SYNBURN: fast-reactor fuel-cycle program

International Nuclear Information System (INIS)

Pizzica, P.A.; Meneley, D.A.

1976-01-01

The SYNBURN computer program for fast reactors will calculate all the neutronics necessary to completely characterize the equilibrium cycle as well as the startup to equilibrium cycles. The program's run time is very short and this makes the program suitable for survey of parametric studies. It can search on the cycle time for a specified burnup, for the shim control necessary for criticality as well as feed enrichments and the enrichment ratio among core zones. SYNBURN synthesizes in a very simple fashion the one-dimensional fluxes in radial and axial geometry to achieve an approximate two-dimensional solution which agrees very well with the exact two-dimensional solution when measuring regional integrated quantities

24 CFR 92.62 - Review of program description and certifications.

Science.gov (United States)

2010-04-01

... and Urban Development HOME INVESTMENT PARTNERSHIPS PROGRAM Allocation Formula Insular Areas Program... description unless the insular area has failed to submit information sufficient to allow HUD to make the... projects or activities in its program description. (c) HOME Investment Partnership Agreement. After HUD...

Hanford Waste Vitrification Plant quality assurance program description: Overview and applications

International Nuclear Information System (INIS)

Caplinger, W.H.

1990-12-01

This document describes the Hanford Waste Vitrification Plant Project Quality Assurance Program. This program is being implemented to ensure the acceptability of high-level radioactive canistered waste forms produced by the Hanford Waste Vitrification Plant for disposal in a licensed federal repository. The Hanford Waste Vitrification Plant Quality Assurance Program is comprised of this Quality Assurance Program Description as well as the associated contractors' quality assurance programs. The objective of this Quality Assurance Program Description is to provide the Hanford Waste Vitrification Plant Project participants with guidance and direction for program implementation while satisfying the US Department of Energy Office of Civilian Radioactive Waste Management needs in repository licensing activities with regard to canistered waste forms. To accomplish this objective, this description will be prepared in three parts: Part 1 - Overview and applications document; Part 2 - Development and qualification of the canistered waste form; Part 3 - Production of canistered waste forms. Part 1 describes the background, strategy, application, and content of the Hanford Waste Vitrification Plant Quality Assurance Program. This Quality Assurance Program Description, when complete, is designed to provide a level of confidence in the integrity of the canistered waste forms. 8 refs

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.

Description and application of the EAP computer program for calculating life-cycle energy use and greenhouse gas emissions of household consumption items

NARCIS (Netherlands)

Benders, R.M.J.; Wilting, H.C.; Kramer, K.J.; Moll, H.C.

2001-01-01

Focusing on reduction in energy use and greenhouse gas emissions, a life-cycle-based analysis tool has been developed. The energy analysis program (EAP) is a computer program for determining energy use and greenhouse gas emissions related to household consumption items, using a hybrid calculation

French development program on fuel cycle

International Nuclear Information System (INIS)

Viala, M.; Bourgeois, M.

1991-01-01

The need to close the fuel cycle of fast reactors makes the development of the cycle installations (fuel fabrication, irradiated assembly conditioning before reprocessing, reprocessing and waste management) especially independent with the development of the reactor. French experience with the integrated cycle over a period of about 25 years, the tonnage of fuels fabricated (more than 100 t of mixed oxides) for the Rapsodie, Phoenix and SuperPhoenix reactors, and the tonnage of reprocessed fuel (nearly 30 t of plutonium fuel) demonstrate the control of the cycle operations. The capacities of the cycle installations in existence and under construction are largely adequate for presents needs, even including a new European EFR reactor. They include the Cadarache fuel fabrication complex, the La Hague UP2-800 reprocessing plant, and the Marcoule pilot facility. Short- and medium-term R and D programs are connected with fuel developments, with the primary objective of very high burnups. For the longer term and for a specific plant to reprocess fast reactor fuels, the programs could concern new fabrication and reprocessing systems and the study of the consequences of the reduction in fuel out-of-core time

Regulatory research and support program for 1988/89 - project descriptions

Energy Technology Data Exchange (ETDEWEB)

NONE

1988-03-15

Information Bulletin, 1988. Project descriptions for the Regulatory Research and Support Program. This Information Bulletin contains a list of the projects with a brief description of each, and additional supporting information.

Regulatory research and support program for 1988/89 - project descriptions

International Nuclear Information System (INIS)

1988-01-01

Information Bulletin, 1988. Project descriptions for the Regulatory Research and Support Program. This Information Bulletin contains a list of the projects with a brief description of each, and additional supporting information

Technical support for open-cycle MHD program

Energy Technology Data Exchange (ETDEWEB)

None

1978-05-01

The support program for open-cycle MHD at Argonne National Lab is developing the analytical tools needed to investigate the performance of the major components in the combined-cycle MHD/steam power system. The analytical effort is centered on the primary components of the system that are unique to MHD and also on the integration of these analytical representations into a model of the entire power producing system. The present project activities include modeling of the combustor, MHD channel, slag separator, and the high-temperature air preheater. In addition, these models are combined into a complete system model, which is at present capable of carrying out optimizations of the entire system on either thermodynamic efficiency or with less confidence, cost of electrical power. Also, in support of the open-cycle program, considerable effort has gone into the formulation of a CDIF Test Plan and a National MHD Test Program.

MUICYCL and MUIFAP: models tracking minor uranium isotopes in the nuclear fuel cycle

International Nuclear Information System (INIS)

Blum, S.R.; McLaren, R.A.

1979-10-01

Two computer programs have been written to provide information on the buildup of minor uranium isotopes in the nuclear fuel cycle. The Minor Uranium Isotope Cycle Program, MUICYCL, tracks fuel through a multiyear campaign cycle of enrichment, reactor burnup, reprocessing, enrichment, etc. MUICYCL facilities include preproduction stockpiles, U 235 escalation, and calculation of losses. The Minor Uranium Isotope Flowsheet Analyzer Program, MUIFAP, analyzes one minor isotope in one year of an enrichment operation. The formulation of the enrichment cascade, reactors, and reprocessing facility is presented. Input and output descriptions and sample cases are presented. The programs themselves are documented by short descriptions of each routine, flowcharts, definitions of common blocks and variables, and internal documentation. The programs are written in FORTRAN for use in batch mode

Water Resources Research Grant Program project descriptions, fiscal year 1987

Science.gov (United States)

,

1987-01-01

This report contains information on the 34 new projects funded by the United States Geological Survey 's Water Resources Research Grant Program in fiscal year 1987 and on 3 projects completed during the year. For the new projects, the report gives the grant number, project title, performing organization, principal investigator(s), and a project description that includes: (1) identification of water related problems and problem-solution approach (2) contribution to problem solution, (3) objectives, and (4) approach. The 34 projects include 12 in the area of groundwater quality problems, 12 in the science and technology of water quality management, 1 in climate variability and the hydrologic cycle, 4 in institutional change in water resources management, and 5 in surface water management. For the three completed projects, the report furnishes the grant number; project title; performing organization; principal investor(s); starting data; data of receipt of final report; and an abstract of the final report. Each project description provides the information needed to obtain a copy of the final report. The report contains tables showing: (1) proposals received according to area of research interest, (2) grant awards and funding according to area of research interest, (3) proposals received according to type of submitting organization, and (4) awards and funding according to type of organization. (Author 's abstract)

FFTF-cycle 10 program and future plan

Science.gov (United States)

Kohyama, Akira

1988-04-01

Brief outlines are provided of the FFTF cycle 10 program and future plans in consideration. The primary objective of the Japan-US collaboration program is to enable predictions of material behavior in MFRs to be made from data obtained in other irradiation environments. Major program goals are outlined.

Land reclamation program description

Energy Technology Data Exchange (ETDEWEB)

None

1977-05-01

The Land Reclamation Program will address the need for coordinated applied and basic research into the physical and ecological problems of land reclamation, and advance the development of cost-effective techniques for reclaiming and rehabilitating mined coal land to productive end uses. The purpose of this new program is to conduct integrated research and development projects focused on near- and long-term reclamation problems in all major U.S. coal resource regions including Alaska and to coordinate, evaluate, and disseminate the results of related studies conducted at other research institutions. The activities of the Land Reclamation Laboratory program will involve close cooperation with industry and focus on establishing a comprehensive field and laboratory effort. Research demonstration sites will be established throughout the United States to address regional and site-specific problems. Close cooperation with related efforts at academic institutions and other agencies, to transfer pertinent information and avoid duplication of effort, will be a primary goal of the program. The major effort will focus on the complete coal extraction/reclamation cycle where necessary to develop solutions to ameliorating the environmental impacts of coal development. A long-range comprehensive national reclamation program will be established that can schedule and prioritize research activities in all of the major coal regions. A fully integrated data management system will be developed to store and manage relevant environmental and land use data. Nine research demonstration sites have been identified.

ENDF/B-V utility programs: description and operating instructions

International Nuclear Information System (INIS)

McLaughlin, K.

1984-03-01

A description and operating instructions are supplied for the following ENDF/B-V Processing Programs: CHECKER, CRECT, STNDRD, FIZCON, PSYCHE, RESEND, INTER, INTEND, SUMRIZ, PLOTEF, LSTFCV, RIGEL. These programs can be obtained on magnetic tape, free of charge, from the IAEA Nuclear Data Section. (author)

Determination of HSE program proportional to organizational Corporate life cycles

Directory of Open Access Journals (Sweden)

2013-02-01

Result: Corporate life cycles questionnaire with 10 indicators, available HSE programs score cards with 47 indicators according to OGP model and corporate life cycles proper programs table were results of this article. .Conclusion: The results showedweakness in the HSE programs implementation.Therefore, we offered the management methods like upgrade HSE culture and leadership for modification.

Quality assurance program description: Hanford Waste Vitrification Plant, Part 1

International Nuclear Information System (INIS)

1992-01-01

This document describes the Department of Energy's Richland Field Office (DOE-RL) quality assurance (QA) program for the processing of high-level waste as well as the Vitrification Project Quality Assurance Program for the design and construction of the Hanford Waste Vitrification Plant (HWVP). It also identifies and describes the planned activities that constitute the required quality assurance program for the HWVP. This program applies to the broad scope of quality-affecting activities associated with the overall HWVP Facility. Quality-affecting activities include designing, purchasing, fabricating, handling, shipping, storing, cleaning, erecting, installing, inspecting, testing, maintaining, repairing, and modifying. Also included are the development, qualification, and production of waste forms which may be safely used to dispose of high-level radioactive waste resulting from national defense activities. The HWVP QA program is made up of many constituent programs that are being implemented by the participating organizations. This Quality Assurance program description is intended to outline and define the scope and application of the major programs that make up the HWVP QA program. It provides a means by which the overall program can be managed and directed to achieve its objectives. Subsequent parts of this description will identify the program's objectives, its scope, application, and structure

77 FR 48102 - Closed Captioning and Video Description of Video Programming

Science.gov (United States)

2012-08-13

... Captioning and Video Description of Video Programming AGENCY: Federal Communications Commission. [[Page 48103... show that providing captions on their programming would be economically burdensome. DATES: Effective...) establishing requirements for closed captioning on video programming to ensure access by persons with hearing...

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.

Program MASTERCALC: an interactive computer program for radioanalytical computations. Description and operating instructions

International Nuclear Information System (INIS)

Goode, W.

1980-10-01

MASTERCALC is a computer program written to support radioanalytical computations in the Los Alamos Scientific Laboratory (LASL) Environmental Surveillance Group. Included in the program are routines for gross alpha and beta, 3 H, gross gamma, 90 Sr and alpha spectroscopic determinations. A description of MASTERCALC is presented and its source listing is included. Operating instructions and example computing sessions are given for each type of analysis

CANGEO program description and user's instruction

International Nuclear Information System (INIS)

Park, Joo Hwan; Jun, J. S.; Suk, H. C.; Hwang, D. H.; Yoo, Y. J.

1997-10-01

This is a report for the description and user's instruction of CANGEO (CANdu GEOmetry) program. CANGEO program is able to generate the geometry input for thermalhydraulic subchannel analysis of CANDU fuel channel. It is developed for the calculation of subchannel analysis of CANDU fuel channel. It is developed for the calculation of subchannel data for a complicated geometry such as a CANDU fuel channel. And this code can be applicable to a bundle eccentricity from pressure tube center to bundle center, pressure tube creep, rod ballooning, and any symmetric subchannel geometry required by thermalhydraulic subchannel analysis code. The report also describes the basic calculation method of subchannel geometry, including user's manual, input and output for a CANDU fuel channel loaded with 37-element fuel bundle. (author). 35 refs., 6 figs

Nuclear criticality safety program at the Fuel Cycle Facility

International Nuclear Information System (INIS)

Lell, R.M.; Fujita, E.K.; Tracy, D.B.; Klann, R.T.; Imel, G.R.; Benedict, R.W.; Rigg, R.H.

1994-01-01

The Fuel Cycle Facility (FCF) is designed to demonstrate the feasibility of a novel commercial-scale remote pyrometallurgical process for metallic fuels from liquid metal-cooled reactors and to show closure of the Integral Fast Reactor (IFR) fuel cycle. Requirements for nuclear criticality safety impose the most restrictive of the various constraints on the operation of FCF. The upper limits on batch sizes and other important process parameters are determined principally by criticality safety considerations. To maintain an efficient operation within appropriate safety limits, it is necessary to formulate a nuclear criticality safety program that integrates equipment design, process development, process modeling, conduct of operations, a measurement program, adequate material control procedures, and nuclear criticality analysis. The nuclear criticality safety program for FCF reflects this integration, ensuring that the facility can be operated efficiently without compromising safety. The experience gained from the conduct of this program in the Fuel cycle Facility will be used to design and safely operate IFR facilities on a commercial scale. The key features of the nuclear criticality safety program are described. The relationship of these features to normal facility operation is also described

Simulation model for wind energy storage systems. Volume III. Program descriptions. [SIMWEST CODE

Energy Technology Data Exchange (ETDEWEB)

Warren, A.W.; Edsinger, R.W.; Burroughs, J.D.

1977-08-01

The effort developed a comprehensive computer program for the modeling of wind energy/storage systems utilizing any combination of five types of storage (pumped hydro, battery, thermal, flywheel and pneumatic). An acronym for the program is SIMWEST (Simulation Model for Wind Energy Storage). The level of detail of SIMWEST is consistent with a role of evaluating the economic feasibility as well as the general performance of wind energy systems. The software package consists of two basic programs and a library of system, environmental, and load components. Volume III, the SIMWEST program description contains program descriptions, flow charts and program listings for the SIMWEST Model Generation Program, the Simulation program, the File Maintenance program and the Printer Plotter program. Volume III generally would not be required by SIMWEST user.

Development of fusion fuel cycles: Large deviations from US defense program systems

Energy Technology Data Exchange (ETDEWEB)

Klein, James Edward, E-mail: james.klein@srnl.doe.gov; Poore, Anita Sue; Babineau, David W.

2015-10-15

Highlights: • All tritium fuel cycles start with a “Tritium Process.” All have similar tritium processing steps. • Fusion tritium fuel cycles minimize process tritium inventories for various reasons. • US defense program facility designs did not minimize in-process inventories. • Reduced inventory tritium facilities will lower public risk. - Abstract: Fusion energy research is dominated by plasma physics and materials technology development needs with smaller levels of effort and funding dedicated to tritium fuel cycle development. The fuel cycle is necessary to supply and recycle tritium at the required throughput rate; additionally, tritium confinement throughout the facility is needed to meet regulatory and environmental release limits. Small fuel cycle development efforts are sometimes rationalized by stating that tritium processing technology has already been developed by nuclear weapons programs and these existing processes only need rescaling or engineering design to meet the needs of fusion fuel cycles. This paper compares and contrasts features of tritium fusion fuel cycles to United States Cold War era defense program tritium systems. It is concluded that further tritium fuel cycle development activities are needed to provide technology development beneficial to both fusion and defense programs tritium systems.

13 CFR 108.10 - Description of the New Markets Venture Capital Program.

Science.gov (United States)

2010-01-01

... Venture Capital Program. 108.10 Section 108.10 Business Credit and Assistance SMALL BUSINESS ADMINISTRATION NEW MARKETS VENTURE CAPITAL (âNMVCâ) PROGRAM Introduction to Part 108 § 108.10 Description of the New Markets Venture Capital Program. The New Markets Venture Capital (“NMVC”) Program is a...

A CONCEPTUAL MODEL OF THE LIFE CYCLE OF THE PROGRAM

Directory of Open Access Journals (Sweden)

Марія Костянтинівна СУХОНОС

2016-02-01

Full Text Available A conceptual model of the life cycle of the program is proposed. This model is based on the value approach. As a resulting index, it uses a category of complex structural value. This model renders the process of the life cycle of the program in the context of time/result. It assumes the presence of four basic phases of the life cycle, namely, initiation, planning, executing and closing. Also, this model formalizes interconnection of management processes of integration of program and management of its community and subprocesses. Selection of a value approach for the forming of a resulting index of a program determines by a variety of results of the program. This is a result of its variety and complexity in the process of finding a criterion for evaluation. Worked out a mechanism for assessing the value of the program. It consists of four steps and involves using of conventional methods (decomposition and expert estimates. As a unit of measurement assumes to use points and rating scale with the maximum score a hundred points. A complex value, which is evaluated at one hundred points, is a result of the program. It is critically important in the process of current and final evaluation of the program.

A microcomputer program for coupled cycle burnup calculations

International Nuclear Information System (INIS)

Driscoll, M.J.; Downar, T.J.; Taylor, E.L.

1986-01-01

A program, designated BRACC (Burnup, Reactivity, And Cycle Coupling), has been developed for fuel management scoping calculations, and coded in the BASIC language in an interactive format for use with microcomputers. BRACC estimates batch and cycle burnups for sequential reloads for a variety of initial core conditions, and permits the user to specify either reload batch properties (enrichment, burnable poison reactivity) or the target cycle burnup. Most important fuel management tactics (out-in or low-leakage loading, coastdown, variation in number of assemblies charged) can be simulated

Nuclear-fuel-cycle costs. Consolidated Fuel-Reprocessing Program

International Nuclear Information System (INIS)

Burch, W.D.; Haire, M.J.; Rainey, R.H.

1981-01-01

The costs for the back-end of the nuclear fuel cycle, which were developed as part of the Nonproliferation Alternative Systems Assessment Program (NASAP), are presented. Total fuel-cycle costs are given for the pressurized-water reactor once-through and fuel-recycle systems, and for the liquid-metal fast-breeder-reactor system. These calculations show that fuel-cycle costs are a small part of the total power costs. For breeder reactors, fuel-cycle costs are about half that of the present once-through system. The total power cost of the breeder-reactor system is greater than that of light-water reactor at today's prices for uranium and enrichment

ELESTRES.M11K 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.

1992-12-01

ELESTRES.M11K is a computer program for simulating the behaviour of UO 2 fuel elements under normal operating conditions of a CANDU reactor. It computers the one-dimensional temperature distribution and thermal expansion of the fuel pellets, and computes two-dimensional pellet deformation using FEM. The amount of fission gas released and sheath strain/stress are also computed. This document is intended as a users' manual and description for ELESTRES.M11K program. (Author)

Life Cycle V and V Process for Hardware Description Language Programs of Programmable Logic Device-based Instrumentation and Control Systems

International Nuclear Information System (INIS)

Cha, K. H.; Lee, D. Y.

2010-01-01

Programmable Logic Device (PLD), especially Complex PLD (CPLD) or Field Programmable Logic Array (FPGA), has been growing in interest in nuclear Instrumentation and Control (I and C) applications. PLD has been applied to replace an obsolete analog device or old-fashioned microprocessor, or to develop digital controller, subsystem or overall system on hardware aspects. This is the main reason why the PLD-based I and C design provides higher flexibility than the analog-based one, and the PLD-based I and C systems shows better real-time performance than the processor-based I and C systems. Due to the development of the PLD-based I and C systems, their nuclear qualification has been issued in the nuclear industry. Verification and Validation (V and V) is one of necessary qualification activities when a Hardware Description Language (HDL) is used to implement functions of the PLD-based I and C systems. The life cycle V and V process, described in this paper, has been defined as satisfying the nuclear V and V requirements, and it has been applied to verify Correctness, Completeness, and Consistency (3C) among design outputs in a safety-grade programmable logic controller and a safety-critical data communication system. Especially, software engineering techniques such as the Fagan Inspection, formal verification, simulated verification and automated testing have been defined for the life cycle V and V tasks of behavioral, structural, and physical design in VHDL

ORD Water Quality Research Program Mid-Cycle Review - June 2009

Science.gov (United States)

The Board of Scientific Counselors (BOSC) completed a mid-cycle review of the Office of Research and Development’s (ORD) Water Quality Research Program (WQRP), focusing on Agency efforts to enhance the program following the 2006 BOSC program review.

Nuclear proliferation and civilian nuclear power: report of the Nonproliferation Alternative Systems Assessment Program. Volume 1. Program summary

Energy Technology Data Exchange (ETDEWEB)

1979-12-01

This report summarizes the Nonproliferation Alternative Systems Assessment Program (NASAP): its background, its studies, and its results. This introductory chapter traces the growth of the issue of nuclear weapons proliferation and the organization and objectives of NASAP. Chapter 2 summarizes the program's assessments, findings and recommendations. Each of Volumes II-VII reports on an individual assessment (Volume II: Proliferation Resistance; Volume III: Resources and Fuel Cycle Facilities; Volume IV: Commercial Potential; Volume V: Economics and Systems Analysis; Volume VI: Safety and Environmental Considerations for Licensing; Volume VII: International Perspectives). Volume VIII (Advanced Concepts) presents a combined assessment of several less fully developed concepts, and Volume IX (Reactor and Fuel Cycle Descriptions) provides detailed descriptions of the reactor and fuel-cycle systems studied by NASAP.

Nuclear proliferation and civilian nuclear power: report of the Nonproliferation Alternative Systems Assessment Program. Volume 1. Program summary

International Nuclear Information System (INIS)

1979-12-01

This report summarizes the Nonproliferation Alternative Systems Assessment Program (NASAP): its background, its studies, and its results. This introductory chapter traces the growth of the issue of nuclear weapons proliferation and the organization and objectives of NASAP. Chapter 2 summarizes the program's assessments, findings and recommendations. Each of Volumes II-VII reports on an individual assessment (Volume II: Proliferation Resistance; Volume III: Resources and Fuel Cycle Facilities; Volume IV: Commercial Potential; Volume V: Economics and Systems Analysis; Volume VI: Safety and Environmental Considerations for Licensing; Volume VII: International Perspectives). Volume VIII (Advanced Concepts) presents a combined assessment of several less fully developed concepts, and Volume IX (Reactor and Fuel Cycle Descriptions) provides detailed descriptions of the reactor and fuel-cycle systems studied by NASAP

Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume I. Program summary

International Nuclear Information System (INIS)

1980-06-01

This report summarizes the Nonproliferation Alternative Systems Assessment Program (NASAP): its background, its studies, and its results. The introductory chapter traces the growth of the issue of nuclear weapons proliferation and the organization and objectives of NASAP. Chapter 2 summarizes the program's assessments, findings, and recommendations. Each of Volumes II-VII reports on an individual assessment (Volumn II: Proliferation Resistance; Volume III: Resources and Fuel Cycle Facilities; Volume IV: Commercial Potential; Volume V: Economics and Systems Analysis; Volume VI: Safety and Environmental Considerations for Licensing; Volume VII: International Perspectives). Volume VIII (Advanced Concepts) presents a combined assessment of several less fully developed concepts, and Volume IX (Reactor and Fuel Cycle Descriptions) provides detailed descriptions of the reactor and fuel-cycle systems studied by NASAP

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)

Using Specification and Description Language for Life Cycle Assesment in Buildings

Directory of Open Access Journals (Sweden)

Pau Fonseca i Casas

2017-06-01

Full Text Available The definition of a Life Cycle Assesment (LCA for a building or an urban area is a complex task due to the inherent complexity of all the elements that must be considered. Furthermore, a multidisciplinary approach is required due to the different sources of knowledge involved in this project. This multidisciplinary approach makes it necessary to use formal language to fully represent the complexity of the used models. In this paper, we explore the use of Specification and Description Language (SDL to represent the LCA of a building and residential area. We also introduce a tool that uses this idea to implement an optimization and simulation mechanism to define the optimal solution for the sustainability of a specific building or residential.

