evaluation) conclusions to reduce the proliferation risk worldwide to a large extent. Worldwide is important. IAEA and others have to convince operators and organizations upon the necessity in doing so. One of the best way convincing people is giving convincing examples. At present none of the nations having a military nuclear weapons program is giving such a convincing example. Even in cases where the qualified fuel and all other necessary tools for converting specific research reactors are existing only small or no progress can be seen. Only non-weapon states are being pressed today.

  11. Comments on the future activities of the RERTR program - part II

    International Nuclear Information System (INIS)

    Krull, W.

    1997-01-01

    At the last RERTR meeting an historical overview was given and the status and consequences of enrichment reduction were discussed. At that time and somewhat more today many doubts are raised that enrichment reduction, as a tool for reducing the proliferation risk, is being done in the most efficient and convincing manner. The informations presented in this report were taken from IAEA, US-DOE, US-GAO publications and from proceedings of the RERTR meetings. The data presented should be compared only on a relative basis. It was not the intention for many reasons to present quantitative exact values as some figures used for developing the conclusions are being confidential. Others are available in the above mentioned publications and proceedings. But nevertheless conclusions drawn and recommendations developed are believed to be worth to be taken into account by research reactor operators, their funding organizations and administrators when they are faced with decisions about the future of their facilities. All of the international effort on reducing the enrichment on research and test reactors has their only justification from the INFCE (International Nuclear Fuel Cycle Evaluation) conclusions to reduce the proliferation risk worldwide to a large extent. Worldwide is important. IAEA and others have to convince operators and organizations upon the necessity in doing so. One of the best way convincing people is giving convincing examples. At present none of the nations having a military nuclear weapons program is giving such a convincing example. Even in cases where the qualified fuel and all other necessary tools for converting specific research reactors are existing only small or no progress can be seen. Only non-weapon states are being pressed today. being pressed today

  12. Parallel implementation of the PHOENIX generalized stellar atmosphere program. II. Wavelength parallelization

    International Nuclear Information System (INIS)

    Baron, E.; Hauschildt, Peter H.

    1998-01-01

    We describe an important addition to the parallel implementation of our generalized nonlocal thermodynamic equilibrium (NLTE) stellar atmosphere and radiative transfer computer program PHOENIX. In a previous paper in this series we described data and task parallel algorithms we have developed for radiative transfer, spectral line opacity, and NLTE opacity and rate calculations. These algorithms divided the work spatially or by spectral lines, that is, distributing the radial zones, individual spectral lines, or characteristic rays among different processors and employ, in addition, task parallelism for logically independent functions (such as atomic and molecular line opacities). For finite, monotonic velocity fields, the radiative transfer equation is an initial value problem in wavelength, and hence each wavelength point depends upon the previous one. However, for sophisticated NLTE models of both static and moving atmospheres needed to accurately describe, e.g., novae and supernovae, the number of wavelength points is very large (200,000 - 300,000) and hence parallelization over wavelength can lead both to considerable speedup in calculation time and the ability to make use of the aggregate memory available on massively parallel supercomputers. Here, we describe an implementation of a pipelined design for the wavelength parallelization of PHOENIX, where the necessary data from the processor working on a previous wavelength point is sent to the processor working on the succeeding wavelength point as soon as it is known. Our implementation uses a MIMD design based on a relatively small number of standard message passing interface (MPI) library calls and is fully portable between serial and parallel computers. copyright 1998 The American Astronomical Society

  13. Revised Pourbaix diagrams for Copper at 5-150 C

    International Nuclear Information System (INIS)

    Beverskog, B.; Puigdomenech, I.

    1995-10-01

    Pourbaix diagrams have been revised. Predominance diagrams for dissolved copper species have also been calculated. Five different total concentrations for dissolved copper have been used in the calculations (from 10 -3 to 10 -9 ). The complete hydrolysis series of copper(I) and (II) have not been included in earlier published Pourbaix diagrams, and these species are covered for the first time in this work. At acidic pH, increasing temperature decreases the immunity area, and therefore, it increases the corrosion of the copper. At alkaline pH-values corrosion also increases with the temperature due to the decrease of both passivity and immunity areas. The calculated diagrams are used as a base for the discussion of the corrosion behaviour of the copper canisters in the Swedish radioactive waste management program. 62 refs, 37 figs, 3 tabs

  14. Refurbishment, Modernization and Ageing Management Program of The 3MW TRIGA Mark-II Research Reactor of Bangladesh

    International Nuclear Information System (INIS)

    Salam, M. A.