US Department of Energy, Richland Operations Office Integrated Safety Management System Program Description

International Nuclear Information System (INIS)

SHOOP, D.S.

2000-01-01

The purpose of this Integrated Safety Management System (ISMS) Program Description (PD) is to describe the U.S. Department of Energy (DOE), Richland Operations Office (RL) ISMS as implemented through the RL Integrated Management System (RIMS). This PD does not impose additional requirements but rather provides an overview describing how various parts of the ISMS fit together. Specific requirements for each of the core functions and guiding principles are established in other implementing processes, procedures, and program descriptions that comprise RIMS. RL is organized to conduct work through operating contracts; therefore, it is extremely difficult to provide an adequate ISMS description that only addresses RL functions. Of necessity, this PD contains some information on contractor processes and procedures which then require RL approval or oversight

FURNACE; a toroidal geometry neutronic program system method description and users manual

International Nuclear Information System (INIS)

Verschuur, K.A.

1984-12-01

The FURNACE program system performs neutronic and photonic calculations in 3D toroidal geometry for application to fusion reactors. The geometry description is quite general, allowing any torus cross section and any neutron source density distribution for the plasma, as well as simple parametric representations of circular, elliptic and D-shaped tori and plasmas. The numerical method is based on an approximate transport model that produces results with sufficient accuracy for reactor-design purposes, at acceptable calculational costs. A short description is given of the numerical method, and a user manual for the programs of the system: FURNACE, ANISN-PT, LIBRA, TAPEMA and DRAWER is presented

46 CFR 176.620 - Description of the Alternative Hull Examination (AHE) Program for certain passenger vessels.

Science.gov (United States)

2010-10-01

... 46 Shipping 7 2010-10-01 2010-10-01 false Description of the Alternative Hull Examination (AHE... Hull and Tailshaft Examinations § 176.620 Description of the Alternative Hull Examination (AHE) Program for certain passenger vessels. The Alternative Hull Examination (AHE) Program provides you with an...

46 CFR 71.50-15 - Description of the Alternative Hull Examination (AHE) Program for certain passenger vessels.

Science.gov (United States)

2010-10-01

... 46 Shipping 3 2010-10-01 2010-10-01 false Description of the Alternative Hull Examination (AHE... Description of the Alternative Hull Examination (AHE) Program for certain passenger vessels. The Alternative Hull Examination (AHE) Program provides you with an alternative to a drydock examination by allowing...

Water Conservation Study (Water and Energy), Energy Engineering Analysis Program (EEAP) FY94S, Fort Knox, Kentucky; Executive Summary

National Research Council Canada - National Science Library

1994-01-01

.... Life cycle cost analyses were performed using the Life Cycle Cost in Design (LCCID) computer program. Project descriptions and DD1391 forms were prepared for four Energy Conservation Investment program...

Flash Memory Reliability: Read, Program, and Erase Latency Versus Endurance Cycling

Science.gov (United States)

Heidecker, Jason

2010-01-01

This report documents the efforts and results of the fiscal year (FY) 2010 NASA Electronic Parts and Packaging Program (NEPP) task for nonvolatile memory (NVM) reliability. This year's focus was to measure latency (read, program, and erase) of NAND Flash memories and determine how these parameters drift with erase/program/read endurance cycling.

Windows Calorimeter Control (WinCal) program computer software design description

International Nuclear Information System (INIS)

Pertzborn, N.F.

1997-01-01

The Windows Calorimeter Control (WinCal) Program System Design Description contains a discussion of the design details for the WinCal product. Information in this document will assist a developer in maintaining the WinCal system. The content of this document follows the guidance in WHC-CM-3-10, Software Engineering Standards, Standard for Software User Documentation

Water Conservation Study (Water and Energy) Energy Engineering Analysis Program (EEAP) FY94S Fort Knox, Kentucky. Volume 1

National Research Council Canada - National Science Library

1994-01-01

.... Life cycle cost analyses were performed using the Life Cycle Cost in Design (LCCID) computer program. Project descriptions and DDl39l forms were prepared for four Energy Conservation Investment Program...

Verifiable Fuel Cycle Simulation Model (VISION): A Tool for Analyzing Nuclear Fuel Cycle Futures

International Nuclear Information System (INIS)

Jacobson, Jacob J.; Piet, Steven J.; Matthern, Gretchen E.; Shropshire, David E.; Jeffers, Robert F.; Yacout, A.M.; Schweitzer, Tyler

2010-01-01

The nuclear fuel cycle consists of a set of complex components that are intended to work together. To support the nuclear renaissance, it is necessary to understand the impacts of changes and timing of events in any part of the fuel cycle system such as how the system would respond to each technological change, a series of which moves the fuel cycle from where it is to a postulated future state. The system analysis working group of the United States research program on advanced fuel cycles (formerly called the Advanced Fuel Cycle Initiative) is developing a dynamic simulation model, VISION, to capture the relationships, timing, and changes in and among the fuel cycle components to help develop an understanding of how the overall fuel cycle works. This paper is an overview of the philosophy and development strategy behind VISION. The paper includes some descriptions of the model components and some examples of how to use VISION. For example, VISION users can now change yearly the selection of separation or reactor technologies, the performance characteristics of those technologies, and/or the routing of material among separation and reactor types - with the model still operating on a PC in <5 min.

Policy and Programs for Cycling in the City of Zagreb – A Critical Review

Directory of Open Access Journals (Sweden)

Hrvoje Pilko

2015-10-01

Full Text Available Studying cycling traffic issues in a beginner city – City of Zagreb, stems from unclear development policy, an increase in cycling volume, a large number of traffic accidents, an inadequate infrastructure and legislation, a small number of high quality studies and published papers, and the question, did current cycling policy and programs advance cycling? A comprehensive search of available literature, including data from the Zagreb Traffic Department, was made. These data do not adequately address the direction of causality, such as whether current cycling policy and programs advance cycling or whether cycling demand led to increased levels of cycling. This review paper suggests that, it is not yet possible to evaluate which pro-bicycle packages are the most effective and, development of cycling traffic requires a coordinated holistic planning strategy. Results could serve as a beacon light for similarly sized beginner cities, especially those who are located in South-eastern and Eastern Europe.

Description of the thermoelastic/plastic computer program TEPCO. Memorandum report RSI-0040

International Nuclear Information System (INIS)

Pariseau, W.G.

1975-01-01

Presented is a description of the two-dimensional (plane strain, axial symmetry) thermoelastic/plastic computer program TEPCO used by RE/SPEC Inc. in conjunction with an investigation of rock mechanics of underground radioactive waste disposal

NUFACTS-nuclear fuel cycle activity simulator: reference manual. Final report

International Nuclear Information System (INIS)

Triplett, M.B.; Waddell, J.D.; Breese, T.A.

1978-01-01

The Nuclear Fuel Cycle Activity Simulator (NUFACTS) is a package of FORTRAN subroutines which facilitate the simulation of a diversity of nuclear power growth scenarios. An approach to modeling the nuclear fuel cycle has been developed that is highly adaptive and capable of addressing a variety of problems. Being a simulation model rather than an optimization model, NUFACTS mimics the events and processes that are characteristic of the nuclear fuel cycle. This approach enables the model user to grasp the modeling approach rather quickly. Within this report descriptions of the model and its components are provided with several emphases. First, a discussion of modeling approach and basic assumptions is provided. Next, instructions are provided for generating data, inputting the data properly, and running the code. Finally, detailed descriptions of individual program element are given as an aid to modifying and extending the present capabilities

Technical support for open-cycle MHD program. Progress report, July--December 1978

Energy Technology Data Exchange (ETDEWEB)

Doss, E D [ed.

1979-06-01

The support program for open-cycle MHD at Argonne National Laboratory is developing the analytical tools needed to investigate the performance of the major components in the combined cycle MHD/steam power system. The analytical effort is centered on the primary components of the system that are unique to MHD and also on the integration of these analytical representations into a model of the entire power producing system. The present project activities include modeling of the combustor, MHD channel, slag separator, and high-temperature air heater. In addition, these models are combined into a complete system model, which is at present capable of carrying out optimizations of the entire system relative to either thermodynamic efficiency or cost of electrical power. Also, in support of other aspects of the open-cycle program, test plans are developed and facility and program reviews are provided upon request in support of the needs and requirements of the DOE/MHD Division.

GESIT: a thermodynamic program for single cycle gas turbine plants with and without intercoolers

Energy Technology Data Exchange (ETDEWEB)

Heil, J

1973-08-01

A computer program for the thermodynamic modeling of singlecycle gas turbine plants is described. A high-temperature reactor is assumed as a heat source in the program, but the HTR can be replaced with another heat source without difficulty. Starting from a set of independent data, the program calculates efficiencies and mass flows. It indicates all values for a heat and power balance and prints out the temperatures and pressures for the different parts of the cycle. Besides this, the program is able to optimize the compression ratios for minimal power input. It also takes into account turbine rotor cooling (at the roots of the blades). Furthermore, the program is able to use either total pressure loss or specified losses in different parts of the cycle. The program GESlT can also handle systems with one or two intercoolers, or with no intercooler. GESIT gives all input and output values for the heat exchangers and turbo-machines. First the single-cycle gas turbine plant is described. After that the computational basis for the program and the program structure is explained. Instructions for data input are given so that the program can be immediately utilized. An example of input data together with the associated output is presented. (auth)

Data Science Programs in U.S. Higher Education: An Exploratory Content Analysis of Program Description, Curriculum Structure, and Course Focus

Science.gov (United States)

Tang, Rong; Sae-Lim, Watinee

2016-01-01

In this study, an exploratory content analysis of 30 randomly selected Data Science (DS) programs from eight disciplines revealed significant gaps in current DS education in the United States. The analysis centers on linguistic patterns of program descriptions, curriculum requirements, and DS course focus as pertaining to key skills and domain…

Variable Cycle Engine Technology Program Planning and Definition Study

Science.gov (United States)

Westmoreland, J. S.; Stern, A. M.

1978-01-01

The variable stream control engine, VSCE-502B, was selected as the base engine, with the inverted flow engine concept selected as a backup. Critical component technologies were identified, and technology programs were formulated. Several engine configurations were defined on a preliminary basis to serve as demonstration vehicles for the various technologies. The different configurations present compromises in cost, technical risk, and technology return. Plans for possible variably cycle engine technology programs were formulated by synthesizing the technology requirements with the different demonstrator configurations.

Description Fuel Cycle Spanish. Technical Visits

International Nuclear Information System (INIS)

Ochoa Valero, R.; Vinuesa Carretero, A.

2014-01-01

The nuclear fuel cycle includes all processes and operations from the mining of uranium to the management of radioactive waste generated. These processes include the manufacture of nuclear fuel, the operation of the plants and the storage of radioactive waste in the corresponding temporary stores. (Author)

Fast Reactor Fuel Cycle Cost Estimates for Advanced Fuel Cycle Studies

International Nuclear Information System (INIS)

Harrison, Thomas

2013-01-01

Presentation Outline: • Why Do I Need a Cost Basis?; • History of the Advanced Fuel Cycle Cost Basis; • Description of the Cost Basis; • Current Work; • Fast Reactor Fuel Cycle Applications; • Sample Fuel Cycle Cost Estimate Analysis; • Future Work

46 CFR 115.620 - Description of the Alternative Hull Examination (AHE) Program for certain passenger vessels.

Science.gov (United States)

2010-10-01

... 46 Shipping 4 2010-10-01 2010-10-01 false Description of the Alternative Hull Examination (AHE... ACCOMMODATIONS FOR MORE THAN 49 PASSENGERS INSPECTION AND CERTIFICATION Hull and Tailshaft Examinations § 115.620 Description of the Alternative Hull Examination (AHE) Program for certain passenger vessels. The Alternative...

Comparative analysis of methods and tools for open and closed fuel cycles modeling: MESSAGE and DESAE

International Nuclear Information System (INIS)

Andrianov, A.A.; Korovin, Yu.A.; Murogov, V.M.; Fedorova, E.V.; Fesenko, G.A.

2006-01-01

Comparative analysis of optimization and simulation methods by the example of MESSAGE and DESAE programs is carried out for nuclear power prospects and advanced fuel cycles modeling. Test calculations for open and two-component nuclear power and closed fuel cycle are performed. Auxiliary simulation-dynamic model is developed to specify MESSAGE and DESAE modeling approaches difference. The model description is given [ru

BWR Full Integral Simulation Test (FIST) program: facility description report

International Nuclear Information System (INIS)

Stephens, A.G.

1984-09-01

A new boiling water reactor safety test facility (FIST, Full Integral Simulation Test) is described. It will be used to investigate small breaks and operational transients and to tie results from such tests to earlier large-break test results determined in the TLTA. The new facility's full height and prototypical components constitute a major scaling improvement over earlier test facilities. A heated feedwater system, permitting steady-state operation, and a large increase in the number of measurements are other significant improvements. The program background is outlined and program objectives defined. The design basis is presented together with a detailed, complete description of the facility and measurements to be made. An extensive component scaling analysis and prediction of performance are presented

NASA's Heliophysics Theory Program - Accomplishments in Life Cycle Ending 2011

Science.gov (United States)

Grebowsky, J.

2011-01-01

NASA's Heliophysics Theory Program (HTP) is now into a new triennial cycle of funded research, with new research awards beginning in 2011. The theory program was established by the (former) Solar Terrestrial Division in 1980 to redress a weakness of support in the theory area. It has been a successful, evolving scientific program with long-term funding of relatively large "critical mass groups" pursuing theory and modeling on a scale larger than that available within the limits of traditional NASA Supporting Research and Technology (SR&T) awards. The results of the last 3 year funding cycle, just ended, contributed to ever more cutting edge theoretical understanding of all parts of the Sun-Earth Connection chain. Advances ranged from the core of the Sun out into the corona, through the solar wind into the Earth's magnetosphere and down to the ionosphere and lower atmosphere, also contributing to understanding the environments of other solar system bodies. The HTP contributions were not isolated findings but continued to contribute to the planning and implementation of NASA spacecraft missions and to the development of the predictive computer models that have become the workhorses for analyzing satellite and ground-based measurements.

Description and comparison of pharmacy technician training programs in the United States.

Science.gov (United States)

Anderson, Douglas C; Draime, Juanita A; Anderson, Timothy S

2016-01-01

To describe pharmacy technician training programs in the United States and to compare pharmacy technician program characteristics between programs with and without a pharmacist on faculty and between programs with different accreditation status. Descriptive, cross-sectional study. Not applicable. United States pharmacy technician programs. Not applicable. Student class size, faculty credentials, coursework components, program length, tuition rates, and admission criteria. Currently, there are more than 698 pharmacy technician programs across 1114 campuses, with complete data available for 216 programs. Programs varied widely in terms of class sizes, faculty credentials, and admission criteria. Programs with pharmacists on faculty were significantly less expensive than were those without pharmacists (P = 0.009). Accreditation had no impact on tuition prices. This is the first study of its kind to describe and characterize pharmacy technician training programs. There is relatively little control of technician training by the profession of pharmacy. The quality of these programs in terms of student outcomes is unknown, and it should be explored. Rigorous debate and discussion is needed regarding the future of pharmacy technician roles and the training required for those roles. Copyright © 2016 American Pharmacists Association®. Published by Elsevier Inc. All rights reserved.

Definition study of a Variable Cycle Experimental Engine (VCEE) and associated test program and test plan

Science.gov (United States)

Allan, R. D.

1978-01-01

The Definition Study of a Variable Cycle Experimental Engine (VCEE) and Associated Test Program and Test Plan, was initiated to identify the most cost effective program for a follow-on to the AST Test Bed Program. The VCEE Study defined various subscale VCE's based on different available core engine components, and a full scale VCEE utilizing current technology. The cycles were selected, preliminary design accomplished and program plans and engineering costs developed for several program options. In addition to the VCEE program plans and options, a limited effort was applied to identifying programs that could logically be accomplished on the AST Test Bed Program VCE to extend the usefulness of this test hardware. Component programs were provided that could be accomplished prior to the start of a VCEE program.

Effectiveness of cycle fit, a 6-week training program for novice cyclers, on increasing physical activity: a controlled study.

NARCIS (Netherlands)

Ooms, L.; Veenhof, C.

2014-01-01

Introduction: In the Netherlands, National Sports Federations were funded to develop “easily accessible” sporting programs aimed at inactive population groups. Cycle Fit, a 6-week training program for novice cyclers (i.e. mountain biking, race cycling), developed by the Dutch Cycle Federation, is

Comprehensive Technical Report, General Electric Direct-Air-Cycle Aircraft Nuclear Propulsion Program, Program Summary and References

Energy Technology Data Exchange (ETDEWEB)

Thornton, G.; Rothstein, A.J.

1962-06-28

This is one of twenty-one volumes sumarizing the Aircraft Nuclear Propulsion Program of the General Electric Company. This volume discusses the background to the General Electric program, and summarizes the various direct-air-cycle nuclear test assemblies and power plants that were developed. Because of the requirements of high performance, low weight, and small size, vast improvements in existing technology were required to meet the flight objectives. The technological progress achieved during the program is also summarized. The last appendix contains a compilation of the abstracts, tables of contents, and reference lists of the other twenty volumes.

New approach to the optimization of nuclear fuel cycle - application of the goal programming and the AHP

International Nuclear Information System (INIS)

Kim, Poong Oh

1998-02-01

The front-end fuel cycle from mining to enrichment is in the maturity. Unlike the front-end fuel cycle, there are several pathways in the back-end fuel cycle. in this study five fuel cycle scenarios derived from a unique position in Korea of having a two-reactor programme of PWR and PHWR are proposed. In a selection of an optimal fuel cycle in a country, a number of attributes and factors that interact each other should be taken into account. Those factors to be considered in the study are categorized into two groups, one is tangible factor and the other is intangible factor. The major factors consist of minimizing fuel cycle cost, maximizing resource utilization, minimizing environmental impact and satisfying domestic and international politics. The long-term consequences of any decision for the back-end fuel cycle requires some sophisticated decision making tools. In this paper the Goal Programming method in combination with the Analytic Hierarchy Process (AHP) is applied in the decision making process. The Goal Programming is a very useful decision making tool to solve complex and multi-objective problems. The AHP, a method of solving complex decision problems with multiple attributes or objectives shows the strength in measuring the preferences of the attributes. In the study, the AHP is used for quantification of the intangible factors of which the evaluation is done by a team of nuclear experts. A model for fuel cycle selection is established in accordance with the logic of the Goal Programming. Also an interactive computer program is developed to obtain a solution for the most optimal fuel cycle in Korea

Summary description of the Babcock and Wilcox integrated nuclear design system

International Nuclear Information System (INIS)

Wittkopf, W.A.

1976-03-01

The Babcock and Wilcox integrated nuclear design system is divided into three broad areas: basic nuclear data processing, applications data processing, and nuclear design calculations. In basic nuclear data processing, basic nuclear data are collected, evaluated, and processed into a specified fine-energy mesh multigroup data file called a Master Library. In applications data processing, data for selected materials are retrieved from the Master Library and processed into an optimally structured, multigroup Production Library. Using these data and input descriptions of cells or regions, neutron spectra are generated and few-group constants are computed and fitted as a function of fuel burnup, initial enrichment, temperature, etc. In nuclear design calculations, few-group cross-section fits and descriptions of each core region and core geometry are input to a diffusion-depletion program or a nodal program that computes core reactivity, core power distribution, control rod worth, fuel cycle studies, core operating limitations, etc

Mathematical description and program documentation for CLASSY, an adaptive maximum likelihood clustering method

Science.gov (United States)

Lennington, R. K.; Rassbach, M. E.

1979-01-01

Discussed in this report is the clustering algorithm CLASSY, including detailed descriptions of its general structure and mathematical background and of the various major subroutines. The report provides a development of the logic and equations used with specific reference to program variables. Some comments on timing and proposed optimization techniques are included.

Nuclear-fuel-cycle risk assessment: descriptions of representative non-reactor facilities, Sections 15-19

Energy Technology Data Exchange (ETDEWEB)

Schneider, K.J.

1982-09-01

Information is presented under the following section headings: fuel reprocessing; spent fuel and high-level and transuranic waste storage; spent fuel and high-level and transuranic waste disposal; low-level and intermediate-level waste disposal; and, transportation of radioactive materials in the nuclear fuel cycle. In each of the first three sections a description is given on the mainline process, effluent processing and waste management systems, plant layout, and alternative process schemes. Safety information and a summary are also included in each. The section on transport of radioactive materials includes information on the transportation of uranium ore, uranium ore concentrate, UF/sub 6/, PuO/sub 2/ powder, unirradiated uranium and mixed-oxide fuel assemblies, spent fuel, solidified high-level waste, contact-handled transuranic waste, remote-handled transuranic waste, and low and intermediate level nontransuranic waste. A glossary is included. (JGB)

Nuclear-fuel-cycle risk assessment: descriptions of representative non-reactor facilities, Sections 15-19

International Nuclear Information System (INIS)

Schneider, K.J.

1982-09-01

Information is presented under the following section headings: fuel reprocessing; spent fuel and high-level and transuranic waste storage; spent fuel and high-level and transuranic waste disposal; low-level and intermediate-level waste disposal; and, transportation of radioactive materials in the nuclear fuel cycle. In each of the first three sections a description is given on the mainline process, effluent processing and waste management systems, plant layout, and alternative process schemes. Safety information and a summary are also included in each. The section on transport of radioactive materials includes information on the transportation of uranium ore, uranium ore concentrate, UF 6 , PuO 2 powder, unirradiated uranium and mixed-oxide fuel assemblies, spent fuel, solidified high-level waste, contact-handled transuranic waste, remote-handled transuranic waste, and low and intermediate level nontransuranic waste. A glossary is included

Plutonium immobilization project development and testing quality assurance program description - February 1999

International Nuclear Information System (INIS)

MacLean, L. M.; Ziemba, J.

1999-01-01

Lawrence Livermore National Laboratory Immobilization Development and Testing organization (LLNL ID and T) is a Participant in the Plutonium Immobilization Project (PIP). The LLNL D and T has lead responsibilities for form characterization and qualification, ceramic form development, process/equipment development with plutonium, and process systems testing and validation for both conversion and immobilization. This work must be performed in accordance with the graded approach of a Quality Assurance (QA) Program. A QA Program has been developed at LLNL to meet the requirements of the DOE/MD Quality Assurance Requirements. The LLNL QA Program consists of a Quality Assurance Program Description (QAPD) and Quality Implementing Procedures. These documents interface and are a subset of the overall PIP QA Program Documents. The PIP QA Program is described in the PIP ID and T QA Plan, PIP QAPD, and QA Procedures. Other Participant Organizations also must document and describe their PIP compliant QA Programs in a QAPD and implementing procedures. The purpose of this LLNL QAPD is to describe the organization, management processes, QA Controls for Grading, functional responsibilities, levels of authority, and interfaces for those managing, performing, and assessing the adequacy of work

Reversing the irreversible: From limit cycles to emergent time symmetry

Science.gov (United States)

Cortês, Marina; Smolin, Lee

2018-01-01

In 1979 Penrose hypothesized that the arrows of time are explained by the hypothesis that the fundamental laws are time irreversible [R. Penrose, in General Relativity: An Einstein Centenary Survey (1979)]. That is, our reversible laws, such as the standard model and general relativity are effective, and emerge from an underlying fundamental theory which is time irreversible. In [M. Cortês and L. Smolin, Phys. Rev. D 90, 084007 (2014), 10.1103/PhysRevD.90.084007; 90, 044035 (2014), 10.1103/PhysRevD.90.044035; 93, 084039 (2016), 10.1103/PhysRevD.93.084039] we put forward a research program aiming at realizing just this. The aim is to find a fundamental description of physics above the Planck scale, based on irreversible laws, from which will emerge the apparently reversible dynamics we observe on intermediate scales. Here we continue that program and note that a class of discrete dynamical systems are known to exhibit this very property: they have an underlying discrete irreversible evolution, but in the long term exhibit the properties of a time reversible system, in the form of limit cycles. We connect this to our original model proposal in [M. Cortês and L. Smolin, Phys. Rev. D 90, 084007 (2014), 10.1103/PhysRevD.90.084007], and show that the behaviors obtained there can be explained in terms of the same phenomenon: the attraction of the system to a basin of limit cycles, where the dynamics appears to be time reversible. Further than that, we show that our original models exhibit the very same feature: the emergence of quasiparticle excitations obtained in the earlier work in the space-time description is an expression of the system's convergence to limit cycles when seen in the causal set description.