    2013-01-01

    The 3 MW TRIGA MK-II research reactor of Bangladesh Atomic Energy Commission (BAEC) achieved its first criticality on 14 September 1986. The reactor has been used for manpower training, radioisotope production and various R and D activities in the field of neutron activation analysis, neutron radiography and neutron scattering. Reactor Operation and Maintenance Unit (ROMU) is responsible for operation and maintenance of the research reactor. During the past twenty seven years ROMU carried out several refurbishments, replacement, modification and modernization activities in the reactor facility. The major tasks carried out under refurbishment program were replacement of the corrosion damaged N-16 decay tank by a new one, replacement of the fouled shell and tube type heat exchanger by a plate type one, modification of the shielding arrangements around the N-16 decay tank and ECCS system and solving the radial beam port-1 leakage problem. All of these refurbishment activities were performed under an annual development project (ADP) funded by Bangladesh government. BAEC research reactor (RR) was operated by analogue console system from its commissioning to July, 2011. Old analog based console has been replaced by digital console on June, 2012. Modernization program for the reactor control console due to obsolescence and unavailability of spare parts of I and C system was vital to restore the safe operation of the reactor. Considering these facts, installation of a digital control console and I and C system based on the state-of-the-art digital technology became necessary. Reactor digital console system installation tasks were performed under another ADP funded project by Bangladesh government. Now the reactor is operating with the digital control system. Besides this, the Neutron Radiography (NR) facility has been modernized by the addition of a digital neutron radiography set-up at the tangential beam port. The Neutron Scattering (NS) facility also has been upgraded

  15. Refurbishment, Modernization and Ageing Management Program of The 3MW TRIGA Mark-II Research Reactor of Bangladesh

    Energy Technology Data Exchange (ETDEWEB)

    Salam, M. A. [Atomic Energy Research Establishment, Dhaka (Bangladesh)

    2013-07-01

    The 3 MW TRIGA MK-II research reactor of Bangladesh Atomic Energy Commission (BAEC) achieved its first criticality on 14 September 1986. The reactor has been used for manpower training, radioisotope production and various R and D activities in the field of neutron activation analysis, neutron radiography and neutron scattering. Reactor Operation and Maintenance Unit (ROMU) is responsible for operation and maintenance of the research reactor. During the past twenty seven years ROMU carried out several refurbishments, replacement, modification and modernization activities in the reactor facility. The major tasks carried out under refurbishment program were replacement of the corrosion damaged N-16 decay tank by a new one, replacement of the fouled shell and tube type heat exchanger by a plate type one, modification of the shielding arrangements around the N-16 decay tank and ECCS system and solving the radial beam port-1 leakage problem. All of these refurbishment activities were performed under an annual development project (ADP) funded by Bangladesh government. BAEC research reactor (RR) was operated by analogue console system from its commissioning to July, 2011. Old analog based console has been replaced by digital console on June, 2012. Modernization program for the reactor control console due to obsolescence and unavailability of spare parts of I and C system was vital to restore the safe operation of the reactor. Considering these facts, installation of a digital control console and I and C system based on the state-of-the-art digital technology became necessary. Reactor digital console system installation tasks were performed under another ADP funded project by Bangladesh government. Now the reactor is operating with the digital control system. Besides this, the Neutron Radiography (NR) facility has been modernized by the addition of a digital neutron radiography set-up at the tangential beam port. The Neutron Scattering (NS) facility also has been upgraded

  16. Bibliocable. Revised Edition.

    Science.gov (United States)

    Cable Television Information Center, Washington, DC.