Thorium fuel cycle management

International Nuclear Information System (INIS)

Zajac, R.; Darilek, P.; Breza, J.; Necas, V.

2010-01-01

In this presentation author deals with the thorium fuel cycle management. Description of the thorium fuels and thorium fuel cycle benefits and challenges as well as thorium fuel calculations performed by the computer code HELIOS are presented.

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

International Nuclear Information System (INIS)

1992-01-01

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

Development of a Standardized Job Description for Healthcare Managers of Metabolic Syndrome Management Programs in Korean Community Health Centers

Directory of Open Access Journals (Sweden)

Youngjin Lee, RN, PhD

2014-03-01

Conclusion: A job description for healthcare managers may provide basic data essential for the development of a job training program for healthcare managers working in community health promotion programs.

Planetary Biology and Microbial Ecology: Molecular Ecology and the Global Nitrogen cycle

Science.gov (United States)

Nealson, Molly Stone (Editor); Nealson, Kenneth H. (Editor)

1993-01-01

This report summarizes the results of the Planetary Biology and Molecular Ecology's summer 1991 program, which was held at the Marine Biological Laboratory in Woods Hole, Massachusetts. The purpose of the interdisciplinary PBME program is to integrate, via lectures and laboratory work, the contributions of university and NASA scientists and student interns. The goals of the 1991 program were to examine several aspects of the biogeochemistry of the nitrogen cycle and to teach the application of modern methods of molecular genetics to field studies of organisms. Descriptions of the laboratory projects and protocols and abstracts and references of the lectures are presented.

Lightweight two-stroke cycle aircraft diesel engine technology enablement program, volume 2

Science.gov (United States)

Freen, P. D.; Berenyi, S. G.; Brouwers, A. P.; Moynihan, M. E.

1985-01-01

An experimental Single Cylinder Test Engine Program is conducted to confirm the analytically projected performance of a two-stroke cycle diesel engine for aircraft applications. Testing confirms the ability of a proposed 4-cylinder version of such an engine to reach the target power at altitude in a highly turbocharged configuration. The experimental program defines all necessary parameters to permit a design of a multicylinder engine for eventual flight applications.

Description of CORSET: a computer program for quantitative x-ray fluorescence analysis

International Nuclear Information System (INIS)

Stohl, F.V.

1980-08-01

Quantitative x-ray fluorescence analysis requires a method of correcting for absorption and secondary fluorescence effects due to the sample matrix. The computer program CORSET carries out these corrections without requiring a knowledge of the spectral distribution of the x-ray source, and only requires one standard per element or one standard containing all the elements. Sandia's version of CORSET has been divided into three separate programs to fit Sandia's specific requirements for on-line analysis in a melt facility. The melt facility is used to fabricate new alloys with very variable compositions and requires very rapid analyses during a run. Therefore, the standards must be analyzed several days in advance. Program DAT1 is used to set up a permanent file consisting of all the data related to the standards. Program UNINT is used to set up a permanent file with the intensities, background counts and counting times of the unknowns. Program CORSET uses the files created in UNINT and DAT1 to carry out the analysis. This report contains descriptions, listings, and sample runs for these programs. The accuracy of the analyses carried out with these three programs is about 1 to 2% relative with an elemental concentration of about 10 wt %

Oil and Gas R&D Programs

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-03-01

This publication describes the major components of the research and development programs of the Department of Energy`s Office of Natural Gas and Petroleum Technology. These programs are commonly referred to collectively as the `Oil and Gas Program.` This document provides customers with a single source of information describing the details of the individual technology program components. This document reflects the results of a planning cycle that began in early 1996 with the development of a scenario analysis for the programs, followed by the development of the coordinated strategic plan. The technology program plans, which are the most recent products of the planning cycle, expand on the program descriptions presented in the coordinated strategic plan, and represent an initial effort to coordinate the Oil and Gas Program exploration and production programs and budgets. Each technology program plan includes a `roadmap` that summarizes the progress of the program to the present and indicates its future direction. The roadmaps describe the program drivers, vision, mission, strategies, and measures of success. Both the individual technology program plans and the strategic plan are dynamic and are intended to be updated regularly.

A computer program for calculation of the fuel cycle in pressurized water reactors

International Nuclear Information System (INIS)

Solanilla, R.

1976-01-01

The purpose of the FUCEFURE program is two-fold: first, it is designed to solve the problem of nuclear fuel cycle cost in one pressurized light water reactor calculation. The code was developed primarily for comparative and sensitivity studies. The program contains simple correlations between exposure and available depletion data used to predict the uranium and plutonium content of the fuel as a function of the fuel initial enrichment. Second, it has been devised to evaluate the nuclear fuel demand associated with an expanding nuclear power system. Evaluation can be carried out at any time and stage in the fuel cycle. The program can calculate the natural uranium and separate work requirements of any final and tails enrichment. It also can determine the nuclear power share of each reactor in the system when a decision has been made about the long-term nuclear power installations to be used and the types of PWR and fast breeder reactor characteristics to be involved in them. (author)

Cycling in Sydney, Australia

Directory of Open Access Journals (Sweden)

Alexis Zander

2013-01-01

Full Text Available Introduction. Cycling can be an enjoyable way to meet physical activity recommendations and is suitable for older people; however cycling participation by older Australians is low. This qualitative study explored motivators, enablers, and barriers to cycling among older people through an age-targeted cycling promotion program. Methods. Seventeen adults who aged 50–75 years participated in a 12-week cycling promotion program which included a cycling skills course, mentor, and resource pack. Semistructured interviews at the beginning and end of the program explored motivators, enablers, and barriers to cycling. Results. Fitness and recreation were the primary motivators for cycling. The biggest barrier was fear of cars and traffic, and the cycling skills course was the most important enabler for improving participants’ confidence. Reported outcomes from cycling included improved quality of life (better mental health, social benefit, and empowerment and improved physical health. Conclusions. A simple cycling program increased cycling participation among older people. This work confirms the importance of improving confidence in this age group through a skills course, mentors, and maps and highlights additional strategies for promoting cycling, such as ongoing improvement to infrastructure and advertising.

A program-level management system for the life cycle environmental and economic assessment of complex building projects

International Nuclear Information System (INIS)

Kim, Chan-Joong; Kim, Jimin; Hong, Taehoon; Koo, Choongwan; Jeong, Kwangbok; Park, Hyo Seon

2015-01-01

Climate change has become one of the most significant environmental issues, of which about 40% come from the building sector. In particular, complex building projects with various functions have increased, which should be managed from a program-level perspective. Therefore, this study aimed to develop a program-level management system for the life-cycle environmental and economic assessment of complex building projects. The developed system consists of three parts: (i) input part: database server and input data; (ii) analysis part: life cycle assessment and life cycle cost; and (iii) result part: microscopic analysis and macroscopic analysis. To analyze the applicability of the developed system, this study selected ‘U’ University, a complex building project consisting of research facility and residential facility. Through value engineering with experts, a total of 137 design alternatives were established. Based on these alternatives, the macroscopic analysis results were as follows: (i) at the program-level, the life-cycle environmental and economic cost in ‘U’ University were reduced by 6.22% and 2.11%, respectively; (ii) at the project-level, the life-cycle environmental and economic cost in research facility were reduced 6.01% and 1.87%, respectively; and those in residential facility, 12.01% and 3.83%, respective; and (iii) for the mechanical work at the work-type-level, the initial cost was increased 2.9%; but the operation and maintenance phase was reduced by 20.0%. As a result, the developed system can allow the facility managers to establish the operation and maintenance strategies for the environmental and economic aspects from a program-level perspective. - Highlights: • A program-level management system for complex building projects was developed. • Life-cycle environmental and economic assessment can be conducted using the system. • The design alternatives can be analyzed from the microscopic perspective. • The system can be used to

A program-level management system for the life cycle environmental and economic assessment of complex building projects

Energy Technology Data Exchange (ETDEWEB)

Kim, Chan-Joong [Parsons Brinckerhoff, Seoul 135-763 (Korea, Republic of); Kim, Jimin; Hong, Taehoon; Koo, Choongwan; Jeong, Kwangbok; Park, Hyo Seon [Department of Architectural Engineering, Yonsei University, Seoul 120-749 (Korea, Republic of)

2015-09-15

Climate change has become one of the most significant environmental issues, of which about 40% come from the building sector. In particular, complex building projects with various functions have increased, which should be managed from a program-level perspective. Therefore, this study aimed to develop a program-level management system for the life-cycle environmental and economic assessment of complex building projects. The developed system consists of three parts: (i) input part: database server and input data; (ii) analysis part: life cycle assessment and life cycle cost; and (iii) result part: microscopic analysis and macroscopic analysis. To analyze the applicability of the developed system, this study selected ‘U’ University, a complex building project consisting of research facility and residential facility. Through value engineering with experts, a total of 137 design alternatives were established. Based on these alternatives, the macroscopic analysis results were as follows: (i) at the program-level, the life-cycle environmental and economic cost in ‘U’ University were reduced by 6.22% and 2.11%, respectively; (ii) at the project-level, the life-cycle environmental and economic cost in research facility were reduced 6.01% and 1.87%, respectively; and those in residential facility, 12.01% and 3.83%, respective; and (iii) for the mechanical work at the work-type-level, the initial cost was increased 2.9%; but the operation and maintenance phase was reduced by 20.0%. As a result, the developed system can allow the facility managers to establish the operation and maintenance strategies for the environmental and economic aspects from a program-level perspective. - Highlights: • A program-level management system for complex building projects was developed. • Life-cycle environmental and economic assessment can be conducted using the system. • The design alternatives can be analyzed from the microscopic perspective. • The system can be used to

Closed Cycle Engine Program Used in Solar Dynamic Power Testing Effort

Science.gov (United States)

Ensworth, Clint B., III; McKissock, David B.

1998-01-01

NASA Lewis Research Center is testing the world's first integrated solar dynamic power system in a simulated space environment. This system converts solar thermal energy into electrical energy by using a closed-cycle gas turbine and alternator. A NASA-developed analysis code called the Closed Cycle Engine Program (CCEP) has been used for both pretest predictions and post-test analysis of system performance. The solar dynamic power system has a reflective concentrator that focuses solar thermal energy into a cavity receiver. The receiver is a heat exchanger that transfers the thermal power to a working fluid, an inert gas mixture of helium and xenon. The receiver also uses a phase-change material to store the thermal energy so that the system can continue producing power when there is no solar input power, such as when an Earth-orbiting satellite is in eclipse. The system uses a recuperated closed Brayton cycle to convert thermal power to mechanical power. Heated gas from the receiver expands through a turbine that turns an alternator and a compressor. The system also includes a gas cooler and a radiator, which reject waste cycle heat, and a recuperator, a gas-to-gas heat exchanger that improves cycle efficiency by recovering thermal energy.

Water reactor safety research program. A description of current and planned research

International Nuclear Information System (INIS)

1978-07-01

The U.S. Nuclear Regulatory Commission (NRC) sponsors confirmatory safety research on lightwater reactors in support of the NRC regulatory program. The principal responsibility of the NRC, as implemented through its regulatory program is to ensure that public health, public safety, and the environment are adequately protected. The NRC performs this function by defining conditions for the use of nuclear power and by ensuring through technical review, audit, and follow-up that these conditions are met. The NRC research program provides technical information, independent of the nuclear industry, to aid in discharging these regulatory responsibilities. The objectives of NRC's research program are the following: (1) to maintain a confirmatory research program that supports assurance of public health and safety, and public confidence in the regulatory program, (2) to provide objectively evaluated safety data and analytical methods that meet the needs of regulatory activities, (3) to provide better quantified estimates of the margins of safety for reactor systems, fuel cycle facilities, and transportation systems, (4) to establish a broad and coherent exchange of safety research information with other Federal agencies, industry, and foreign organization. Current and planned research toward these goals is described

A Descriptive Analysis of the Use of Twitter by Emergency Medicine Residency Programs.

Science.gov (United States)

Diller, David; Yarris, Lalena M

2018-02-01

Twitter is increasingly recognized as an instructional tool by the emergency medicine (EM) community. In 2012, the Council of Residency Directors in Emergency Medicine (CORD) recommended that EM residency programs' Twitter accounts be managed solely by faculty. To date, little has been published regarding the patterns of Twitter use by EM residency programs. We analyzed current patterns in Twitter use among EM residency programs with accounts and assessed conformance with CORD recommendations. In this mixed methods study, a 6-question, anonymous survey was distributed via e-mail using SurveyMonkey. In addition, a Twitter-based search was conducted, and the public profiles of EM residency programs' Twitter accounts were analyzed. We calculated descriptive statistics and performed a qualitative analysis on the data. Of 168 Accreditation Council for Graduate Medical Education-accredited EM programs, 88 programs (52%) responded. Of those programs, 58% (51 of 88) reported having a program-level Twitter account. Residents served as content managers for those accounts in the majority of survey respondents (61%, 28 of 46). Most programs did not publicly disclose the identity or position of their Twitter content manager. We found a wide variety of applications for Twitter, with EM programs most frequently using Twitter for educational and promotional purposes. There is significant variability in the numbers of followers for EM programs' Twitter accounts. Applications and usage among EM residency programs are varied, and are frequently not consistent with current CORD recommendations.

On the use of naturalistic methods to examine safety-relevant behaviours amongst children and evaluate a cycling education program.

Science.gov (United States)

Hatfield, J; Dozza, M; Patton, D A; Maharaj, P; Boufous, S; Eveston, T

2017-11-01

School-based cycling education programs aim to improve cycling safety and participation amongst children. Available research suggests that typical programs, which focus on bicycle manoeuvring skills, have limited effects on behaviour observed on a track or planned route. The current study uses theoretically more valid, naturalistic cycling data, to evaluate Safe Cycle, a program that incorporates hazard and self-awareness training. Soon after Safe Cycle was delivered at treatment schools, research bicycles instrumented with a rearward- and a forward-facing camera were loaned to six children from treatment schools and six children from (waitlist) control schools. In each group half the children were in Year 6, and half were in Year 7/8. Each child was instructed to ride the research bicycle instead of their own bicycle for the 1-2 weeks that they had a research bicycle. Video data were reduced using a purpose-designed coding scheme that identified whether participants performed specific safety-relevant behaviours in appropriate circumstances. While the participants controlled their bicycles well, gave way appropriately to traffic at intersections, and stopped at red lights, participants frequently removed one or both hands from the handlebars, and seldom signalled turns, conducted over-shoulder-checks when changing lanes, or looked in multiple directions at intersections (except when crossing a road). While aspects of design and small sample sizes limited evaluation findings, this research demonstrated the feasibility and potential of naturalistic data to support cycling education program evaluation. Further, the study substantially extended available naturalistic study of children's cycling behaviour to highlight behaviours which might be targeted by cycling safety initiatives. Copyright © 2017 Elsevier Ltd. All rights reserved.

Development of a standardized job description for healthcare managers of metabolic syndrome management programs in Korean community health centers.

Science.gov (United States)

Lee, Youngjin; Choo, Jina; Cho, Jeonghyun; Kim, So-Nam; Lee, Hye-Eun; Yoon, Seok-Jun; Seomun, GyeongAe

2014-03-01

This study aimed to develop a job description for healthcare managers of metabolic syndrome management programs using task analysis. Exploratory research was performed by using the Developing a Curriculum method, the Intervention Wheel model, and focus group discussions. Subsequently, we conducted a survey of 215 healthcare workers from 25 community health centers to verify that the job description we created was accurate. We defined the role of healthcare managers. Next, we elucidated the tasks of healthcare managers and performed needs analysis to examine the frequency, importance, and difficulty of each of their duties. Finally, we verified that our job description was accurate. Based on the 8 duties, 30 tasks, and 44 task elements assigned to healthcare managers, we found that the healthcare managers functioned both as team coordinators responsible for providing multidisciplinary health services and nurse specialists providing health promotion services. In terms of importance and difficulty of tasks performed by the healthcare managers, which were measured using a determinant coefficient, the highest-ranked task was planning social marketing (15.4), while the lowest-ranked task was managing human resources (9.9). A job description for healthcare managers may provide basic data essential for the development of a job training program for healthcare managers working in community health promotion programs. Copyright © 2014. Published by Elsevier B.V.

Studying the Water Cycle in an Environmental Context: The "Blue Planet" Program.

Science.gov (United States)

Ben-zvi-assaraf, Orit; Orion, Nir

The Blue Planet program aims to develop an understanding of and insight into the environment among students by introducing environmental problems such as pollution. This paper presents a study investigating junior high school students' previous knowledge and understanding of environmental issues and perceptions on the nature of the water cycle.…

Lightweight two-stroke cycle aircraft diesel engine technology enablement program, volume 1

Science.gov (United States)

Freen, P. D.; Berenyi, S. G.; Brouwers, A. P.; Moynihan, M. E.

1985-01-01

An experimental Single Cylinder Test Engine Program is conducted to confirm the analytically projected performance of a two-stroke cycle diesel engine for aircraft applications. The test engine delivered 78kW indicated power from 1007cc displacement, operating at 3500 RPM on Schnuerle loop scavenged two-stroke cycle. Testing confirms the ability of a proposed 4-cylinder version of such an engine to reach the target power at altitude, in a highly turbocharged configuration. The experimental program defines all necessary parameters to permit design of a multicylinder engine for eventual flight applications; including injection system requirement, turbocharging, heat rejection, breathing, scavenging, and structural requirements. The multicylinder engine concept is configured to operate with an augmented turbocharger, but with no primary scavenge blower. The test program is oriented to provide a balanced turbocharger compressor to turbine power balance without an auxiliary scavenging system. Engine cylinder heat rejection to the ambient air has been significantly reduced and the minimum overall turbocharger efficiency required is within the range of commercially available turbochargers. Analytical studies and finite element modeling is made of insulated configurations of the engines - including both ceramic and metallic versions. A second generation test engine is designed based on current test results.

Fuel cycle and waste management demonstration in the IFR Program

International Nuclear Information System (INIS)

Lineberry, M.J.; Phipps, R.D.; Benedict, R.W.; Laidler, J.J.; Battles, J.E.; Miller, W.E.

1992-01-01

Argonne's National Laboratory's Integral Fast Reactor (IFR) is the main element in the US advanced reactor development program. A unique fuel cycle and waste process technology is being developed for the IFR. Demonstration of this technology at engineering scale will begin within the next year at the EBR-II test facility complex in Idaho. This paper describes the facility being readied for this demonstration, the process to be employed, the equipment being built, and the waste management approach

Description of Transmutation Library for Fuel Cycle System Analyses

International Nuclear Information System (INIS)

Piet, Steven J.; Bays, Samuel E.; Hoffman, Edward A.

2010-01-01

This report documents the Transmutation Library that is used in Fuel Cycle System Analyses. This version replaces the 2008 version.(Piet2008) The Transmutation Library has the following objectives: (1) Assemble past and future transmutation cases for system analyses. (2) For each case, assemble descriptive information such as where the case was documented, the purpose of the calculation, the codes used, source of feed material, transmutation parameters, and the name of files that contain raw or source data. (3) Group chemical elements so that masses in separation and waste processes as calculated in dynamic simulations or spreadsheets reflect current thinking of those processes. For example, the CsSr waste form option actually includes all Group 1A and 2A elements. (4) Provide mass fractions at input (charge) and output (discharge) for each case. (5) Eliminate the need for either ''fission product other'' or ''actinide other'' while conserving mass. Assessments of waste and separation cannot use ''fission product other'' or ''actinide other'' as their chemical behavior is undefined. (6) Catalog other isotope-specific information in one place, e.g., heat and dose conversion factors for individual isotopes. (7) Describe the correlations for how input and output compositions change as a function of UOX burnup (for LWR UOX fuel) or fast reactor (FR) transuranic (TRU) conversion ratio (CR) for either FR-metal or FR-oxide. This document therefore includes the following sections: (1) Explanation of the data set information, i.e., the data that describes each case. In no case are all of the data presented in the Library included in previous documents. In assembling the Library, we return to raw data files to extract the case and isotopic data, into the specified format. (2) Explanation of which isotopes and elements are tracked. For example, the transition metals are tracked via the following: two Zr isotopes, Zr-other, Tc99, Tc-other, two Mo-Ru-Rh-Pd isotopes, Mo

Computer automation of continuous-flow analyzers for trace constituents in water. Volume 4. Description of program segments. Part 3. TAASTART

International Nuclear Information System (INIS)

Crawford, R.W.

1979-01-01

This report describes TAASTART, the third program in the series of programs necessary in automating the Technicon AutoAnalyzer. Included is a flow chart that illustrates the program logic and a description of each section and subroutine. In addition, all arrays, variables and strings are listed and defined, and a sample program listing with a complete list of symbols and references is provided

78 FR 40421 - Inquiry Regarding Video Description in Video Programming Distributed on Television and on the...

Science.gov (United States)

2013-07-05

... description services for television are provided on a secondary audio stream, and typically a consumer can... box. The Commission recently adopted rules requiring apparatus that is designed to receive, play back, or record video programming transmitted simultaneously with sound to make secondary audio streams...

The AutoBayes Program Synthesis System: System Description

Science.gov (United States)

Fischer, Bernd; Pressburger, Thomas; Rosu, Grigore; Schumann, Johann; Norvog, Peter (Technical Monitor)

2001-01-01

AUTOBAYES is a fully automatic program synthesis system for the statistical data analysis domain. Its input is a concise description of a data analysis problem in the form of a statistical model; its output is optimized and fully documented C/C++ code which can be linked dynamically into the Matlab and Octave environments. AUTOBAYES synthesizes code by a schema-guided deductive process. Schemas (i.e., code templates with associated semantic constraints) are applied to the original problem and recursively to emerging subproblems. AUTOBAYES complements this approach by symbolic computation to derive closed-form solutions whenever possible. In this paper, we concentrate on the interaction between the symbolic computations and the deductive synthesis process. A statistical model specifies for each problem variable (i.e., data or parameter) its properties and dependencies in the form of a probability distribution, A typical data analysis task is to estimate the best possible parameter values from the given observations or measurements. The following example models normal-distributed data but takes prior information (e.g., from previous experiments) on the data's mean value and variance into account.

Study of advanced professional educational requirements relative to nuclear fuel cycle engineering in industry and government. Final report

Energy Technology Data Exchange (ETDEWEB)

Jur, T.A.; Huhns, M.N.; Keating, D.A.; Orloff, D.I.; Rhodes, C.A.; Stanford, T.G.; Stephens, L.M.; Tatterson, G.B.; Van Brunt, V.

1978-12-01

An assessment was conducted of educational needs among engineers working in nuclear fuel cycle-related areas, focusing on the nuclear industry in the Southeast. Educational needs addressed were those at the post-baccalaureate professional level. As a result of the study, a list of subject areas has been compiled as best representing the current content of an educational program. In addition to identifying subject areas, a set of course descriptions and reference materials has been developed around each subject. Each course description contains information regarding objectives, anticipated audience, and prerequisites and offers a suggested course outline. An initial modest program of implementation is recommended which would continue to concentrate on the Southeast as a target area.

Study of advanced professional educational requirements relative to nuclear fuel cycle engineering in industry and government. Final report

International Nuclear Information System (INIS)

Jur, T.A.; Huhns, M.N.; Keating, D.A.; Orloff, D.I.; Rhodes, C.A.; Stanford, T.G.; Stephens, L.M.; Tatterson, G.B.; Van Brunt, V.

1978-12-01

An assessment was conducted of educational needs among engineers working in nuclear fuel cycle-related areas, focusing on the nuclear industry in the Southeast. Educational needs addressed were those at the post-baccalaureate professional level. As a result of the study, a list of subject areas has been compiled as best representing the current content of an educational program. In addition to identifying subject areas, a set of course descriptions and reference materials has been developed around each subject. Each course description contains information regarding objectives, anticipated audience, and prerequisites and offers a suggested course outline. An initial modest program of implementation is recommended which would continue to concentrate on the Southeast as a target area

Development of Thermal Performance Analysis Computer Program on Turbine Cycle of Yoggwang 3,4 Units

Energy Technology Data Exchange (ETDEWEB)

Hong, S.Y.; Choi, K.H.; Jee, M.H.; Chung, S.I. [Korea Electric Power Research Institute, Taejon (Korea)

2002-07-01

The objective of the study ''Development of Thermal Performance Analysis Computer Program on Turbine Cycle of Yonggwang 3,4 Units'' is to utilize computerized program to the performance test of the turbine cycle or the analysis of the operational status of the thermal plants. In addition, the result can be applicable to the analysis of the thermal output at the abnormal status and be a powerful tool to find out the main problems for such cases. As a results, the output of this study can supply the way to confirm the technical capability to operate the plants efficiently and to obtain the economic gains remarkably. (author). 27 refs., 73 figs., 6 tabs.

Accreditation status of U.S. military graduate medical education programs.

Science.gov (United States)

De Lorenzo, Robert A

2008-07-01

Military graduate medical education (GME) comprises a substantial fraction of U.S. physician training capacity. The wars in Iraq and Afghanistan have placed substantial stress on military medicine, and lay and professional press accounts have raised awareness of the effects on military GME. To date, however, objective data on military GME quality remains sparse. Determine the accreditation status of U.S. military GME programs. Additionally, military GME program data will be compared to national (U.S.) accreditation lengths. Retrospective review of Accreditation Council for Graduate Medical Education (ACGME) data. All military-sponsored core programs in specialties with at least three residencies were included. Military-affiliated but civilian-sponsored programs were excluded. The current and past cycle data were used for the study. For each specialty, the current mean accreditation length and the net change in cycle was calculated. National mean accreditation lengths by specialty for 2005 to 2006 were obtained from the ACGME. Comparison between the overall mean national and military accreditation lengths was performed with a z test. All other comparisons employed descriptive statistics. Ninety-nine military programs in 15 specialties were included in the analysis. During the study period, 1 program was newly accredited, and 6 programs had accreditation withdrawn or were closed. The mean accreditation length of the military programs was 4.0 years. The overall national mean for the same specialties is 3.5 years (p < 0.01). In previous cycles, 68% of programs had accreditation of 4 years or longer, compared to 70% in the current cycle, while 13% had accreditation of 2 years or less in the previous cycle compared to 14% in the current cycle. Ten (68%) of the military specialties had mean accreditation lengths greater than the national average, while 5 (33%) were below it. Ten (68%) specialties had stable or improving cycle lengths when compared to previous cycles

A weight-loss program adapted to the menstrual cycle increases weight loss in healthy, overweight, premenopausal women

DEFF Research Database (Denmark)

Geiker, Nina R W; Ritz, Christian; Pedersen, Sue D

2016-01-01

compared with the effect of simple energy restriction. DESIGN: A total of 60 healthy, overweight, premenopausal women were included in a 6-mo weight-loss program in which each subject consumed a diet of 1600 kcal/d. Subjects were randomly assigned to either a combined diet and exercise program...... that was tailored to metabolic changes of the menstrual cycle (Menstralean) or to undergo simple energy restriction (control). RESULTS: Thirty-one women (19 Menstralean and 12 control women) completed the study [mean ± SD body mass index (in kg/m(2)): 32.0 ± 5.2]. Both groups lost weight during the study....... CONCLUSION: A differentiated diet and exercise program that is tailored to counteract food cravings and metabolic changes throughout the menstrual cycle may increase weight loss above that achieved with a traditional diet and exercise program in women who can comply with the program. This trial...

ITER fuel cycle

International Nuclear Information System (INIS)

Leger, D.; Dinner, P.; Yoshida, H.

1991-01-01

Resulting from the Conceptual Design Activities (1988-1990) by the parties involved in the International Thermonuclear Experimental Reactor (ITER) project, this document summarizes the design requirements and the Conceptual Design Descriptions for each of the principal subsystems and design options of the ITER Fuel Cycle conceptual design. The ITER Fuel Cycle system provides for the handling of all tritiated water and gas mixtures on ITER. The system is subdivided into subsystems for fuelling, primary (torus) vacuum pumping, fuel processing, blanket tritium recovery, and common processes (including isotopic separation, fuel management and storage, and processes for detritiation of solid, liquid, and gaseous wastes). After an introduction describing system function and conceptual design procedure, a summary of the design is presented including a discussion of scope and main parameters, and the fuel design options for fuelling, plasma chamber vacuum pumping, fuel cleanup, blanket tritium recovery, and auxiliary and common processes. Design requirements are defined and design descriptions are given for the various subsystems (fuelling, plasma vacuum pumping, fuel cleanup, blanket tritium recovery, and auxiliary/common processes). The document ends with sections on fuel cycle design integration, fuel cycle building layout, safety considerations, a summary of the research and development programme, costing, and conclusions. Refs, figs and tabs

Employee assistance programs: history and program description.

Science.gov (United States)

Gilbert, B

1994-10-01

1. The history and development of Employee Assistance Programs (EAPs) can be traced back to the 1800s. There are currently over 10,000 EAPs in the United States. 2. Standards for program accreditation and counselor certification have been established for EAPs. The "core technology of Employee Assistance Programs" includes identification of behavioural problems based on job performance issues, expert consultation with supervisors, appropriate use of constructive confrontation, microlinkages with treatment providers and resources, macrolinkages between providers, resources, and work organizations, focus on substance abuse, and evaluation of employee success based on job performance. 3. Some EAPs take a broad brush approach, and incorporate health promotion and managed care functions.

The EBR-II fuel cycle story

International Nuclear Information System (INIS)

Stevenson, C.E.

1987-01-01

This volume on the history of the Experimental Breeder Reactor (EBR) program and the Fuel Cycle Facility (FCF) offers both the historical perspective and ''reasons why'' the project was so successful. The operation of the FCF in conjunction with the EBR-II was prepared because of the unique nature of the pyrmetallurgical processing system that was demonstrated at the time. Following brief descriptions and histories of the EBR-I and EBR-II reactors, the FCF and its process requirements are described. The seven principal process steps are presented, including for each one, the development, equipment used, operating procedures, results, problems and other data. Scrap and waste disposition, analytical control, safety, management, and cost of the FCF are also included

Firebird-III program description

International Nuclear Information System (INIS)

Lin, M.R.; Prawirosochardjo, S.; Rennick, D.F.; Wessman, E.; Blain, R.J.D.; Wilson, J.M.

1979-09-01

The FIREBIRD-III digital computer program is a general network code developed primarily for predicting the thermalhydraulic behaviour of CANDU power reactors during a postulated loss-of-coolant accident and the subsequent emergency coolant injection. Because of its flexibility, the code can also be used to solve a large variety of general two-phase flow problems. This report describes the thermalhydraulic models and the computation methods used in the program

A Cycle of Redemption in a Medical Error Disclosure and Apology Program.

Science.gov (United States)

Carmack, Heather J

2014-06-01

Physicians accept that they have an ethical responsibility to disclose and apologize for medical errors; however, when physicians make a medical error, they are often not given the opportunity to disclose and apologize for the mistake. In this article, I explore how one hospital negotiated the aftermath of medical mistakes through a disclosure and apology program. Specifically, I used Burke's cycle of redemption to position the hospital's disclosure and apology program as a redemption process and explore how the hospital physicians and administrators worked through the experiences of disclosing and apologizing for medical errors. © The Author(s) 2014.

Respiratory Protection Program. Programmatic description

Energy Technology Data Exchange (ETDEWEB)

Brooks, J.M.; Porter, W.E.

1986-03-01

The ORNL Respirator Program is designed to provide employees with devices which afford maximum protection with minimum inconvenience and discomfort. Teamwork is essential since a comprehensive program involves the Medical Department, the Industrial Hygiene Department, Radiation and Safety Surveys, the Operations Division, Quality Assurance and Inspection, and the Fire Department. The purpose of this manual is to describe in detail the ORNL Respirator Program. Included are discussions of the following elements: quality assurance, selection, fit-testing, maintenance and issue, certified breathing air for self-contained breathing apparatus, inspection, program surveillance, available devices, and standard operating procedures. As program modifications develop and improvements are made, periodic revisions may be necessary. The Industrial Hygiene Department will perform this task on an ''as required'' basis.

Emended description of Pasteuria nishizawae.

Science.gov (United States)

Noel, Gregory R; Atibalentja, N; Domier, Leslie L

2005-07-01

The description of the Gram-positive, obligately parasitic, mycelial and endospore-forming bacterium, Pasteuria nishizawae, is emended to include additional observations on the life cycle, host specificity and endospore morphology. The nucleotide sequence of the 16S rRNA gene is also provided.

RIMS Program Description.

Science.gov (United States)

Kraepelien, Hans

Computer routines for the translation of teacher-prepared mark sense forms to magnetic tape are described. The program, Receiving IMS (RIMS), is part of the Southwest Regional Laboratory's (SWRL) Instructional Management System (IMS). It accepts mark sense sheets from remotely located Xerox 660 scanner copiers and/or IMS update information from…

Summary of non-US national and international fuel cycle and radioactive waste management programs 1982

Energy Technology Data Exchange (ETDEWEB)

Harmon, K.M.; Kelman, J.A.

1982-08-01

Brief program overviews of fuel cycle, spent fuel, and waste management activities in the following countries are provided: Argentina, Australia, Austria, Belgium, Brazil, Canada, China, Denmark, Finland, France, German Federal Republic, India, Italy, Japan, Republic of Korea, Mexico, Netherlands, Pakistan, South Africa, Spain, Sweden, Switzerland, Taiwan, USSR, and the United Kingdom. International nonproliferation activities, multilateral agreements and projects, and the international agencies specifically involved in the nuclear fuel cycle are also described.

Summary of non-US national and international fuel cycle and radioactive waste management programs 1982

International Nuclear Information System (INIS)

Harmon, K.M.; Kelman, J.A.

1982-08-01

Brief program overviews of fuel cycle, spent fuel, and waste management activities in the following countries are provided: Argentina, Australia, Austria, Belgium, Brazil, Canada, China, Denmark, Finland, France, German Federal Republic, India, Italy, Japan, Republic of Korea, Mexico, Netherlands, Pakistan, South Africa, Spain, Sweden, Switzerland, Taiwan, USSR, and the United Kingdom. International nonproliferation activities, multilateral agreements and projects, and the international agencies specifically involved in the nuclear fuel cycle are also described

Strategic environmental safety inspection for the National disposal program. Description of the inspection volume. Documentation for the scoping team

International Nuclear Information System (INIS)

2015-01-01

The Strategic environmental safety inspection for the National disposal program covers the following topics: Legal framework: determination of the requirement for an environmental inspection program, coordination of the scoping team into the overall context; environmental targets; approach for assessment and evaluation of environmental impact, description of the inspection targets for the strategic environmental inspection; consideration of alternatives.

System description of the Repository-Only System for the FY 1990 systems integration program studies

International Nuclear Information System (INIS)

McKee, R.W.; Young, J.R.; Konzek, G.J.

1991-07-01

This document provides both functional and physical descriptions of a conceptual high-level waste management system defined as a Repository-Only System. Its purpose is to provide a basis for required system computer modeling and system studies initiated in FY 1990 under the Systems Integration Program of the US Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM). The Repository-Only System is designed to accept 3000 MTU per year of spent fuel and 400 equivalent MTU per year of high-level wastes disposal in the geologic repository. This document contains both functional descriptions of the processes in the waste management system and physical descriptions of the equipment and facilities necessary for performance of those processes. These descriptions contain the level of detail needed for the projected systems analysis studies. The Repository-Only System contains all system components, from the waste storage facilities of the waste generators to the underground facilities for final disposal of the wastes. The major facilities in the system are the waste generator waste storage facilities, a repository facility that packages the wastes and than emplaces them in the geologic repository, and the transportation equipment and facilities for transporting the wastes between these major facilities. 18 refs., 39 figs

Effects of menstrual cycle phase on ratings of implicitly erotic art.

Science.gov (United States)

Rudski, Jeffrey M; Bernstein, Lauren R; Mitchell, Joy E

2011-08-01

Women's perceptions of and responses to explicitly erotic stimuli have been shown to vary across the menstrual cycle. The present study examined responses to implicit eroticism. A total of 83 women provided reactions to paintings by Georgia O'Keeffe in 6 day intervals over the course of 1 month. Among freely cycling women (n = 37), 31% of their descriptions included sexual themes during the first half of their cycle, dropping to 9% of descriptions in the second half. In women using oral contraceptives (n = 46), there was no significant difference in descriptions across the cycle (13% in the first half vs. 17% in the second half). Results were discussed in terms of evolutionary psychology and social-cognitive perspectives on the relationships between hormonal fluctuations and sexuality.

Hardware description languages

Science.gov (United States)

Tucker, Jerry H.

1994-01-01

Hardware description languages are special purpose programming languages. They are primarily used to specify the behavior of digital systems and are rapidly replacing traditional digital system design techniques. This is because they allow the designer to concentrate on how the system should operate rather than on implementation details. Hardware description languages allow a digital system to be described with a wide range of abstraction, and they support top down design techniques. A key feature of any hardware description language environment is its ability to simulate the modeled system. The two most important hardware description languages are Verilog and VHDL. Verilog has been the dominant language for the design of application specific integrated circuits (ASIC's). However, VHDL is rapidly gaining in popularity.

Hanford Waste Vitrification Plant Quality Assurance Program description for high-level waste form development and qualification

International Nuclear Information System (INIS)

1993-08-01

The Hanford Waste Vitrification Plant Project has been established to convert the high-level radioactive waste associated with nuclear defense production at the Hanford Site into a waste form suitable for disposal in a deep geologic repository. The Hanford Waste Vitrification Plant will mix processed radioactive waste with borosilicate material, then heat the mixture to its melting point (vitrification) to forin a glass-like substance that traps the radionuclides in the glass matrix upon cooling. The Hanford Waste Vitrification Plant Quality Assurance Program has been established to support the mission of the Hanford Waste Vitrification Plant. This Quality Assurance Program Description has been written to document the Hanford Waste Vitrification Plant Quality Assurance Program

Computer automation of continuous-flow analyzers for trace constituents in water. Volume 4. Description of program segments. Part 2. TAAINRE

International Nuclear Information System (INIS)

Crawford, R.W.

1979-01-01

TAAINRE, the second program in the series of programs necessary in automating the Technicon AutoAnalyzer, is presented. A flow chart and sequence list that describes and illustrates the function of each logical group of coding, and a description of the contents and function of each section and subroutine in the program is included. In addition, all arrays, strings, and variables are listed and defined, and a sample program listing with a complete list of symbols and references provided

Computer automation of continuous-flow analyzers for trace constituents in water. Volume 4. Description of program segments. Part 1. TAAIN

International Nuclear Information System (INIS)

Crawford, R.W.

1979-01-01

This report describes TAAIN, the first program in the series of programs necessary in automating the Technicon AutoAnalyzer. A flow chart and sequence list that describes and illustrates each logical group of coding, and a description of the contents and functions of each section and subroutine in the program is included. In addition, all arrays, strings, and variables are listed and defined, and a sample program listing with a complete list of symbols and references is provided

Description and use of NUFCOS-2 for fuel cycle analyses

International Nuclear Information System (INIS)

Westerberg, R.; Vira, J.

1980-12-01

NUFCOS-2 is a continuation to the series of computerized nuclear fuel cycle models which recently have been developed at the Nuclear Engineering Laboratory of the Technical Research Centre of Finland. While the main purpose of the previous NUFCOS model was the multiobjective optimization of the light water reactor fuel cycle, the present version takes a broader view of the global development of the different fuel cycles, especially with regard to the use of plutonium as a fuel in converters or breeders. In this respect an essential feature of NUFCOS-2 is the consideration of the coupling between the consumption and the prices of natural uranium. This report describes the NUFCOS-2 model with main emphasis on the computer application. First the underlying flow equations for the nuclear material are explained in some detail and the structure of the calculation system is represented. The rest of the report, including the appendices, then describes the practical use of the computer model. An example of the input has been provided. (author)

NICMOS Cycles 13 and 14 Calibration Plans

Science.gov (United States)

Arribas, Santiago; Bergeron, Eddie; de Jong, Roeof; Malhotra, Sangeeta; Mobasher, Bahram; Noll, Keith; Schultz, Al; Wiklind, Tommy; Xu, Chun

2005-11-01

This document summarizes the NICMOS Calibration Plans for Cycles 13 and 14. These plans complement the SMOV3b, the Cycle 10 (interim), and the Cycles 11 and 12 (regular) calibration programs executed after the installation of the NICMOS Cooling System (NCS).. These previous programs have shown that the instrument is very stable, which has motivated a further reduction in the frequency of the monitoring programs for Cycle 13. In addition, for Cycle 14 some of these programs were slightly modified to account for 2 Gyro HST operations. The special calibrations on Cycle 13 were focussed on a follow up of the spectroscopic recalibration initiated in Cycle 12. This program led to the discovery of a possible count rate non-linearity, which has triggered a special program for Cycle 13 and a number of subsequent tests and calibrations during Cycle 14. At the time of writing this is a very active area of research. We also briefly comment on other calibrations defined to address other specific issues like: the autoreset test, the SPAR sequences tests, and the low-frequency flat residual for NIC1. The calibration programs for the 2-Gyro campaigns are not included here, since they have been described somewhere else. Further details and updates on specific programs can be found via the NICMOS web site.

Identification and Analysis of Critical Gaps in Nuclear Fuel Cycle Codes Required by the SINEMA Program

International Nuclear Information System (INIS)

Miron, Adrian; Valentine, Joshua; Christenson, John; Hawwari, Majd; Bhatt, Santosh; Dunzik-Gougar, Mary Lou; Lineberry, Michael

2009-01-01

The current state of the art in nuclear fuel cycle (NFC) modeling is an eclectic mixture of codes with various levels of applicability, flexibility, and availability. In support of the advanced fuel cycle systems analyses, especially those by the Advanced Fuel Cycle Initiative (AFCI), University of Cincinnati in collaboration with Idaho State University carried out a detailed review of the existing codes describing various aspects of the nuclear fuel cycle and identified the research and development needs required for a comprehensive model of the global nuclear energy infrastructure and the associated nuclear fuel cycles. Relevant information obtained on the NFC codes was compiled into a relational database that allows easy access to various codes' properties. Additionally, the research analyzed the gaps in the NFC computer codes with respect to their potential integration into programs that perform comprehensive NFC analysis.

Identification and Analysis of Critical Gaps in Nuclear Fuel Cycle Codes Required by the SINEMA Program

Energy Technology Data Exchange (ETDEWEB)

Adrian Miron; Joshua Valentine; John Christenson; Majd Hawwari; Santosh Bhatt; Mary Lou Dunzik-Gougar: Michael Lineberry

2009-10-01

The current state of the art in nuclear fuel cycle (NFC) modeling is an eclectic mixture of codes with various levels of applicability, flexibility, and availability. In support of the advanced fuel cycle systems analyses, especially those by the Advanced Fuel Cycle Initiative (AFCI), Unviery of Cincinnati in collaboration with Idaho State University carried out a detailed review of the existing codes describing various aspects of the nuclear fuel cycle and identified the research and development needs required for a comprehensive model of the global nuclear energy infrastructure and the associated nuclear fuel cycles. Relevant information obtained on the NFC codes was compiled into a relational database that allows easy access to various codes' properties. Additionally, the research analyzed the gaps in the NFC computer codes with respect to their potential integration into programs that perform comprehensive NFC analysis.

Combined cycle power plant with integrated low temperature heat (LOTHECO)

International Nuclear Information System (INIS)

Kakaras, E.; Doukelis, A.; Leithner, R.; Aronis, N.

2004-01-01

The major driver to enhance the efficiency of the simple gas turbine cycle has been the increase in process conditions through advancements in materials and cooling methods. Thermodynamic cycle developments or cycle integration are among the possible ways to further enhance performance. The current paper presents the possibilities and advantages from the LOTHECO natural gas-fired combined cycle concept. In the LOTHECO cycle, low-temperature waste heat or solar heat is used for the evaporation of injected water droplets in the compressed air entering the gas turbine's combustion chamber. Following a description of this innovative cycle, its advantages are demonstrated by comparison between different gas turbine power generation systems for small and large-scale applications, including thermodynamic and economic analysis. A commercial gas turbine (ALSTOM GT10C) has been selected and computed with the heat mass balance program ENBIPRO. The results from the energy analysis are presented and the features of each concept are discussed. In addition, the exergy analysis provides information on the irreversibilities of each process and suggested improvements. Finally, the economic analysis reveals that the combined cycle plant with a heavy-duty gas turbine is the most efficient and economic way to produce electricity at base load. However, on a smaller scale, innovative designs, such as the LOTHECO concept, are required to reach the same level of performance at feasible costs

Design of Training Systems, Phase II Report, Volume III; Model Program Descriptions and Operating Procedures. TAEG Report No. 12-2.

Science.gov (United States)

Naval Training Equipment Center, Orlando, FL. Training Analysis and Evaluation Group.

The Design of Training Systems (DOTS) project was initiated by the Department of Defense (DOD) to develop tools for the effective management of military training organizations. Volume 3 contains the model and data base program descriptions and operating procedures designed for phase 2 of the project. Flow charts and program listings for the…

Status of the joint United States/Japanese criticality data development program for the Fast Breeder fuel cycle

International Nuclear Information System (INIS)

Takeda, H.; Kishimoto, Y.; Matsumoto, T.; Haire, M.J.

1987-01-01

An experimental program is described to accumulate the basic criticality data on uranium-plutonium aqueous solution systems, including pin and water systems. This experimental program, managed by the Consolidated Fuel Reprocessing Program, utilized existing critical experiment facilities. However, Japan at least for the near future, does not have a facility for conducting critical experiments where fissible solution can be treated and processed. Therefore, Japan has remoted the existing US experimental program as well as enlarged the program so that a close cooperative relationship may exist in this area. This paper is an update of a description of the program presented in September 1985. 9 refs., 5 figs., 1 tab

ALKASYS, Rankine-Cycle Space Nuclear Power System

International Nuclear Information System (INIS)

2001-01-01

1 - Description of program or function: The program ALKASYS is used for the creation of design concepts of multimegawatt space power systems that employ potassium Rankine power conversion cycles. 2 - Method of solution: ALKASYS calculates performance and design characteristics and mass estimates for the major subsystems composing the total power system. Design and engineering performance characteristics are determined by detailed engineering procedures rather than by empirical algorithms. Mass estimates are developed using basic design principles augmented in some cases by empirical coefficients determined from the literature. The reactor design is based on a fast spectrum, metallic-clad rod fuel element containing UN pellets. 3 - Restrictions on the complexity of the problem: ALKASYS was developed primarily for the analysis of systems with electric power in the range from 1,000 to 25,000 kW(e) and full-power life from 1 to 10 years. The program should be used with caution in systems that are limited by heat flux (which might indicate need for extended surfaces on fuel elements) or criticality (which might indicate the need for other geometries or moderators)

The Analysis of Simulation Based Acquisition (SBA) Economic Breakpoints in the Life Cycle of Major Programs

National Research Council Canada - National Science Library

Hunt, George

2002-01-01

...). Application of SBA initiatives relies upon the use of modeling and simulation, among other methods, to effectively use scarce resources funds, manpower, equipment in the life cycle of major programs...

Ethanol Research : Alternative Fuels & Life-Cycle Engineering Program : November 29, 2006 to November 28, 2011

Science.gov (United States)

2011-12-20

This report presents the results of the successful ethanol fuel demonstration program conducted from September 2007 to September 2010. This project was a part of the U.S. Department of Transportation (DOT) Alternative Fuels and Life Cycle Engineering...

REFCO83, Nuclear Fuel Cycle Cost Economics Using Discounted Cash Flow Analysis

International Nuclear Information System (INIS)

Delene, J.G.; Hermann, O.W.