    This selective, annotated bibliography is a revision of the original published in 1972 (ED 071 402). Some 104 books, articles, and reports included here deal with access, applications, franchising, regulation, technology, and other aspects of cable television. The listings are of two types in each category. First are revisions of the original…

  17. Diesel Emission Control- Sulfur Effects (DECSE) Program- Phase II Summary Report: NOx Adsorber Catalysts; FINAL

    International Nuclear Information System (INIS)

    None

    2000-01-01

    The investigations performed in this project demonstrated the ability to develop a NO(sub x) regeneration strategy including both an improved lean/rich modulation cycle and rich engine calibration, which resulted in a high NO(sub x) conversion efficiency over a range of operating temperatures. A high-temperature cycle was developed to desulfurize the NO(sub x) absorber catalyst. The effectiveness of the desulfurization process was demonstrated on catalysts aged using two different sulfur level fuels. The major findings of this project are as follows: (1) The improved lean/rich engine calibration achieved as a part of this test project resulted in NO(sub x) conversion efficiencies exceeding 90% over a catalyst inlet operating temperature window of 300 C-450 C. This performance level was achieved while staying within the 4% fuel economy penalty target defined for the regeneration calibration. (2) The desulfurization procedure developed showed that six catalysts, which had been exposed to fuel sulfur levels of 3-, 16-, and 30-ppm for as long as 250 hours, could be recovered to greater than 85% NO(sub x) conversion efficiency over a catalyst inlet operating temperature window of 300 C-450 C, after a single desulfurization event. This performance level was achieved while staying within the 4% fuel economy penalty target defined for the regeneration calibration. (3) The desulfurization procedure developed has the potential to meet in-service engine operating conditions and provide acceptable driveability conditions. (4) Although aging with 78-ppm sulfur fuel reduced NO(sub x) conversion efficiency more than aging with 3-ppm sulfur fuel as a result of sulfur contamination, the desulfurization events restored the conversion efficiency to nearly the same level of performance. However, repeatedly exposing the catalyst to the desulfurization procedure developed in this program caused a continued decline in the catalyst's desulfurized performance. Additional work will be

  18. Final Report for the MANNRRSS II Program Management of Nevada's Natural Resources with Remote Sensing Systems, Beatty, NV

    Energy Technology Data Exchange (ETDEWEB)

    Lester Miller; Brian Horowitz; Chris Kratt; Tim Minor; Stephen F. Zitzer; James. V. Taranik; Zan L. Aslett; Todd O. Morken

    2009-06-04

    This document provides the Final Report on the Management of Nevada’s Natural Resources with Remote Sensing Systems (MANNRRSS) II program. This is a U.S. Department of Energy (DOE)-funded project tasked with utilizing hyperspectral and ancillary electro-optical instrumentation data to create an environmental characterization of an area directly adjacent to the Nevada Test Site (NTS).

  19. Apollo guidance, navigation and control: Guidance system operations plan for manned CM earth orbital and lunar missions using Program COLOSSUS 3. Section 3: Digital autopilots (revision 14)

    Science.gov (United States)

    1972-01-01

    Digital autopilots for the manned command module earth orbital and lunar missions using program COLOSSUS 3 are discussed. Subjects presented are: (1) reaction control system digital autopilot, (2) thrust vector control autopilot, (3) entry autopilot and mission control programs, (4) takeover of Saturn steering, and (5) coasting flight attitude maneuver routine.

  20. Medicare Program; Revisions to Payment Policies Under the Physician Fee Schedule and Other Revisions to Part B for CY 2017; Medicare Advantage Bid Pricing Data Release; Medicare Advantage and Part D Medical Loss Ratio Data Release; Medicare Advantage Provider Network Requirements; Expansion of Medicare Diabetes Prevention Program Model; Medicare Shared Savings Program Requirements. Final rule.

    Science.gov (United States)

    2016-11-15

    This major final rule addresses changes to the physician fee schedule and other Medicare Part B payment policies, such as changes to the Value Modifier, to ensure that our payment systems are updated to reflect changes in medical practice and the relative value of services, as well as changes in the statute. This final rule also includes changes related to the Medicare Shared Savings Program, requirements for Medicare Advantage Provider Networks, and provides for the release of certain pricing data from Medicare Advantage bids and of data from medical loss ratio reports submitted by Medicare health and drug plans. In addition, this final rule expands the Medicare Diabetes Prevention Program model.