2001-01-01

1 - Description of program or function: REFCO83 utilizes a discounted cash flow (DCF) analysis procedure to calculate batch, cycle, and lifetime levelized average nuclear fuel cycle costs. The DCF analysis establishes an energy 'cost' associated with the fuel by requiring that the revenues from the sale of energy be adequate to pay the required return on outstanding capital, to pay all expenses including taxes, and to retire the outstanding investment to zero by the end of the economic life of the set of fuel investments. The program uses reactor mass flow information together with individual fuel cost parameters and utility capital structure and money costs to calculate levelized costs cumulatively through any batch or cycle. 2 - Method of solution: A fuel cycle cost component is considered to be any fuel material purchase, processing cost, or discharge material credit in the complete fuel cycle. The costs for each individual component, i.e. uranium, enrichment, etc., may either be expensed or capitalized for tax purposes or, in the case of waste disposal, the cost may also be made proportional to power production. To properly account for the effect of income taxes, all calculations in REFCO83 are done using 'then' current dollars, including price escalations caused by inflation. The database used for the default values for REFCO83 was taken from the Nuclear Energy Cost Data Base. 3 - Restrictions on the complexity of the problem: The maximum number of fuel batches is 120

U.S. FUEL CYCLE TECHNOLOGIES R&D PROGRAM FOR NEXT GENERATION NUCLEAR MATERIALS MANAGEMENT

Directory of Open Access Journals (Sweden)

M.C. MILLER

2013-11-01

Full Text Available The U.S. Department of Energy's Fuel Cycle Technologies R&D program under the Office of Nuclear Energy is working to advance technologies to enhance both the existing and future fuel cycles. One thrust area is in developing enabling technologies for next generation nuclear materials management under the Materials Protection, Accounting and Control Technologies (MPACT Campaign where advanced instrumentation, analysis and assessment methods, and security approaches are being developed under a framework of Safeguards and Security by Design. An overview of the MPACT campaign's activities and recent accomplishments is presented along with future plans.

Development programs on decommissioning technology for reactors and fuel cycle facilities in Japan

International Nuclear Information System (INIS)

Fujiki, K.

1992-01-01

The Science and Technology Agency (STA) of Japan is promoting technology development for decommissioning of nuclear facilities by entrusting various research programs to concerned research organisations: JAERI, PNC and RANDEC, including first full scale reactor decommissioning of JPDR. According to the results of these programs, significant improvement on dismantling techniques, decontamination, measurement etc. has been achieved. Further development of advanced decommissioning technology has been started in order to achieve reduction of duration of decommissioning work and occupational exposures in consideration of the decommissioning of reactors and fuel cycle facilities. (author) 5 refs.; 7 figs.; 1 tab

Definition study for variable cycle engine testbed engine and associated test program

Science.gov (United States)

Vdoviak, J. W.

1978-01-01

The product/study double bypass variable cycle engine (VCE) was updated to incorporate recent improvements. The effect of these improvements on mission range and noise levels was determined. This engine design was then compared with current existing high-technology core engines in order to define a subscale testbed configuration that simulated many of the critical technology features of the product/study VCE. Detailed preliminary program plans were then developed for the design, fabrication, and static test of the selected testbed engine configuration. These plans included estimated costs and schedules for the detail design, fabrication and test of the testbed engine and the definition of a test program, test plan, schedule, instrumentation, and test stand requirements.

Recent developments in the nuclear fuel cycle

International Nuclear Information System (INIS)

Wunderer, A.

1984-01-01

There is a description of the present situation in each individual area of the nuclear fuel cycle. Further topics are: risk and safety factors and emissions from the fuel cycle, availability and disruptions, waste disposal and the storage of radioactive waste. (UA) [de

LIFE CYCLE OF INFORMATION SYSTEMS

Directory of Open Access Journals (Sweden)

Y. S. Sennik

2015-01-01

Full Text Available This work is a generalization of the theoretical propositions related to the life cycle of information systems. There was given the definition of the life cycle, specify which items you should include every step of the cycle. Describes the methodology division of the life cycle on the main stage, including methodology Rational Unified Process. The description of the fundamental standards in this area. Special attention was paid to the work of the basic life cycle models. It was carried out their comparative characteristics. On the basis of the theoretical propositions, it was concluded that the preferred model of the life cycle for the corporate network is a spiral model and the use of international standards in the life cycle saves a lot of effort, time and material resources.

AGRIS: Description of computer programs

International Nuclear Information System (INIS)

Schmid, H.; Schallaboeck, G.

1976-01-01

The set of computer programs used at the AGRIS (Agricultural Information System) Input Unit at the IAEA, Vienna, Austria to process the AGRIS computer-readable data is described. The processing flow is illustrated. The configuration of the IAEA's computer, a list of error messages generated by the computer, the EBCDIC code table extended for AGRIS and INIS, the AGRIS-6 bit code, the work sheet format, and job control listings are included as appendixes. The programs are written for an IBM 370, model 145, operating system OS or VS, and require a 130K partition. The programming languages are PL/1 (F-compiler) and Assembler

Major weapon system environmental life-cycle cost estimating for Conservation, Cleanup, Compliance and Pollution Prevention (C3P2)

Science.gov (United States)

Hammond, Wesley; Thurston, Marland; Hood, Christopher

1995-01-01

The Titan 4 Space Launch Vehicle Program is one of many major weapon system programs that have modified acquisition plans and operational procedures to meet new, stringent environmental rules and regulations. The Environmental Protection Agency (EPA) and the Department of Defense (DOD) mandate to reduce the use of ozone depleting chemicals (ODC's) is just one of the regulatory changes that has affected the program. In the last few years, public environmental awareness, coupled with stricter environmental regulations, has created the need for DOD to produce environmental life-cycle cost estimates (ELCCE) for every major weapon system acquisition program. The environmental impact of the weapon system must be assessed and budgeted, considering all costs, from cradle to grave. The Office of the Secretary of Defense (OSD) has proposed that organizations consider Conservation, Cleanup, Compliance and Pollution Prevention (C(sup 3)P(sup 2)) issues associated with each acquisition program to assess life-cycle impacts and costs. The Air Force selected the Titan 4 system as the pilot program for estimating life-cycle environmental costs. The estimating task required participants to develop an ELCCE methodology, collect data to test the methodology and produce a credible cost estimate within the DOD C(sup 3)P(sup 2) definition. The estimating methodology included using the Program Office weapon system description and work breakdown structure together with operational site and manufacturing plant visits to identify environmental cost drivers. The results of the Titan IV ELCCE process are discussed and expanded to demonstrate how they can be applied to satisfy any life-cycle environmental cost estimating requirement.

U. S. Fuel Cycle Technologies R and D Program for Next Generation Nuclear Materials Management

International Nuclear Information System (INIS)

Miller, M. C.; Vega, D. A.

2013-01-01

The U. S. Department of Energy's Fuel Cycle Technologies R and D program under the Office of Nuclear Energy is working to advance technologies to enhance both the existing and future fuel cycles. One thrust area is in developing enabling technologies for next generation nuclear materials management under the Materials Protection, Accounting and Control Technologies (MPACT) Campaign where advanced instrumentation, analysis and assessment methods, and security approaches are being developed under a framework of Safeguards and Security by Design. An overview of the MPACT campaign's activities and recent accomplishments is presented along with future plans

Description of a medical writing rotation for a postgraduate pharmacy residency program.

Science.gov (United States)

Brown, Jamie N; Tiemann, Kelsey A; Ostroff, Jared L

2014-04-01

To provide a description of a pharmacy residency rotation dedicated to medical writing developed at a tertiary care academic medical center. Contribution to the medical literature is an important component of professional pharmacy practice, and there are many benefits seen by practitioners actively involved in scholarly activities. Residency programs have an opportunity to expand beyond the standard roles of postgraduate pharmacist training but rarely is there formal instruction on medical writing skills or are scholarship opportunities provided to residents. In order to address this deficiency, a residency program may consider the implementation of a formal Medical Writing rotation. This rotation is designed to introduce the resident to medical writing through active discussion on medical writing foundational topics, engage the resident in a collaborative review of a manuscript submitted to a peer-reviewed professional journal, and support the resident in the design and composition of manuscript of publishable quality. A structured Medical Writing rotation during a pharmacy resident's training can help develop the skills necessary to promote scholarly activities and foster resident interest in future pursuit of professional medical writing.

NRC/RSR Data Bank Program description

International Nuclear Information System (INIS)

Bankert, S.F.

1979-01-01

The United States Nuclear Regulatory Commission (NRC) has established the NRC/Reactor Safety Research (RSR) Data Bank Program to collect, store, and make available data from the many domestic and foreign water reactor safety research programs. Local direction of the program is provided by EG and G Idaho, Inc., at Idaho National Engineering Laboratory. The NRC/RSR Data Bank Program provides a central computer storage mechanism and access software for data to be used by code development and assessment groups in meeting the code and correlation needs of the nuclear industry. The administrative portion of the program provides data entry, documentation, and training and advisory services to users and the NRC. The NRC/RSR Data Bank Program and the capabilities of the data access software are described

Characteristics of fuel cycle waste

International Nuclear Information System (INIS)

Aquilina, C.A.; Everette, S.E.

1982-01-01

The Low-Level Waste Management System started in 1979 to describe and model the existing commercial low-level waste management system. The system description produced is based on the identification of the different elements making up both the fuel and non-fuel cycle and their relationships to each other. A systems model based on the system description can accurately reflect the flow of low-level waste from generator to disposal site and is only limited by the reliability of the information it uses. For both the fuel cycle and non-fuel cycle large quantities of information is required in order to allow the system to operate at its full potential. Work is ongoing to collect this information. Significant progress is being made in the fuel cycle area primarily because the majority of fuel cycle low-level radioactive waste is produced by commercial power reactor plant operations. The Low-Level Waste Management system is only beginning to derive the benefits to be obtained from an accurate low-level waste management information system. As data is verified and analyzed, results on a national as well as individual organization level will be gained. Comparisons to previous studies will be made. Accurate projections of waste volumes and activities to be produced, projected impacts of waste streams of treatment or management changes are only examples of information to be produced. 1 figure, 1 table

A new semidefinite programming relaxation for cycles in binary matroids and cuts in graphs

NARCIS (Netherlands)

Gouveia, J.; Laurent, M.; Parrilo, P.; Thomas, R.

2012-01-01

The theta bodies of a polynomial ideal are a series of semidefinite programming relaxations of the convex hull of the real variety of the ideal. In this paper we construct the theta bodies of the vanishing ideal of cycles in a binary matroid. Applied to cuts in graphs, this yields a new hierarchy of

Not all counterclockwise thermodynamic cycles are refrigerators

Science.gov (United States)

Dickerson, R. H.; Mottmann, J.

2016-06-01

Clockwise cycles on PV diagrams always represent heat engines. It is therefore tempting to assume that counterclockwise cycles always represent refrigerators. This common assumption is incorrect: most counterclockwise cycles cannot be refrigerators. This surprising result is explored here for quasi-static ideal gas cycles, and the necessary conditions for refrigeration cycles are clarified. Three logically self-consistent criteria can be used to determine if a counterclockwise cycle is a refrigerator. The most fundamental test compares the counterclockwise cycle with a correctly determined corresponding Carnot cycle. Other criteria we employ include a widely accepted description of the functional behavior of refrigerators, and a corollary to the second law that limits a refrigerator's coefficient of performance.

Compatibility of accounting information systems (AISs with activities in production cycle

Directory of Open Access Journals (Sweden)

Farnaz Vali Moghaddam Zanjani

2013-01-01

Full Text Available The intricacies of economic activities and growing increase in competition have made commercial units with the duty of production and financial data processing, orienting themselves with production cycle. This is considered as the heart of organization such that they could be more effective in decision-making. The method adopted in this research is descriptive – survey and it attempts to attain the objectives the researchers based on four independent variables including Production design, Programming, production operations and cost accounting. To test the hypotheses, the study adopts one sample T test method and to investigate uniformity of effects of each variable, Kruscal-Wallis test is employed. The results obtained from the tests indicate that AISs are not compatible with production cycle, where, in turn, has led to rejection of modern costing systems such as activity based costing (ABC.

Assessment Report Sandia National Laboratories Fuel Cycle Technologies Quality Assurance Evaluation of FY15 SNL FCT M2 Milestone Deliverables

International Nuclear Information System (INIS)

Appel, Gordon John

2016-01-01

Sandia National Laboratories (SNL) Fuel Cycle Technologies (FCT) program activities are conducted in accordance with FCT Quality Assurance Program Document (FCT-QAPD) requirements. The FCT-QAPD interfaces with SNL approved Quality Assurance Program Description (SNL-QAPD) as explained in the Sandia National Laboratories QA Program Interface Document for FCT Activities (Interface Document). This plan describes SNL's FY16 assessment of SNL's FY15 FCT M2 milestone deliverable's compliance with program QA requirements, including SNL R&A requirements. The assessment is intended to confirm that SNL's FY15 milestone deliverables contain the appropriate authenticated review documentation and that there is a copy marked with SNL R&A numbers.

Assessment Report Sandia National Laboratories Fuel Cycle Technologies Quality Assurance Evaluation of FY15 SNL FCT M2 Milestone Deliverables

Energy Technology Data Exchange (ETDEWEB)

Appel, Gordon John [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2016-05-01

Sandia National Laboratories (SNL) Fuel Cycle Technologies (FCT) program activities are conducted in accordance with FCT Quality Assurance Program Document (FCT-QAPD) requirements. The FCT-QAPD interfaces with SNL approved Quality Assurance Program Description (SNL-QAPD) as explained in the Sandia National Laboratories QA Program Interface Document for FCT Activities (Interface Document). This plan describes SNL's FY16 assessment of SNL's FY15 FCT M2 milestone deliverable's compliance with program QA requirements, including SNL R&A requirements. The assessment is intended to confirm that SNL's FY15 milestone deliverables contain the appropriate authenticated review documentation and that there is a copy marked with SNL R&A numbers.

Survey of the nuclear fuel cycle

International Nuclear Information System (INIS)

Zech, H.J.; Pickert, F.K.

1975-01-01

A brief outline of the technical aspects of the fuel cycle, starting from the mining of uranium up to fuel element fabrication, is followed by a more detailed description of the management of the outer fuel cycle. This includes the system of contracts and their reciprocal technical and chronological interdepence, as well as financial aspects, market conditions and trends. (RB) [de

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

Energy Technology Data Exchange (ETDEWEB)

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

1984-07-01

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

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

International Nuclear Information System (INIS)

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

1984-07-01

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

International nuclear fuel cycle fact book. Revision 6

International Nuclear Information System (INIS)

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

1986-01-01

The International Fuel Cycle Fact Book has been compiled in an effort to provide (1) an overview of worldwide nuclear power and fuel cycle programs and (2) current data concerning fuel cycle and waste management facilities, R and D programs and key personnel. Additional information on each country's program is available in the International Source Book: Nuclear Fuel Cycle Research and Development, PNL-2478, Rev. 2

Nuclear-fuel-cycle education: Module 1. Nuclear fuel cycle overview

International Nuclear Information System (INIS)

Eckhoff, N.D.

1981-07-01

This educational module is an overview of the nuclear-fule-cycle. The overview covers nuclear energy resources, the present and future US nuclear industry, the industry view of nuclear power, the International Nuclear Fuel Cycle Evaluation program, the Union of Concerned Scientists view of the nuclear-fuel-cycle, an analysis of this viewpoint, resource requirements for a model light water reactor, and world nuclear power considerations

The diffusion of the distance Entomology Master's Degree Program at the University of Nebraska Lincoln: A descriptive case study

Science.gov (United States)

Hubbell, Jody M.

This study explored three selected phases of Rogers' (1995) Diffusion of Innovations Theory to examine the diffusion process of the distance Entomology Master's Degree program at the University of Nebraska, Lincoln. A qualitative descriptive case study approach incorporated semi-structured interviews with individuals involved in one or more of the three stages: Development, Implementation, and Institutionalization. Documents and archival evidence were used to triangulate findings. This research analyzed descriptions of the program as it moved from the Development, to the Implementation, and finally, the Institutionalization stages of diffusion. Each respective stage was examined through open and axial coding. Process coding identified themes common to two or more diffusion stages, and explored the evolution of themes from one diffusion stage to the next. At a time of significant budget constraints, many departments were faced with the possibility of merger or dissolution. The Entomology Master's Degree Program evolved from being an entrepreneurial means to prevent departmental dissolution to eventually being viewed as a model for the development of similar programs across this university and other institutions of higher education. During this evolution, the program was reinvented to meet the broader needs of industry and a global student market. One finding not consistent with Rogers' model was that smaller, rather than larger, departmental size contributed to the success of the program. Within this small department, faculty members were able to share their experiences and knowledge with each other on a regular basis, which promoted greater acceptance of the distance program. How quality and rigor may be defined and measured was a key issue in each respective stage. In this specific case, quality and rigor was initially a comparison of on-campus and distance course content and then moved to program-based assessment and measures of student outcomes such as job

Summary of entire research achievements of creative engineering research program on nuclear fuel cycle

International Nuclear Information System (INIS)

Takenaka, Shingo; Ikegami, Tetsuo

2008-03-01

Creative Engineering Research Program on Nuclear Fuel Cycle (former In-house Innovative Research Encouraging Program) was implemented from FY 2001 to FY 2007 in order to support such in-house researches that create innovative new concepts and aim technical break-through. Totally 37 applications have been received and 14 research themes have been accepted and been performed in this program. As for the research achievements of the 14 research themes, first author papers accepted by scientific journals and by science councils were 47 and 32, respectively, and oral presentations at scientific societies were 99. Furthermore, interpretive articles for scientific journals, requested lectures, patents, and prize winnings were 13, 30, 8, and 3, respectively. Consequently, it can be evaluated that the research achievements resulted from this program are generally in high level and that the expectations, at the starting point of this program, to activate the innovative research activities have been accomplished. In this report, the final reports of the 14 research themes together with the outline of this program are included. (author)

Generalized fish life-cycle poplulation model and computer program

International Nuclear Information System (INIS)

DeAngelis, D.L.; Van Winkle, W.; Christensen, S.W.; Blum, S.R.; Kirk, B.L.; Rust, B.W.; Ross, C.

1978-03-01

A generalized fish life-cycle population model and computer program have been prepared to evaluate the long-term effect of changes in mortality in age class 0. The general question concerns what happens to a fishery when density-independent sources of mortality are introduced that act on age class 0, particularly entrainment and impingement at power plants. This paper discusses the model formulation and computer program, including sample results. The population model consists of a system of difference equations involving age-dependent fecundity and survival. The fecundity for each age class is assumed to be a function of both the fraction of females sexually mature and the weight of females as they enter each age class. Natural mortality for age classes 1 and older is assumed to be independent of population size. Fishing mortality is assumed to vary with the number and weight of fish available to the fishery. Age class 0 is divided into six life stages. The probability of survival for age class 0 is estimated considering both density-independent mortality (natural and power plant) and density-dependent mortality for each life stage. Two types of density-dependent mortality are included. These are cannibalism of each life stage by older age classes and intra-life-stage competition

International nuclear fuel cycle fact book. Revision 6

Energy Technology Data Exchange (ETDEWEB)

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

1986-01-01

The International Fuel Cycle Fact Book has been compiled in an effort to provide (1) an overview of worldwide nuclear power and fuel cycle programs and (2) current data concerning fuel cycle and waste management facilities, R and D programs and key personnel. Additional information on each country's program is available in the International Source Book: Nuclear Fuel Cycle Research and Development, PNL-2478, Rev. 2.

Clean Coal Technology Demonstration Program: Program Update 1998

Energy Technology Data Exchange (ETDEWEB)

Assistant Secretary for Fossil Energy

1999-03-01

Annual report on the Clean Coal Technology Demonstration Program (CCT Program). The report address the role of the CCT Program, implementation, funding and costs, accomplishments, project descriptions, legislative history, program history, environmental aspects, and project contacts. The project descriptions describe the technology and provides a brief summary of the demonstration results.

"In Our Corner": A Qualitative Descriptive Study of Patient Engagement in a Community-Based Care Coordination Program.

Science.gov (United States)

Sefcik, Justine S; Petrovsky, Darina; Streur, Megan; Toles, Mark; O'Connor, Melissa; Ulrich, Connie M; Marcantonio, Sherry; Coburn, Ken; Naylor, Mary D; Moriarty, Helene

2018-03-01

The purpose of this study was to explore participants' experience in the Health Quality Partners (HQP) Care Coordination Program that contributed to their continued engagement. Older adults with multiple chronic conditions often have limited engagement in health care services and face fragmented health care delivery. This can lead to increased risk for disability, mortality, poor quality of life, and increased health care utilization. A qualitative descriptive design with two focus groups was conducted with a total of 20 older adults enrolled in HQP's Care Coordination Program. Conventional content analysis was the analytical technique. The overarching theme resulting from the analysis was "in our corner," with subthemes "opportunities to learn and socialize" and "dedicated nurses," suggesting that these are the primary contributing factors to engagement in HQP's Care Coordination Program. Study findings suggest that nurses play an integral role in patient engagement among older adults enrolled in a care coordination program.

Quality Assurance Program Description

Energy Technology Data Exchange (ETDEWEB)

Halford, Vaughn Edward [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Ryder, Ann Marie [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2017-07-01

Effective May 1, 2017, led by a new executive leadership team, Sandia began operating within a new organizational structure. National Technology and Engineering Solutions of Sandia (Sandia’s) Quality Assurance Program (QAP) was established to assign responsibilities and authorities, define workflow policies and requirements, and provide for the performance and assessment of work.

Environmental Assessment for the Warren Station externally fired combined cycle demonstration project

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-04-01

The proposed Penelec project is one of 5 projects for potential funding under the fifth solicitation under the Clean Coal Technology program. In Penelec, two existing boilers would be replaced at Warren Station, PA; the new unit would produce 73 MW(e) in a combined cycle mode (using both gas-fired and steam turbines). The project would fill the need for a full utility-size demonstration of externally fire combined cycle (EFCC) technology as the next step toward commercialization. This environmental assessment was prepared for compliance with NEPA; its purpose is to provide sufficient basis for determining whether to prepare an environmental impact statement or to issue a finding of no significant impact. It is divided into the sections: purpose and need for proposed action; alternatives; brief description of affected environment; environmental consequences, including discussion of commercial operation beyond the demonstration period.

Univariate characterization of the German business cycle 1955-1994

OpenAIRE

Weihs, Claus; Garczarek, Ursula

2002-01-01

We present a descriptive analysis of stylized facts for the German business cycle. We demonstrate that simple ad-hoc instructions for identifying univariate rules characterizing the German business cycle 1955-1994 lead to an error rate comparable to standard multivariate methods.

Nuclear fuel cycle risk assessment: survey and computer compilation of risk-related literature. [Once-through Cycle and Plutonium Recycle

Energy Technology Data Exchange (ETDEWEB)

Yates, K.R.; Schreiber, A.M.; Rudolph, A.W.

1982-10-01

The US Nuclear Regulatory Commission has initiated the Fuel Cycle Risk Assessment Program to provide risk assessment methods for assistance in the regulatory process for nuclear fuel cycle facilities other than reactors. Both the once-through cycle and plutonium recycle are being considered. A previous report generated by this program defines and describes fuel cycle facilities, or elements, considered in the program. This report, the second from the program, describes the survey and computer compilation of fuel cycle risk-related literature. Sources of available information on the design, safety, and risk associated with the defined set of fuel cycle elements were searched and documents obtained were catalogued and characterized with respect to fuel cycle elements and specific risk/safety information. Both US and foreign surveys were conducted. Battelle's computer-based BASIS information management system was used to facilitate the establishment of the literature compilation. A complete listing of the literature compilation and several useful indexes are included. Future updates of the literature compilation will be published periodically. 760 annotated citations are included.

Reduction of uncertainties on the components of the reactivity loss per cycle, the Balzac program on Masurca

International Nuclear Information System (INIS)

D'Angelo, A.; Karouby-Cohen, N.; Palmiotti, G.; Rimpault, G.; Salvatores, M.; Soule, R.

1984-10-01

The uncertainties on the reactivity loss per cycle are mainly due to the uncertainties on the heavy isotopes component. This paper, presents an experimental program for reducing these uncertainties. This program is based on a range of fuel irradiation experiments on power reactor and a range of isotopic variations experiments in the critical facility MASURCA consisting basically of subcritical measurements, from a reference configuration and in several different spectra

Environmental Compliance and Protection Program Description Oak Ridge, Tennessee

Energy Technology Data Exchange (ETDEWEB)

Bechtel Jacobs

2009-02-26

The objective of the Environmental Compliance and Protection (EC and P) Program Description (PD) is to establish minimum environmental compliance requirements and natural resources protection goals for the Bechtel Jacobs Company LLC (BJC) Oak Ridge Environmental Management Cleanup Contract (EMCC) Contract Number DE-AC05-98OR22700-M198. This PD establishes the work practices necessary to ensure protection of the environment during the performance of EMCC work activities on the US Department of Energy's (DOE's) Oak Ridge Reservation (ORR) in Oak Ridge, Tennessee, by BJC employees and subcontractor personnel. Both BJC and subcontractor personnel are required to implement this PD. A majority of the decontamination and demolition (D and D) activities and media (e.g., soil and groundwater) remediation response actions at DOE sites on the ORR are conducted under the authority of the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). CERCLA activities are governed by individual CERCLA decision documents (e.g., Record of Decision [ROD] or Action Memorandum) and according to requirements stated in the Federal Facility Agreement for the Oak Ridge Reservation (DOE 1992). Applicable or relevant and appropriate requirements (ARARs) for the selected remedy are the requirements for environmental remediation responses (e.g., removal actions and remedial actions) conducted under CERCLA.

Clean Coal Technology Demonstration Program: Program Update 2001

Energy Technology Data Exchange (ETDEWEB)

Assistant Secretary for Fossil Energy

2002-07-30

Annual report on the Clean Coal Technology Demonstration Program (CCT Program). The report address the role of the CCT Program, implementation, funding and costs, accomplishments, project descriptions, legislative history, program history, environmental aspects, and project contacts. The project descriptions describe the technology and provides a brief summary of the demonstration results. Also includes Power Plant Improvement Initiative Projects.

Plutonium immobilization project development and testing technical project office quality assurance program description

International Nuclear Information System (INIS)

Gould, T.H.; MacLean, L.M.; Ziemba, J.M.

1999-01-01

The Plutonium Immobilization Project (PIP) is one of several fissile materials disposition projects managed by the Department of Energy (DOE) Office of Fissile Materials Disposition (OFMD). The PIP is expected to evolve from the current Development and Testing (D and T) effort, to design, to construction, and finally to operations. Overall management and technical management of the D and T effort resides at the Lead Laboratory, Lawrence Livermore National Laboratory (LLNL), through the LLNL Manager, Fissile Materials Disposition Program (FMDP). Day to day project activities are managed by the D and T Technical Project Office (TPO), which reports to the LLNL Manager, FMDP. The D and T TPO consists of the Technical Manager, the TPO Quality Assurance (QA) Program Manager, and TPO Planning and Support Staff. This Quality Assurance Program Description (QAPD) defines the QA policies and controls that will be implemented by these TPO personnel in their management of D and T activities. This QAPD is consistent with and responsive to the Department of Energy Fissile Materials Disposition Program Quality Assurance Requirements Document (FMDP QARD). As the Project and upper level requirement's documents evolve, this QAPD will be updated as necessary to accurately define and describe the QA Program and Management of the PIP. The TPO has a policy that all development and testing activities be planned, performed and assessed in accordance with its customer's requirements, needs and expectations, and with a commitment to excellence and continuous improvement. The TPO QAPD describes implementation requirements which, when completed, will ensure that the project development and testing activities conform to the appropriate QA requirements. For the program to be effective, the TPO QA Program Manager will ensure that each site participating in D and T activities has developed a QAPD, which meets the customer's requirements, and has a designated quality leader in place. These customer

Descriptive study of external employee assistance program providers (EAP) in Japan.

Science.gov (United States)

Muto, Takashi; Haruyama, Yasuo; Higashi, Toshiaki

2012-01-01

The mental health problems of employees have become a major occupational health issue in Japan. External employee assistance program providers (EAP) have become important in mental health care for workers, but their activities are poorly documented. This descriptive study was undertaken to clarify the status and future tasks of EAP in Japan. The subjects were all EAP (n=27) registered in the Japanese Chapter of Employee Assistance Professionals Association. The questionnaire survey was conducted in January 2007. We received 13 replies, a response rate of 54.2%. Most EAP provided seminars, stress checks, stress management, counseling, and support for a return to work. The number of EAP contracted with small-scale enterprises was small. EAP communicated infrequently with companies. To promote the use of EAP, their advertising, education and training of staff, accumulation of scientific evidence, development of an official certification system for staff, and improvement of contents of EAP services were cited.

Improving the description of metabolic networks: the TCA cycle as example

NARCIS (Netherlands)

Stobbe, Miranda D.; Houten, Sander M.; van Kampen, Antoine H. C.; Wanders, Ronald J. A.; Moerland, Perry D.

2012-01-01

To collect the ever-increasing yet scattered knowledge on metabolism, multiple pathway databases like the Kyoto Encyclopedia of Genes and Genomes have been created. A complete and accurate description of the metabolic network for human and other organisms is essential to foster new biological

Solid Waste Program technical baseline description

Energy Technology Data Exchange (ETDEWEB)

Carlson, A.B.

1994-07-01

The system engineering approach has been taken to describe the technical baseline under which the Solid Waste Program is currently operating. The document contains a mission analysis, function analysis, system definition, documentation requirements, facility and project bases, and uncertainties facing the program.

An Overview of the NASA Energy and Water cycle Study (NEWS) and the North American Water Program (NAWP)

Science.gov (United States)

Houser, P. R.

2014-12-01

NEWS: 10 years ago, NASA established the NASA Energy and Water-cycle Study (NEWS), whose long-term grand challenge is to document and enable improved, observationally based, predictions of water and energy cycle consequences of Earth system variability and change. The NEWS program builds upon existing NASA-supported basic research in atmospheric physics and dynamics, radiation, climate modeling, and terrestrial hydrology. While these NASA programs fund research activities that address individual aspects of the global energy and water cycles, they are not specifically designed to generate a coordinated result. NEWS developed the first coordinated attempt to describe the complete global energy and water cycle using existing and forthcoming satellite and ground based observations, and laying the foundation for essential NEWS developments in model representations of atmospheric energy and water exchange processes. This comprehensive energy and water data analysis program exploited crucial datasets, some requiring complete re-processing, and new satellite measurements. NAWP: Dramatically changing climates has had an indelible impact on North America's water crisis. To decisively address these challenges, we recommend that NAWP coalesce an interdisciplinary, international and interagency effort to make significant contributions to continental- to decision-scale hydroclimate science and solutions. By entraining, integrating and coordinating the vast array of interdisciplinary observational and prediction resources available, NAWP will significantly advance skill in predicting, assessing and managing variability and changes in North American water resources. We adopt three challenges to organize NAWP efforts. The first deals with developing a scientific basis and tools for mitigating and adapting to changes in the water supply-demand balance. The second challenge is benchmarking; to use incomplete and uncertain observations to assess water storage and quality dynamics, and

Rock Visualization System. Technical description (RVS v.3.5)

Energy Technology Data Exchange (ETDEWEB)

Curtis, P.; Elfstroem, M.; Markstroem, I. [FB Engineering, Goeteborg (Sweden)

2004-03-01

The Rock Visualization System (RVS) has been developed by SKB for use in visualizing geological and engineering data in 3D. The purpose of this report is to provide a technical description of RVS aimed at potential program users and interested parties as well as fulfilling the function of a more general RVS reference that can be cited when writing other technical reports. It is a description of RVS version 3.5. Updated versions of this report or addenda will be made available following further development of RVS and the release of subsequent versions of the program. The report covers the following main items: Technical description of the program with illustrations and examples; Limitations of the program and of functionality. For most RVS functions step-by-step tutorials are available describing how a particular function can be used to carryout a specific task. A complete set of updated tutorials is issued with each new version release of the RVS program. However, the tutorials do not cover all the possible uses of all the individual functions but rather give an overall view of their functionality. A detailed description of every RVS function and how it can be used is included in the RVS online Help system.

Rock Visualization System. Technical description (RVS v.3.5)

International Nuclear Information System (INIS)

Curtis, P.; Elfstroem, M.; Markstroem, I.

2004-03-01

The Rock Visualization System (RVS) has been developed by SKB for use in visualizing geological and engineering data in 3D. The purpose of this report is to provide a technical description of RVS aimed at potential program users and interested parties as well as fulfilling the function of a more general RVS reference that can be cited when writing other technical reports. It is a description of RVS version 3.5. Updated versions of this report or addenda will be made available following further development of RVS and the release of subsequent versions of the program. The report covers the following main items: Technical description of the program with illustrations and examples; Limitations of the program and of functionality. For most RVS functions step-by-step tutorials are available describing how a particular function can be used to carryout a specific task. A complete set of updated tutorials is issued with each new version release of the RVS program. However, the tutorials do not cover all the possible uses of all the individual functions but rather give an overall view of their functionality. A detailed description of every RVS function and how it can be used is included in the RVS online Help system

Health and environmental aspects of nuclear fuel cycle facilities

International Nuclear Information System (INIS)

1996-11-01

The purpose of the present publication is to give a generic description of health and environmental aspects of nuclear fuel cycle facilities. Primarily the report is meant to stand alone; however, because of the content of the publication and in the context of the DECADES project, it may serve as a means of introducing specialists in other fuel cycles to the nuclear fuel cycle. Refs, figs, tabs

Whi7 is an unstable cell-cycle repressor of the Start transcriptional program.

Science.gov (United States)

Gomar-Alba, Mercè; Méndez, Ester; Quilis, Inma; Bañó, M Carmen; Igual, J Carlos

2017-08-24

Start is the main decision point in eukaryotic cell cycle in which cells commit to a new round of cell division. It involves the irreversible activation of a transcriptional program by G1 CDK-cyclin complexes through the inactivation of Start transcriptional repressors, Whi5 in yeast or Rb in mammals. Here we provide novel keys of how Whi7, a protein related at sequence level to Whi5, represses Start. Whi7 is an unstable protein, degraded by the SCF Grr1 ubiquitin-ligase, whose stability is cell cycle regulated by CDK1 phosphorylation. Importantly, Whi7 associates to G1/S gene promoters in late G1 acting as a repressor of SBF-dependent transcription. Our results demonstrate that Whi7 is a genuine paralog of Whi5. In fact, both proteins collaborate in Start repression bringing to light that yeast cells, as occurs in mammalian cells, rely on the combined action of multiple transcriptional repressors to block Start transition.The commitment of cells to a new cycle of division involves inactivation of the Start transcriptional repressor Whi5. Here the authors show that the sequence related protein Whi7 associates to G1/S gene promoters in late G1 and collaborates with Whi5 in Start repression.

'Only systems thinking can improve family planning program in Pakistan': A descriptive qualitative study.

Science.gov (United States)

Zafar, Saira; Shaikh, Babar Tasneem

2014-12-01

Family Planning (FP) program in Pakistan has been struggling to achieve the desired indicators. Despite a well-timed initiation of the program in late 50s, fertility decline has been sparingly slow. As a result, rapid population growth is impeding economic development in the country. A high population growth rate, the current fertility rate, a stagnant contraceptive prevalence rate and high unmet need remain challenging targets for population policies and FP programs. To accelerate the pace of FP programs and targets concerned, it is imperative to develop and adopt a holistic approach and strategy for plugging the gaps in various components of the health system: service delivery, information systems, drugs-supplies, technology and logistics, Human Resources (HRs), financing, and governance. Hence, World Health Organization (WHO) health systems building blocks present a practical framework for overall health system strengthening. This descriptive qualitative study, through 23 in-depth interviews, explored the factors related to the health system, and those responsible for a disappointing FP program in Pakistan. Provincial representatives from Population Welfare and Health departments, donor agencies and non-governmental organizations involved with FP programs were included in the study to document the perspective of all stakeholders. Content analysis was done manually to generate nodes, sub-nodes and themes. Performance of FP programs is not satisfactory as shown by the indicators, and these programs have not been able to deliver the desired outcomes. Interviewees agreed that inadequate prioritization given to the FP program by successive governments has led to this situation. There are issues with all health system areas, including governance, strategies, funding, financial management, service delivery systems, HRs, technology and logistic systems, and Management Information System (MIS); these have encumbered the pace of success of the program. All stakeholders

User's instructions for ORCENT II: a digital computer program for the analysis of steam turbine cycles supplied by light-water-cooled reactors

International Nuclear Information System (INIS)

Fuller, L.C.

1979-02-01

The ORCENT-II digital computer program will perform calculations at valves-wide-open design conditions, maximum guaranteed rating conditions, and an approximation of part-load conditions for steam turbine cycles supplied with throttle steam characteristic of contemporary light-water reactors. Turbine performance calculations are based on a method published by the General Electric Company. Output includes all information normally shown on a turbine-cycle heat balance diagram. The program is written in FORTRAN IV for the IBM System 360 digital computers at the Oak Ridge National Laboratory

Business cycle indexes : does a heap of data help?

NARCIS (Netherlands)

Inklaar, Robert; Jacobs, Jan; Romp, Ward

2003-01-01

Business cycle indexes are used to get a timely and frequent description of the state of the economy and its likely development in the near future. This paper discusses two methods for constructing business cycle indexes, the traditional NBER method and a recently developed dynamic factor model, and

Nuclear Systems Enhanced Performance Program, Maintenance Cycle Extension in Advanced Light Water Reactor Design

Energy Technology Data Exchange (ETDEWEB)

Professor Neill Todreas

2001-10-01

A renewed interest in new nuclear power generation in the US has spurred interest in developing advanced reactors with features which will address the public's concerns regarding nuclear generation. However, it is economic performance which will dictate whether any new orders for these plants will materialize. Economic performance is, to a great extent, improved by maximizing the time that the plant is on-line generating electricity relative to the time spent off-line conducting maintenance and refueling. Indeed, the strategy for the advanced light water reactor plant IRIS (International Reactor, Innovative and Secure) is to utilize an eight year operating cycle. This report describes a formalized strategy to address, during the design phase, the maintenance-related barriers to an extended operating cycle. The top-level objective of this investigation was to develop a methodology for injecting component and system maintainability issues into the reactor plant design process to overcome these barriers. A primary goal was to demonstrate the applicability and utility of the methodology in the context of the IRIS design. The first step in meeting the top-level objective was to determine the types of operating cycle length barriers that the IRIS design team is likely to face. Evaluation of previously identified regulatory and investment protection surveillance program barriers preventing a candidate operating PWR from achieving an extended (48 month) cycle was conducted in the context of the IRIS design. From this analysis, 54 known IRIS operating cycle length barriers were identified. The resolution methodology was applied to each of these barriers to generate design solution alternatives for consideration in the IRIS design. The methodology developed has been demonstrated to narrow the design space to feasible design solutions which enable a desired operating cycle length, yet is general enough to have broad applicability. Feedback from the IRIS design team

Cycle life test. Evaluation program for secondary spacecraft cells. [performance tests on silver zinc batteries, silver cadmium batteries, and nickel cadmium batteries

Science.gov (United States)

Harkness, J. D.

1976-01-01

Considerable research is being done to find more efficient and reliable means of starting electrical energy for orbiting satellites. Rechargeable cells offer one such means. A test program is described which has been established in order to further the evaluation of certain types of cells and to obtain performance and failure data as an aid to their continued improvement. The purpose of the program is to determine the cycling performance capabilities of packs of cells under different load and temperature conditions. The various kinds of cells tested were nickel-cadmium, silver-cadmium, and silver-zinc sealed cells. A summary of the results of the life cycling program is given in this report.

GGP Program Description, 2006-2011 | IDRC - International ...

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

2010-12-22

Dec 22, 2010 ... This document explains the context and orientation of the IDRC's Globalization, Growth and Poverty (GGP) program initiative for the 2006-11 period, detailing the GGP program's objectives, research areas, cross-cutting themes, and programming approach.Download the PDF : Globalization, Growth and ...

Alternative fuel cycles

International Nuclear Information System (INIS)

Penn, W.J.

1979-05-01

Uranium resource utilization and economic considerations provide incentives to study alternative fuel cycles as future options to the PHWR natural uranium cycle. Preliminary studies to define the most favourable alternatives and their possible introduction dates are discussed. The important and uncertain components which influence option selection are reviewed, including nuclear capacity growth, uranium availability and demand, economic potential, and required technological developments. Finally, a summary of Ontario Hydro's program to further assess cycle selection and define development needs is given. (auth)

Alternatives for managing wastes from reactors and post-fission operations in the LWR fuel cycle. Volume 1. Summary: alternatives for the back of the LWR fuel cycle types and properties of LWR fuel cycle wastes projections of waste quantities; selected glossary

International Nuclear Information System (INIS)

1976-05-01

Volume I of the five-volume report contains executive and technical summaries of the entire report, background information of the LWR fuel cycle alternatives, descriptions of waste types, and projections of waste quantities. Overview characterizations of alternative LWR fuel cycle modes are also included

The Role of Extension Nutrition Education in Student Achievement of Nutrition Standards in Grades K-3: A Descriptive Evaluation of a School-Based Program

Science.gov (United States)

Arnold, Mary E.; Schreiber, Debera

2012-01-01

This article reports the results of a descriptive evaluation of the impact of an in-school Extension nutrition education program in a small, very rural county. The evaluation focused on understanding the nature of the role the Extension educator plays in delivering nutrition education, the impact of the program on student learning and achievement…

IMPLEMENTING CONCEPT MAPPING TECHNIQUE TO IMPROVE STUDENTS’ DESCRIPTIVE WRITING ABILITY

Directory of Open Access Journals (Sweden)

Rubiyah Rubiyah Rubiyah

2018-04-01

Full Text Available This Classroom Action Research aimed at investigating the implementation of Concept Mapping Technique to improve students’ descriptive writing ability. The research was conducted in two cycles at SMP Negeri 21 Samarinda, with 37 seventh grade students participating. In this research, there was one teacher- researcher who implemented the technique and there were two collaborators who did the observation. The data were collected both quantitatively and qualitatively by using writing assessment, interview guide, observation sheets and field notes. The findings showed that: 1 there was an improvement in the students’ descriptive writing average scores at the end of the second research cycle; 2 the implementation of the concept mapping technique was done properly by the teacher- researcher; 3 the concept mapping technique delivered through collaborative working improved the participation of the students in the teaching and learning process. Since all the criteria of success in this research were fulfilled by the end of the second cycle, it could be concluded that this classroom action research was successfully implemented and the technique proposed could very well improve the skills being targeted.

Clean Coal Technology Programs: Program Update 2003 (Volume 1)

Energy Technology Data Exchange (ETDEWEB)

Assistant Secretary for Fossil Energy

2003-12-01

Annual report on the Clean Coal Technology Demonstration Program (CCTDP), Power Plant Improvement Initiative (PPII), and Clean Coal Power Initiative (CCPI). The report addresses the roles of the programs, implementation, funding and costs, project descriptions, legislative history, program history, environmental aspects, and project contacts. The project descriptions describe the technology and provides a brief summary of the demonstration results.

Gulf Coast geopressured-geothermal program summary report compilation. Volume 2-A: Resource description, program history, wells tested, university and company based research, site restoration

Energy Technology Data Exchange (ETDEWEB)

John, C.J.; Maciasz, G.; Harder, B.J.

1998-06-01

The US Department of Energy established a geopressured-geothermal energy program in the mid 1970`s as one response to America`s need to develop alternate energy resources in view of the increasing dependence on imported fossil fuel energy. This program continued for 17 years and approximately two hundred million dollars were expended for various types of research and well testing to thoroughly investigate this alternative energy source. This volume describes the following studies: Geopressured-geothermal resource description; Resource origin and sediment type; Gulf Coast resource extent; Resource estimates; Project history; Authorizing legislation; Program objectives; Perceived constraints; Program activities and structure; Well testing; Program management; Program cost summary; Funding history; Resource characterization; Wells of opportunity; Edna Delcambre No. 1 well; Edna Delcambre well recompletion; Fairfax Foster Sutter No. 2 well; Beulah Simon No. 2 well; P.E. Girouard No. 1 well; Prairie Canal No. 1 well; Crown Zellerbach No. 2 well; Alice C. Plantation No. 2 well; Tenneco Fee N No. 1 well; Pauline Kraft No. 1 well; Saldana well No. 2; G.M. Koelemay well No. 1; Willis Hulin No. 1 well; Investigations of other wells of opportunity; Clovis A. Kennedy No. 1 well; Watkins-Miller No. 1 well; Lucien J. Richard et al No. 1 well; and the C and K-Frank A. Godchaux, III, well No. 1.

Reactor safety research program. A description of current and planned reactor safety research sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research

International Nuclear Information System (INIS)

1975-06-01

The reactor safety research program, sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, is described in terms of its program objectives, current status, and future plans. Elements of safety research work applicable to water reactors, fast reactors, and gas cooled reactors are presented together with brief descriptions of current and planned test facilities. (U.S.)

Status of IFR fuel cycle demonstration

International Nuclear Information System (INIS)

Lineberry, M.J.; Phipps, R.D.; McFarlane, H.F.

1993-01-01

The next major step in Argonne's Integral Fast Reactor (IFR) Program is demonstration of the pyroprocess fuel cycle, in conjunction with continued operation of EBR-II. The Fuel Cycle Facility (FCF) is being readied for this mission. This paper will address the status of facility systems and process equipment, the initial startup experience, and plans for the demonstration program

Hanford Waste Vitrification Plant Quality Assurance Program description for high-level waste form development and qualification. Revision 3, Part 2

Energy Technology Data Exchange (ETDEWEB)

1993-08-01

The Hanford Waste Vitrification Plant Project has been established to convert the high-level radioactive waste associated with nuclear defense production at the Hanford Site into a waste form suitable for disposal in a deep geologic repository. The Hanford Waste Vitrification Plant will mix processed radioactive waste with borosilicate material, then heat the mixture to its melting point (vitrification) to forin a glass-like substance that traps the radionuclides in the glass matrix upon cooling. The Hanford Waste Vitrification Plant Quality Assurance Program has been established to support the mission of the Hanford Waste Vitrification Plant. This Quality Assurance Program Description has been written to document the Hanford Waste Vitrification Plant Quality Assurance Program.

System description of the Basic MRS System for the FY 1990 Systems Integration Program studies

International Nuclear Information System (INIS)

McKee, R.W.; Young, J.R.; Konzek, G.J.

1991-07-01

This document provides both functional and physical descriptions of a conceptual high-level waste management system defined as a Basic MRS System. Its purpose is to provide a basis for required system computer modeling and system studies initiated in FY 1990 under the Systems Integration Program of the Office of Civilian Radioactive Waste Management Office (OCRWM). Two specific systems studies initiated in FY 1990, the Reference System Performance Evaluation and the Aggregate Receipt Rate Study, utilize the information in this document. The Basic MRS System is the current OCRWM reference high-level radioactive wastes repository system concept. It is designed to accept 3000 MTU per year of spent fuel and 400 equivalent MTU per year of high-level wastes. The Basic MRS System includes a storage-only MRS that provides for a limited amount of commercial spent fuel storage capacity prior to acceptance by the geologic repository for disposal. This document contains both functional descriptions of the processes in the waste management system and physical descriptions of the equipment and facilities necessary for performance of those processes. The basic MRS system contains all system components, from the waste storage facilities of the waste generators to the underground facilities for final disposal of the wastes. The major facilities in the system are the waste generator waste storage facilities, an MRS facility that provides interim storage wastes accepted from the waste generators, a repository facility that packages the wastes and then emplaces them in the geologic repository, and the transportation equipment and facilities for transporting the waste between these major facilities

Rethink, Reform, Reenter: An Entrepreneurial Approach to Prison Programming.

Science.gov (United States)

Keena, Linda; Simmons, Chris

2015-07-01

The purpose of this article was to present a description and first-stage evaluation of the impact of the Ice House Entrepreneurship Program on the learning experience of participating prerelease inmates at a Mississippi maximum-security prison and their perception of the transfer of skills learned in program into securing employment upon reentry. The Ice House Entrepreneurship Program is a 12-week program facilitated by volunteer university professors to inmates in a prerelease unit of a maximum-security prison in Mississippi. Participants' perspectives were examined through content analysis of inmates' answers to program Reflection and Response Assignments and interviews. The analyses were conducted according to the constant comparative method. Findings reveal the emergent of eight life-lessons and suggest that this is a promising approach to prison programming for prerelease inmates. This study discusses three approaches to better prepare inmates for a mindset change. The rethink, reform, and reenter approaches help break the traditional cycle of release, reoffend, and return. © The Author(s) 2014.

Life cycle cost optimization of biofuel supply chains under uncertainties based on interval linear programming.

Science.gov (United States)

Ren, Jingzheng; Dong, Liang; Sun, Lu; Goodsite, Michael Evan; Tan, Shiyu; Dong, Lichun

2015-01-01

The aim of this work was to develop a model for optimizing the life cycle cost of biofuel supply chain under uncertainties. Multiple agriculture zones, multiple transportation modes for the transport of grain and biofuel, multiple biofuel plants, and multiple market centers were considered in this model, and the price of the resources, the yield of grain and the market demands were regarded as interval numbers instead of constants. An interval linear programming was developed, and a method for solving interval linear programming was presented. An illustrative case was studied by the proposed model, and the results showed that the proposed model is feasible for designing biofuel supply chain under uncertainties. Copyright © 2015 Elsevier Ltd. All rights reserved.

Nonproliferation norms in civilian nuclear fuel cycle

International Nuclear Information System (INIS)

Kawata, Tomio

2005-01-01

For sustainable use of nuclear energy in large scale, it seems inevitable to choose a closed cycle option. One of the important questions is, then, whether we can really achieve the compatibility between civilian nuclear fuel cycle and nonproliferation norms. In this aspect, Japan is very unique because she is now only one country with full-scope nuclear fuel cycle program as a non-nuclear weapon state in NPT regime. In June 2004 in the midst of heightened proliferation concerns in NPT regime, the IAEA Board of Governors concluded that, for Japanese nuclear energy program, non-diversion of declared nuclear material and the absence of undeclared nuclear material and activities were verified through the inspections and examinations under Comprehensive Safeguards and the Additional Protocol. Based on this conclusion, the IAEA announced the implementation of Integrated Safeguards in Japan in September 2004. This paper reviews how Japan has succeeded in becoming the first country with full-scope nuclear fuel cycle program to qualify for integrated Safeguards, and identifies five key elements that have made this achievement happen: (1) Obvious need of nuclear fuel cycle program, (2) Country's clear intention for renunciation of nuclear armament, (3) Transparency of national nuclear energy program, (4) Record of excellent compliance with nonproliferation obligations for many decades, and (5) Numerous proactive efforts. These five key elements will constitute a kind of an acceptance model for civilian nuclear fuel cycle in NNWS, and may become the basis for building 'Nonproliferation Culture'. (author)

Monitored Retrievable Storage conceptual system study: open cycle vault

International Nuclear Information System (INIS)

Smith, R.I.

1983-11-01

This report provides a modified description of the Open Cycle Vault Storage Concept which meets a specified set of requirements; an estimate of the costs of construction, operation, and decommissioning of the concepts; the costs required to expand the facility throughput and storage capability; and the life-cycle costs of the facility. 11 references, 23 figures, 35 tables

An adaptive maneuvering logic computer program for the simulation of one-on-one air-to-air combat. Volume 1: General description

Science.gov (United States)

Burgin, G. H.; Fogel, L. J.; Phelps, J. P.

1975-01-01

A technique for computer simulation of air combat is described. Volume 1 decribes the computer program and its development in general terms. Two versions of the program exist. Both incorporate a logic for selecting and executing air combat maneuvers with performance models of specific fighter aircraft. In the batch processing version the flight paths of two aircraft engaged in interactive aerial combat and controlled by the same logic are computed. The realtime version permits human pilots to fly air-to-air combat against the adaptive maneuvering logic (AML) in Langley Differential Maneuvering Simulator (DMS). Volume 2 consists of a detailed description of the computer programs.

Capacity building in rural Guatemala by implementing a solid waste management program

International Nuclear Information System (INIS)

Zarate, M.A.; Slotnick, J.; Ramos, M.

2008-01-01

The development and implementation of a solid waste management program served to build local capacity in San Mateo Ixtatan between 2002 and 2003 as part of a public health action plan. The program was developed and implemented in two phases: (1) the identification and education of a working team from the community; and (2) the completion of a solid waste classification and quantification study. Social capital and the water cycle were two public health approaches utilized to build a sustainable program. The activities accomplished gained support from the community and municipal authorities. A description of the tasks completed and findings of the solid waste classification and quantification performed by a local working group are presented in this paper

‘Only Systems Thinking Can Improve Family Planning Program in Pakistan’: A Descriptive Qualitative Study

Directory of Open Access Journals (Sweden)

Saira Zafar

2014-12-01

Full Text Available Background Family Planning (FP program in Pakistan has been struggling to achieve the desired indicators. Despite a well-timed initiation of the program in late 50s, fertility decline has been sparingly slow. As a result, rapid population growth is impeding economic development in the country. A high population growth rate, the current fertility rate, a stagnant contraceptive prevalence rate and high unmet need remain challenging targets for population policies and FP programs. To accelerate the pace of FP programs and targets concerned, it is imperative to develop and adopt a holistic approach and strategy for plugging the gaps in various components of the health system: service delivery, information systems, drugs-supplies, technology and logistics, Human Resources (HRs, financing, and governance. Hence, World Health Organization (WHO health systems building blocks present a practical framework for overall health system strengthening. Methods This descriptive qualitative study, through 23 in-depth interviews, explored the factors related to the health system, and those responsible for a disappointing FP program in Pakistan. Provincial representatives from Population Welfare and Health departments, donor agencies and non-governmental organizations involved with FP programs were included in the study to document the perspective of all stakeholders. Content analysis was done manually to generate nodes, sub-nodes and themes. Results Performance of FP programs is not satisfactory as shown by the indicators, and these programs have not been able to deliver the desired outcomes. Interviewees agreed that inadequate prioritization given to the FP program by successive governments has led to this situation. There are issues with all health system areas, including governance, strategies, funding, financial management, service delivery systems, HRs, technology and logistic systems, and Management Information System (MIS; these have encumbered the pace of

Advancing CANDU technology AECL's Development program

International Nuclear Information System (INIS)

Torgerson, D.F.

1997-01-01

AECL has a comprehensive product development program that is advancing all aspects of CANDU technology including fuel and fuel cycles, fuel channels, heavy water and tritium technology, safety technology, components and systems, constructability, health and environment, and control and instrumentation. The technology arising from these programs is being incorporated into the CANDU design through an evolutionary process. This evolutionary process is focused on improving economics, enhancing safety and ensuring fuel cycle flexibility to secure fuel supply for the foreseeable future. This strategic thrusts are being used by CANDU designers and researchers to set priorities and goals for AECL's development activities. The goals are part of a 25-year development program that culminates in the 'CANDU X'. The 'CANDU X' is not a specific design - it is a concept that articulates our best extrapolation of what is achievable with the CANDU design over the next 25 years, and includes the advanced features arising from the R and D and engineering to be done over that time. AECL's current product, the 700 MWe class CANDU 6 and the 900 MWe class CANDU 9, both incorporate output from the development programs as the technology become available. A brief description of each development areas is given below. The paper ends with the conclusion that AECL has a clear vision of how CANDU technology and products will evolve over the next several years, and has structured a comprehensive development program to take full advantage of the inherent characteristics of heavy water reactors. (author)

Comparative assessment of nuclear fuel cycles. Light-water reactor once-through, classical fast breeder reactor, and symbiotic fast breeder reactor cycles

International Nuclear Information System (INIS)

Hardie, R.W.; Barrett, R.J.; Freiwald, J.G.

1980-06-01

The object of the Alternative Nuclear Fuel Cycle Study is to perform comparative assessments of nuclear power systems. There are two important features of this study. First, this evaluation attempts to encompass the complete, integrated fuel cycle from mining of uranium ore to disposal of waste rather than isolated components. Second, it compares several aspects of each cycle - energy use, economics, technological status, proliferation, public safety, and commercial potential - instead of concentrating on one or two assessment areas. This report presents assessment results for three fuel cycles. These are the light-water reactor once-through cycle, the fast breeder reactor on the classical plutonium cycle, and the fast breeder reactor on a symbiotic cycle using plutonium and 233 U as fissile fuels. The report also contains a description of the methodology used in this assessment. Subsequent reports will present results for additional fuel cycles

Integration of Bilingual Emphasis Program into University Curriculum. Multiple Subjects Credential Program: Hupa, Yurok, Karuk, or Tolowa Emphasis.

Science.gov (United States)

Bennett, Ruth

A description of the American Indian Bilingual Teacher Credential Program offered by Humboldt State University (California) provides background information on the linguistic groups served by the program. Accompanying the program descriptions are lists of lower and upper division requirements, descriptions of competency exam, program schedule,…

User's instructions for ORCENT II: a digital computer program for the analysis of steam turbine cycles supplied by light-water-cooled reactors

Energy Technology Data Exchange (ETDEWEB)

Fuller, L.C.

1979-02-01

The ORCENT-II digital computer program will perform calculations at valves-wide-open design conditions, maximum guaranteed rating conditions, and an approximation of part-load conditions for steam turbine cycles supplied with throttle steam characteristic of contemporary light-water reactors. Turbine performance calculations are based on a method published by the General Electric Company. Output includes all information normally shown on a turbine-cycle heat balance diagram. The program is written in FORTRAN IV for the IBM System 360 digital computers at the Oak Ridge National Laboratory.

Cycle tourism and rail trails as examples of sustainable tourism

OpenAIRE

Macià Serra i Serra

2016-01-01

This article argues that while cycle tourism remains only a small sector within sustainable tourism, it has great growth potential and attractive characteristics for the communities that engage in it. Based on this thesis, first, a description is given of cycle tourism, its characteristics, evolution and impacts. Second, its implementation through public policies over the past two decades is analysed. Third, the way cycle tourism has developed in various countries is examined, along with w...

Promising designs of compact heat exchangers for modular HTRs using the Brayton cycle

International Nuclear Information System (INIS)

Pra, Franck; Tochon, Patrice; Mauget, Christian; Fokkens, Jan; Willemsen, Sander

2008-01-01

The presented study was carried out within the Work Package 2 'Recuperator' of the High Temperature Reactor-E European program. High Temperature gas cooled Reactor concepts with a direct cycle have become potentially interesting for the future. Theoretically, these concepts provide higher efficiency than a classical steam cycle. Within the Brayton cycle the helium/helium recuperator, required to achieve the high efficiency, has to work under very harsh conditions (temperature, pressure, and pressure difference between circuits). Within the project the most promising technologies for the compact recuperator were investigated. First, the requirements for the recuperator to operate under the direct Brayton cycle have been defined. Based on these requirements the various potential technologies available on the market have been investigated. Two particular technologies (HEATRIC Printed Circuit Heat Exchanger, NORDON plate fin concept) have been selected as most promising. For the former, a precise description has been given and a mock-up has been fabricated and tested in the Claire loop at CEA. In the Claire loop the Printed Circuit Heat Exchanger mock-up has been subjected to thermal shocks, which are considered to be representative for a recuperator. Prior to the experimental testing coupled Computational Fluid Dynamic (CFD) and Finite Element analyses have been performed to give insight into the thermal and mechanical behaviour of the mock-ups during the thermal shock. Based on these results the experimental measuring program has been optimized. Upon completion of the tests the experimental and numerical results have been compared. Based on the results from the investigation performed recommendations are given for the full-size recuperator using the selected technologies

Model description. NUDOS: A computer program for assessing the consequences of airborne releases of radionuclides

International Nuclear Information System (INIS)

Poley, A.D.

1996-02-01

NUDOS is a computer program that can be used to evaluate the consequences of airborne releases of radioactive material. The consequences which can be evaluated are individual dose and associated radiological risk, collective dose and the contamination of land. The code is capable of dealing with both continuous (routine) and accidental releases. For accidental releases both deterministic and probabilistic calculations can be performed, and the impact and effectiveness of emergency actions can be evaluated. This report contains a description of the models contained in NUDOS92 and the recommended values for the input parameters of these models. Additionally, a short overview is given of the future model improvement planned for the next NUDOS-version. (orig.)

Baccalaureate Student Nurses' Study Habits Prior to Admission to Nursing Program: A Descriptive Qualitative Study.

Science.gov (United States)

Felicilda-Reynaldo, Rhea Faye D; Cruz, Jonas Preposi; Bigley, Louise; Adams, Kathryn

2017-06-01

Faculty continue to observe students struggling as they adapt their study strategies to learn nursing core content. This study described the study habits of Bachelor of Science in Nursing (BSN) students prior to admission to the program. This study used a descriptive qualitative research design. A purposive sample of 19 BSN students (juniors [n=10] and seniors [n=9]) from a 4-year public Midwestern university were included in this study. Two focus group sessions, using a semi-structured interview guide, were conducted in the spring semester of 2013. The four themes which emerged from the analysis of data were: "I just got it," "I had a lot of time then," "I studied alone" mostly, and "…a little struggle with the sciences." The findings suggest the BSN students did not study much or employed poor study strategies during their years completing general education courses. Academic support is needed by students prior to admission to the nursing program so they can learn effective study skills and modify their study habits for easier adaptation to the rigors of nursing education. Published by Elsevier Ltd.

The Caltech Concurrent Computation Program - Project description

Science.gov (United States)

Fox, G.; Otto, S.; Lyzenga, G.; Rogstad, D.

1985-01-01

The Caltech Concurrent Computation Program wwhich studies basic issues in computational science is described. The research builds on initial work where novel concurrent hardware, the necessary systems software to use it and twenty significant scientific implementations running on the initial 32, 64, and 128 node hypercube machines have been constructed. A major goal of the program will be to extend this work into new disciplines and more complex algorithms including general packages that decompose arbitrary problems in major application areas. New high-performance concurrent processors with up to 1024-nodes, over a gigabyte of memory and multigigaflop performance are being constructed. The implementations cover a wide range of problems in areas such as high energy and astrophysics, condensed matter, chemical reactions, plasma physics, applied mathematics, geophysics, simulation, CAD for VLSI, graphics and image processing. The products of the research program include the concurrent algorithms, hardware, systems software, and complete program implementations.

8 x 8 fuel surveillance program at Monticello site - end of Cycle 6: fourth post-irradiation inspection, October 1978

International Nuclear Information System (INIS)

Skarshaug, N.H.

1980-09-01

A fuel surveillance program for a lead 8 x 8 reload fuel assembly was implemented at the Monticello Nuclear Power Station in May 1974 prior to Reactor Cycle 3. Inspection results of the fourth post-irradiation inspection performed on this surveillance fuel assembly in October 1978 at EOC 6, after a bundle average exposure of 25,900 MWd/MT, are presented. The measurement techniques, results obtained and comparisons to previous measurements are discussed. The bundle and individual rods examined exhibited characteristics of normal operation and were approved for continued irradiation during Monticello operating Cycle 7

Rock Visualization System. Technical description (RVS version 3.8)

International Nuclear Information System (INIS)

Curtis, P.; Elfstroem, M.; Markstroem, I.

2007-06-01

The Rock Visualization System (RVS) has been developed by SKB for use in visualizing geological and engineering data in 3D. The purpose of this report is to provide a technical description of RVS aimed at potential program users and interested parties as well as fulfilling the function of a more general RVS reference that can be cited when writing other technical reports. The report describes RVS version 4.0. Updated versions of this report or addenda will be made available following further development of RVS and the release of subsequent versions of the program. The report covers the following main items: Technical description of the program with illustrations and examples. Limitations of the program and of functionality. For most RVS functions step-by-step tutorials are available describing how a particular function can be used to carry out a specific task. A complete set of updated tutorials is issued with each new version release of the RVS program. However, the tutorials do not cover all the possible uses of all the individual functions but rather give an overall view of their functionality. A detailed description of every RVS function and how it can be used is included in the RVS online Help system

Rock Visualization System. Technical description (RVS version 3.8)

Energy Technology Data Exchange (ETDEWEB)

Curtis, P.; Elfstroem, M.; Markstroem, I. [FB Engineering, Goeteborg (Sweden)

2005-04-01

The Rock Visualization System (RVS) has been developed by SKB for use in visualizing geological and engineering data in 3D. The purpose of this report is to provide a technical description of RVS aimed at potential program users and interested parties as well as fulfilling the function of a more general RVS reference that can be cited when writing other technical reports. The report describes RVS version 3.8. Updated versions of this report or addenda will be made available following further development of RVS and the release of subsequent versions of the program. The report covers the following main items: Technical description of the program with illustrations and examples. Limitations of the program and of functionality. For most RVS functions step-by-step tutorials are available describing how a particular function can be used to carryout a specific task. A complete set of updated tutorials is issued with each new version release of the RVS program. However, the tutorials do not cover all the possible uses of all the individual functions but rather give an overall view of their functionality. A detailed description of every RVS function and how it can be used is included in the RVS online Help system.

Rock Visualization System. Technical description (RVS version 3.8)

Energy Technology Data Exchange (ETDEWEB)

Curtis, P.; Elfstroem, M.; Markstroem, I. [Golder Associates AB (Sweden)

2007-06-15

The Rock Visualization System (RVS) has been developed by SKB for use in visualizing geological and engineering data in 3D. The purpose of this report is to provide a technical description of RVS aimed at potential program users and interested parties as well as fulfilling the function of a more general RVS reference that can be cited when writing other technical reports. The report describes RVS version 4.0. Updated versions of this report or addenda will be made available following further development of RVS and the release of subsequent versions of the program. The report covers the following main items: Technical description of the program with illustrations and examples. Limitations of the program and of functionality. For most RVS functions step-by-step tutorials are available describing how a particular function can be used to carry out a specific task. A complete set of updated tutorials is issued with each new version release of the RVS program. However, the tutorials do not cover all the possible uses of all the individual functions but rather give an overall view of their functionality. A detailed description of every RVS function and how it can be used is included in the RVS online Help system.

Rock Visualization System. Technical description (RVS version 3.8)

International Nuclear Information System (INIS)

Curtis, P.; Elfstroem, M.; Markstroem, I.

2005-04-01

The Rock Visualization System (RVS) has been developed by SKB for use in visualizing geological and engineering data in 3D. The purpose of this report is to provide a technical description of RVS aimed at potential program users and interested parties as well as fulfilling the function of a more general RVS reference that can be cited when writing other technical reports. The report describes RVS version 3.8. Updated versions of this report or addenda will be made available following further development of RVS and the release of subsequent versions of the program. The report covers the following main items: Technical description of the program with illustrations and examples. Limitations of the program and of functionality. For most RVS functions step-by-step tutorials are available describing how a particular function can be used to carryout a specific task. A complete set of updated tutorials is issued with each new version release of the RVS program. However, the tutorials do not cover all the possible uses of all the individual functions but rather give an overall view of their functionality. A detailed description of every RVS function and how it can be used is included in the RVS online Help system

Contracts, grants and funding summary of supersonic cruise research and variable-cycle engine technology programs, 1972 - 1982

Science.gov (United States)

Hoffman, S.; Varholic, M. C.

1983-01-01

NASA-SCAR (AST) program was initiated in 1972 at the direct request of the Executive Office of the White House and Congress following termination of the U.S. SST program. The purpose of SCR was to conduct a focused research and technology program on those technology programs which contributed to the SST termination and, also, to provide an expanded data base for future civil and military supersonic transport aircraft. Funding for the Supersonic Cruise Research (SCR) Program was initiated in fiscal year 1973 and terminated in fiscal year 1981. The program was implemented through contracts and grants with industry, universities, and by in-house investigations at the NASA/OAST centers. The studies included system studies and five disciplines: propulsion, stratospheric emissions impact, materials and structures, aerodynamic performance, and stability and control. The NASA/Lewis Variable-Cycle Engine (VCE) Component Program was initiated in 1976 to augment the SCR program in the area of propulsion. After about 2 years, the title was changed to VCE Technology program. The total number of contractors and grantees on record at the AST office in 1982 was 101 for SCR and 4 for VCE. This paper presents a compilation of all the contracts and grants as well as the funding summaries for both programs.

File list: NoD.Emb.05.AllAg.Mitotic_cycle_12-14 [Chip-atlas[Archive

Lifescience Database Archive (English)

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The future of integrated coal gasification combined cycle power plants

International Nuclear Information System (INIS)

Mueller, R.; Termuehlen, H.

1991-01-01

This paper examines the future of integrated coal gasification combined cycle (IGCC) power plants as affected by various technical, economical and environmental trends in power generation. The topics of the paper include a description of natural gas-fired combined cycle power plants, IGCC plants, coal gasifier concepts, integration of gasifiers into combined cycle power plants, efficiency, environmental impacts, co-products of IGCC power plants, economics of IGCC power plants, and a review of IGCC power plant projects

DOE-RL Integrated Safety Management System Description

International Nuclear Information System (INIS)

SHOOP, D.S.

2000-01-01

The purpose of this Integrated Safety Management System Description (ISMSD) is to describe the U.S. Department of Energy (DOE), Richland Operations Office (RL) ISMS as implemented through the RL Integrated Management System (RIMS). This ISMSD does not impose additional requirements but rather provides an overview describing how various parts of the ISMS fit together. Specific requirements for each of the core functions and guiding principles are established in other implementing processes, procedures, and program descriptions that comprise RIMS. RL is organized to conduct work through operating contracts; therefore, it is extremely difficult to provide an adequate ISMS description that only addresses RL functions. Of necessity, this ISMSD contains some information on contractor processes and procedures which then require RL approval or oversight. This ISMSD does not purport to contain a full description of the contractors' ISM System Descriptions

DOE-RL Integrated Safety Management System Description

CERN Document Server

Shoop, D S

2000-01-01

The purpose of this Integrated Safety Management System Description (ISMSD) is to describe the U.S. Department of Energy (DOE), Richland Operations Office (RL) ISMS as implemented through the RL Integrated Management System (RIMS). This ISMSD does not impose additional requirements but rather provides an overview describing how various parts of the ISMS fit together. Specific requirements for each of the core functions and guiding principles are established in other implementing processes, procedures, and program descriptions that comprise RIMS. RL is organized to conduct work through operating contracts; therefore, it is extremely difficult to provide an adequate ISMS description that only addresses RL functions. Of necessity, this ISMSD contains some information on contractor processes and procedures which then require RL approval or oversight. This ISMSD does not purport to contain a full description of the contractors' ISM System Descriptions.

AHTR Refueling Systems and Process Description

Energy Technology Data Exchange (ETDEWEB)

Varma, V.K.; Holcomb, D.E.; Bradley, E.C.; Zaharia, N.M.; Cooper, E.J.

2012-07-15

The Advanced High-Temperature Reactor (AHTR) is a design concept for a central station-type [1500 MW(e)] Fluoride salt–cooled High-temperature Reactor (FHR) that is currently undergoing development by Oak Ridge National Laboratory for the US. Department of Energy, Office of Nuclear Energy’s Advanced Reactor Concepts program. FHRs, by definition, feature low-pressure liquid fluoride salt cooling, coated-particle fuel, a high-temperature power cycle, and fully passive decay heat rejection. The overall goal of the AHTR development program is to demonstrate the technical feasibility of FHRs as low-cost, large-size power producers while maintaining full passive safety. The AHTR is approaching a preconceptual level of maturity. An initial integrated layout of its major systems, structures, and components (SSCs), and an initial, high-level sequence of operations necessary for constructing and operating the plant is nearing completion. An overview of the current status of the AHTR concept has been recently published [1], and a report providing a more detailed overview of the AHTR structures and mechanical systems is currently in preparation. This report documents the refueling components and processes envisioned at this early development phase. The report is limited to the refueling aspects of the AHTR and does not include overall reactor or power plant design information. The report, however, does include a description of the materials envisioned for the various components and the instrumentation necessary to control the refueling process. The report begins with an overview of the refueling strategy. Next a mechanical description of the AHTR fuel assemblies and core is provided. The reactor vessel upper assemblies are then described. Following this the refueling path structures and the refueling mechanisms and components are described. The sequence of operations necessary to fuel and defuel the reactor is then discussed. The report concludes with a discussion of the

AHTR Refueling Systems and Process Description

Energy Technology Data Exchange (ETDEWEB)

Varma, Venugopal Koikal [ORNL; Holcomb, David Eugene [ORNL; Bradley, Eric Craig [ORNL; Zaharia, Nathaniel M [ORNL; Cooper, Eliott J [ORNL

2012-07-01

The Advanced High-Temperature Reactor (AHTR) is a design concept for a central station-type [1500 MW(e)] Fluoride salt-cooled High-temperature Reactor (FHR) that is currently undergoing development by Oak Ridge National Laboratory for the US. Department of Energy, Office of Nuclear Energy's Advanced Reactor Concepts program. FHRs, by definition, feature low-pressure liquid fluoride salt cooling, coated-particle fuel, a high-temperature power cycle, and fully passive decay heat rejection. The overall goal of the AHTR development program is to demonstrate the technical feasibility of FHRs as low-cost, large-size power producers while maintaining full passive safety. The AHTR is approaching a preconceptual level of maturity. An initial integrated layout of its major systems, structures, and components (SSCs), and an initial, high-level sequence of operations necessary for constructing and operating the plant is nearing completion. An overview of the current status of the AHTR concept has been recently published and a report providing a more detailed overview of the AHTR structures and mechanical systems is currently in preparation. This report documents the refueling components and processes envisioned at this early development phase. The report is limited to the refueling aspects of the AHTR and does not include overall reactor or power plant design information. The report, however, does include a description of the materials envisioned for the various components and the instrumentation necessary to control the refueling process. The report begins with an overview of the refueling strategy. Next a mechanical description of the AHTR fuel assemblies and core is provided. The reactor vessel upper assemblies are then described. Following this the refueling path structures and the refueling mechanisms and components are described. The sequence of operations necessary to fuel and defuel the reactor is then discussed. The report concludes with a discussion of the

International Nuclear Fuel Cycle Fact Book. Revision 5

International Nuclear Information System (INIS)

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

1985-01-01

This Fact Book has been compiled in an effort to provide: (1) an overview of worldwide nuclear power and fuel cycle programs; and (2) current data concerning fuel cycle and waste management facilities, R and D programs, and key personnel in countries other than the United States. Additional information on each country's program is available in the International Source Book: Nuclear Fuel Cycle Research and Development, PNL-2478, Rev. 2. The Fact Book is organized as follows: (1) Overview section - summary tables which indicate national involvement in nuclear reactor, fuel cycle, and waste management development activities; (2) national summaries - a section for each country which summarizes nuclear policy, describes organizational relationships and provides addresses, names of key personnel, and facilities information; (3) international agencies - a section for each of the international agencies which has significant fuel cycle involvement; (4) energy supply and demand - summary tables, including nuclear power projections; (5) fuel cycle - summary tables; and (6) travel aids international dialing instructions, international standard time chart, passport and visa requirements, and currency exchange rate

International Nuclear Fuel Cycle Fact Book. Revision 5

Energy Technology Data Exchange (ETDEWEB)

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

1985-01-01

This Fact Book has been compiled in an effort to provide: (1) an overview of worldwide nuclear power and fuel cycle programs; and (2) current data concerning fuel cycle and waste management facilities, R and D programs, and key personnel in countries other than the United States. Additional information on each country's program is available in the International Source Book: Nuclear Fuel Cycle Research and Development, PNL-2478, Rev. 2. The Fact Book is organized as follows: (1) Overview section - summary tables which indicate national involvement in nuclear reactor, fuel cycle, and waste management development activities; (2) national summaries - a section for each country which summarizes nuclear policy, describes organizational relationships and provides addresses, names of key personnel, and facilities information; (3) international agencies - a section for each of the international agencies which has significant fuel cycle involvement; (4) energy supply and demand - summary tables, including nuclear power projections; (5) fuel cycle - summary tables; and (6) travel aids international dialing instructions, international standard time chart, passport and visa requirements, and currency exchange rate.

International nuclear fuel cycle fact book. Revision 4

Energy Technology Data Exchange (ETDEWEB)

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

1984-03-01

This Fact Book has been compiled in an effort to provide (1) an overview of worldwide nuclear power and fuel cycle programs and (2) current data concerning fuel cycle and waste management facilities, R and D programs, and key personnel in countries other than the United States. Additional information on each country's program is available in the International Source Book: Nuclear Fuel Cycle Research and Development, PNL-2478, Rev. 2. The Fact Book is organized as follows: (1) Overview section - summary tables which indicate national involvement in nuclear reactor, fuel cycle, and waste management development activities; (2) national summaries - a section for each country which summarizes nuclear policy, describes organizational relationships and provides addresses, names of key personnel, and facilities information; (3) international agencies - a section for each of the international agencies which has significant fuel cycle involvement; (4) energy supply and demand - summary tables, including nuclear power projections; (5) fuel cycle - summary tables; and (6) travel aids - international dialing instructions, international standard time chart, passport and visa requirements, and currency exchange rate.

International nuclear fuel cycle fact book. Revision 4

International Nuclear Information System (INIS)

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

1984-03-01

This Fact Book has been compiled in an effort to provide (1) an overview of worldwide nuclear power and fuel cycle programs and (2) current data concerning fuel cycle and waste management facilities, R and D programs, and key personnel in countries other than the United States. Additional information on each country's program is available in the International Source Book: Nuclear Fuel Cycle Research and Development, PNL-2478, Rev. 2. The Fact Book is organized as follows: (1) Overview section - summary tables which indicate national involvement in nuclear reactor, fuel cycle, and waste management development activities; (2) national summaries - a section for each country which summarizes nuclear policy, describes organizational relationships and provides addresses, names of key personnel, and facilities information; (3) international agencies - a section for each of the international agencies which has significant fuel cycle involvement; (4) energy supply and demand - summary tables, including nuclear power projections; (5) fuel cycle - summary tables; and (6) travel aids - international dialing instructions, international standard time chart, passport and visa requirements, and currency exchange rate

Nuclear Fuel Cycle Options Catalog: FY16 Improvements and Additions

Energy Technology Data Exchange (ETDEWEB)

Price, Laura L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Barela, Amanda Crystal [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Schetnan, Richard Reed [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Walkow, Walter M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2016-08-31

The United States Department of Energy, Office of Nuclear Energy, Fuel Cycle Technology Program sponsors nuclear fuel cycle research and development. As part of its Fuel Cycle Options campaign, the DOE has established the Nuclear Fuel Cycle Options Catalog. The catalog is intended for use by the Fuel Cycle Technologies Program in planning its research and development activities and disseminating information regarding nuclear energy to interested parties. The purpose of this report is to document the improvements and additions that have been made to the Nuclear Fuel Cycle Options Catalog in the 2016 fiscal year.

Nuclear Fuel Cycle Options Catalog FY15 Improvements and Additions.

Energy Technology Data Exchange (ETDEWEB)

Price, Laura L. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Barela, Amanda Crystal [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Schetnan, Richard Reed [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Walkow, Walter M. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)

2015-11-01

The United States Department of Energy, Office of Nuclear Energy, Fuel Cycle Technology Program sponsors nuclear fuel cycle research and development. As part of its Fuel Cycle Options campaign, the DOE has established the Nuclear Fuel Cycle Options Catalog. The catalog is intended for use by the Fuel Cycle Technologies Program in planning its research and development activities and disseminating information regarding nuclear energy to interested parties. The purpose of this report is to document the improvements and additions that have been made to the Nuclear Fuel Cycle Options Catalog in the 2015 fiscal year.

Improving Students' Achievement in Writing Descriptive Text by Using Movie Posters

OpenAIRE

Saleha, Ayu -; -, Sumarsih -

2014-01-01

This study concerns on Improving Students' Achievement in Writing Descriptive Text by Using Movie Posters. The underlying objective of this study is to investigate whether teaching descriptive by using movie posters potentially improves students' skill. The research was conducted by using Classroom Action Research (CAR). The subject of the research was class X of SMA SWASTA UTAMA MEDAN. The number of the students was 28. The procedure of the research was administrated into two cycles which ea...

Out-of-core nuclear fuel cycle economic optimization for nonequilibrium cycles

International Nuclear Information System (INIS)

Comes, S.A.

1987-01-01

A methodology and associated computer code was developed to determine near-optimum out-of-core fuel management strategies. The code, named OCEON (Out-of-Core Economic OptimizationN), identified feed-region sizes and enrichments, and partially burned fuel-reload strategies for each cycle of a multi-cycle planning horizon, subject to cycle-energy requirements and constraints on feed enrichments, discharge burnups, and the moderator temperature coefficient. A zero-dimensional reactor physics model, enhanced by a linear reactivity model to provide batch power shares, performs the initial feed enrichment, burnup and constraint evaluations, while a two-dimensional, nodal code is used to refine the calculations for the final solutions. The economic calculations are performed rapidly using an annuity-factor-based model. Use of Monte Carlo integer programming to select the optimum solutions allows for the determination of a family of near-optimum solutions, from which engineering judgment may be used to select an appropriate strategy. Results from various nonequilibrium cycle energy requirement cases typically show a large number of low-cost solutions near the optimum. This confirms that the Monte Carlo integer programming approach of generating a family of solutions will be most useful for selecting optimum strategies when other considerations, such as incore loading pattern concerns, must be addressed

Babcock Redux: An Amendment of Babcock's Schematic of the Sun's Magnetic Cycle

Science.gov (United States)

Moore, Ronald L.; Cirtain, Jonathan W.; Sterling, Alphonse C.

2017-08-01

We amend Babcock's original scenario for the global dynamo process that sustains the Sun's 22-year magnetic cycle. The amended scenario fits post-Babcock observed features of the magnetic activity cycle and convection zone, and is based on ideas of Spruit & Roberts (1983, Nature, 304, 401) about magnetic flux tubes in the convection zone. A sequence of four schematic cartoons lays out the proposed evolution of the global configuration of the magnetic field above, in, and at the bottom of the convection zone through sunspot Cycle 23 and into Cycle 24. Three key elements of the amended scenario are: (1) as the net following-polarity magnetic field from the sunspot-region Ω-loop fields of an ongoing sunspot cycle is swept poleward to cancel and replace the opposite-polarity polar-cap field from the previous sunspot cycle, it remains connected to the ongoing sunspot cycle's toroidal source-field band at the bottom of the convection zone; (2) topological pumping by the convection zone's free convection keeps the horizontal extent of the poleward-migrating following-polarity field pushed to the bottom, forcing it to gradually cancel and replace old horizontal field below it that connects the ongoing-cycle source-field band to the previous-cycle polar-cap field; (3) in each polar hemisphere, by continually shearing the poloidal component of the settling new horizontal field, the latitudinal differential rotation low in the convection zone generates the next-cycle source-field band poleward of the ongoing-cycle band. The amended scenario is a more-plausible version of Babcock's scenario, and its viability can be explored by appropriate kinematic flux-transport solar-dynamo simulations. A paper giving a full description of our dynamo scenario is posted on arXiv (http://arxiv.org/abs/1606.05371).This work was funded by the Heliophysics Division of NASA's Science Mission Directorate through the Living With a Star Targeted Research and Technology Program and the Hinode

IFR fuel cycle demonstration in the EBR-II Fuel Cycle Facility

International Nuclear Information System (INIS)

Lineberry, M.J.; Phipps, R.D.; Rigg, R.H.; Benedict, R.W.; Carnes, M.D.; Herceg, J.E.; Holtz, R.E.

1991-01-01

The next major milestone of the IFR (Integral Fast Reactor) program is engineering-scale demonstration of the pyroprocess fuel cycle. The EBR-II Fuel Cycle Facility has just entered a startup phase which includes completion of facility modifications, and installation and cold checkout of process equipment. This paper reviews the design and construction of the facility, the design and fabrication of the process equipment, and the schedule and initial plan for its operation. (author)

IFR fuel cycle demonstration in the EBR-II Fuel Cycle Facility

International Nuclear Information System (INIS)

Lineberry, M.J.; Phipps, R.D.; Rigg, R.H.; Benedict, R.W.; Carnes, M.D.; Herceg, J.E.; Holtz, R.E.

1991-01-01

The next major milestone of the IFR program is engineering-scale demonstration of the pyroprocess fuel cycle. The EBR-II Fuel Cycle Facility has just entered a startup phase which includes completion of facility modifications, and installation and cold checkout of process equipment. This paper reviews the design and construction of the facility, the design and fabrication of the process equipment, and the schedule and initial plan for its operation. 5 refs., 4 figs

ACTIV - a program for automatic processing of gamma-ray spectra

International Nuclear Information System (INIS)

Zlokazov, V.B.

1982-01-01

Program ACTIV is intended for precise analysis of γ-rays and X-ray spectra and allows the user to carry out the full cycle of automatic processing of a series of spectra, i.e. calibration, automatic peak search, determination of peak positions and areas, identification of the radioisotopes and the transformation of the areas found into masses of isotopes in the irradiated sample. ACTIV uses a complex mathematical technique and is oriented mainly to large computers, but using overlaid loading, it can be run also on small computers like the PDP 11/70. Compared with other similar programs, ACTIV has some advantages in accuracy of peak shape description and in the reliability of the peak search and its least-square analysis. The program can be used for the purpose of activation analysis. The program can analyze spectra with poor statistics and with broad and narrow peaks. (orig.)

A Mobile Health App-Based Postnatal Educational Program (Home-but not Alone): Descriptive Qualitative Study.

Science.gov (United States)

Shorey, Shefaly; Yang, Yen Yen; Dennis, Cindy-Lee

2018-04-19

The postnatal period poses numerous challenges for new parents. Various educational programs are available to support new parents during this stressful period. However, the usefulness of educational programs must be evaluated to ascertain their credibility. The aim of this descriptive, qualitative study was to explore the views of parents of newborns with regard to the content and delivery of a mobile health (mHealth) app-based postnatal educational program. A qualitative semistructured interview guide was used to collect data from 17 participants who belonged to the intervention group of a randomized controlled trial. The intervention, a 4-week-long access to a mHealth app-based educational program, was evaluated. The interviews were conducted in English and at the participants' homes. Thematic analysis was used to analyze the data. The Consolidated Criteria for Reporting Qualitative Research checklist was used to report the findings. The interviews revealed 4 main themes: (1) positive features of the mHealth app, (2) advice from midwives, (3) experiences gained from using the mHealth app, and (4) recommendations for the future. The participants evaluated the educational program to be a good source of information that was tailored to the local context. The different modes of delivery, including audio and video, accentuated the accessibility of information. The parents evaluated that the facilitator of the featured communication platform, a midwife, provided trustworthy advice. Belongingness to a virtual community beyond the hospital endowed the parents the confidence that they were not alone and were supported by other parents and health care professionals. According to the parents, the mHealth app-based educational program was helpful in supporting a multi-ethnic sample of parents during the postnatal period. This insight indicates that the program could be implemented in a wide community of parents in the postnatal period. The helpfulness of the educational

Nuclear fuel cycle and waste management in France

International Nuclear Information System (INIS)

Sousselier, Yves.

1981-05-01

After a short description of the nuclear fuel cycle mining, milling, enrichment and reprocessing, radioactive waste management in France is exposed. The different types of radioactive wastes are examined. Storage, solidification and safe disposal of these wastes are described

IFR fuel cycle

International Nuclear Information System (INIS)

Battles, J.E.; Miller, W.E.; Lineberry, M.J.; Phipps, R.D.

1992-01-01

The next major milestone of the IFR program is engineering-scale demonstration of the pyroprocess fuel cycle. The EBR-II Fuel Cycle Facility has just entered a startup phase, which includes completion of facility modifications and installation and cold checkout of process equipment. This paper reviews the development of the electrorefining pyroprocess, the design and construction of the facility for the hot demonstration, the design and fabrication of the equipment, and the schedule and initial plan for its operation

Evaluation and optimization of LWR fuel cycles

International Nuclear Information System (INIS)

Akbas, T.; Zabunoglu, O.; Tombakoglu, M.

2001-01-01

There are several options in the back-end of the nuclear fuel cycle. Discharge burn-up, length of interim storage period, choice of direct disposal or recycling and method of reprocessing in case of recycling affect the options and determine/define the fuel cycle scenarios. These options have been evaluated in viewpoint of some tangible (fuel cycle cost, natural uranium requirement, decay heat of high level waste, radiological ingestion and inhalation hazards) and intangible factors (technological feasibility, nonproliferation aspect, etc.). Neutronic parameters are calculated using versatile fuel depletion code ORIGEN2.1. A program is developed for calculation of cost related parameters. Analytical hierarchy process is used to transform the intangible factors into the tangible ones. Then all these tangible and intangible factors are incorporated into a form that is suitable for goal programming, which is a linear optimization technique and used to determine the optimal option among alternatives. According to the specified objective function and constraints, the optimal fuel cycle scenario is determined using GPSYS (a linear programming software) as a goal programming tool. In addition, a sensitivity analysis is performed for some selected important parameters

A coherent description of the process of design

DEFF Research Database (Denmark)

Hertz, Kristian Dahl

1992-01-01

, and others. Doing so, a corresponding number of philosophical problems are solved, and the description becomes a coherent theory. The author has shown that it is possible to make a computer program for conceptual modelling based on the theory presented, and the principles of a CAD system including......A description of the creative design process is given based on Empiricism and using the theory of sets on conceptual and subconscious representations of the human mind. Definitions that are more precise are given of a number of common concepts such as association, synthesis, culture, creation, art...... the program and supporting the creative process of the designer is described....

Programming the BBC micro

CERN Document Server

Ferguson, John D; Macari, Louie; Williams, Peter H

1983-01-01

Programming the BBC Micro is a 12-chapter book that begins with a description of the BBC microcomputer, its peripheral, and faults. Subsequent chapters focus on practice in programming, program development, graphics, words, numbers, sound, bits, bytes, and assembly language. The interfacing, file handling, and detailed description of BBC microcomputer are also shown.

Brucella abortus Cell Cycle and Infection Are Coordinated.

Science.gov (United States)

De Bolle, Xavier; Crosson, Sean; Matroule, Jean-Yves; Letesson, Jean-Jacques

2015-12-01

Brucellae are facultative intracellular pathogens. The recent development of methods and genetically engineered strains allowed the description of cell-cycle progression of Brucella abortus, including unipolar growth and the ordered initiation of chromosomal replication. B. abortus cell-cycle progression is coordinated with intracellular trafficking in the endosomal compartments. Bacteria are first blocked at the G1 stage, growth and chromosome replication being resumed shortly before reaching the intracellular proliferation compartment. The control mechanisms of cell cycle are similar to those reported for the bacterium Caulobacter crescentus, and they are crucial for survival in the host cell. The development of single-cell analyses could also be applied to other bacterial pathogens to investigate their cell-cycle progression during infection. Copyright © 2015 Elsevier Ltd. All rights reserved.

National program of breast cancer early detection in Brod-Posavina County (East Croatia).

Science.gov (United States)

Jurišić, Irena; Kolovrat, Ana; Mitrečić, Drago; Cvitković, Ante

2014-09-01

Results of the National Program of Breast Cancer Early Detection in Brod-Posavina County during the 2006-2012 period are presented. Response rate in two National Program cycles, cancers detected according to factors such as first and last menstruation, age at cancer detection, deliveries and mammography findings according to the Breast Imaging Reporting and Data System (BI-RADS) before diagnosis verification were analyzed. Data were obtained from the software connecting Public Health Institutes via Ministry of Health server and questionnaires filled out by the women presenting for screening and processed by the method of descriptive statistics. Mammography findings were classified according to the BI-RADS classification. In two National Program cycles during the 2006-2012 period, women aged 50-69 were called for mammography screening. In the first cycle, the response rate in Brod-Posavina County was 53.2%, with 71 cancers detected at a mean age of 61.3 years. In the second cycle, the response rate was 57.0%, with 44 cancers detected at a mean age of 62.5 years. In the first and second cycles, there were 21.1% and 14.3% of mammography findings requiring additional work-up (BI-RADS 0), respectively. Particular risk factors such as early menarche, late menopause, parity, positive family history and presence of benign breast lesions were not demonstrated in women with verified cancer. There was no increase in the incidence of breast cancer per 100,000 inhabitants in the Brod-Posavina County following implementation of the National Program. In conclusion, efforts should be focused on increasing public health awareness, ensuring appropriate professional staff engaged in screening, and improving medical care in order to reduce the time elapsed from establishing suspicion to confirming the diagnosis of breast cancer.

Closing the fuel cycle

International Nuclear Information System (INIS)

Aycoberry, C.; Rougeau, J.P.

1987-01-01

The progressive implementation of some key nuclear fuel cycle capecities in a country corresponds to a strategy for the acquisition of an independant energy source, France, Japan, and some European countries are engaged in such strategic programs. In France, COGEMA, the nuclear fuel company, has now completed the industrial demonstration of the closed fuel cycle. Its experience covers every step of the front-end and of the back-end: transportation of spent fuels, storage, reprocessing, wastes conditioning. The La Hague reprocessing plant smooth operation, as well as the large investment program under active progress can testify of full mastering of this industry. Together with other French and European companies, COGEMA is engaged in the recycling industry, both for uranium through conversion of uranyl nitrate for its further reeichment, and for plutonium through MOX fuel fabrication. Reprocessing and recycling offer the optimum solution for a complete, economic, safe and future-oriented fuel cycle, hence contributing to the necessary development of nuclear energy. (author)

1995 Baseline solid waste management system description

International Nuclear Information System (INIS)

Anderson, G.S.; Konynenbelt, H.S.

1995-09-01

This provides a detailed solid waste system description that documents the treatment, storage, and disposal (TSD) strategy for managing Hanford's solid low-level waste, low-level mixed waste, transuranic and transuranic mixed waste, and greater-than-Class III waste. This system description is intended for use by managers of the solid waste program, facility and system planners, as well as system modelers. The system description identifies the TSD facilities that constitute the solid waste system and defines these facilities' interfaces, schedules, and capacities. It also provides the strategy for treating each of the waste streams generated or received by the Hanford Site from generation or receipt through final destination

Coding of Information in Limit Cycle Oscillators

Science.gov (United States)

Schleimer, Jan-Hendrik; Stemmler, Martin

2009-12-01

Starting from a general description of noisy limit cycle oscillators, we derive from the Fokker-Planck equations the linear response of the instantaneous oscillator frequency to a time-varying external force. We consider the time series of zero crossings of the oscillator’s phase and compute the mutual information between it and the driving force. A direct link is established between the phase response curve summarizing the oscillator dynamics and the ability of a limit cycle oscillator, such as a heart cell or neuron, to encode information in the timing of peaks in the oscillation.

Innovation Cycles Concerning Strategic Planning of Product-Service-Systems

OpenAIRE

Hepperle, Clemens;Mörtl, Markus;Lindemann, Udo

2017-01-01

This paper proposes a research program for identifying, understanding and describing innovation cycles concerning strategic planning of product-service-systems. A general overview about the background of cycle management in innovation processes, which the proposed research program is part of, is given before focusing cycles concerning strategic planning. As companies offer more and more complex products in order to satisfy market needs, the innovation process of such products becomes also mor...

Status of the breeder fuel cycle in the United States

International Nuclear Information System (INIS)

Burch, W.D.

1985-01-01

This paper reviews the status and plans for the fast reactor fuel cycle in the United States. The United States is undertaking a complete reexamination of its entire breeder program strategy, and the direction of the new program is not yet clear. Studies in progress to examine the associated fuel cycle strategies as they relate to the overall emerging breeder strategy are described. The present status of and recent developments in the fuel cycle R and D programs are summarized

The effectiveness of community-based cycling promotion: findings from the Cycling Connecting Communities project in Sydney, Australia

Directory of Open Access Journals (Sweden)

Merom Dafna

2010-01-01

Full Text Available Abstract Background Encouraging cycling is an important way to increase physical activity in the community. The Cycling Connecting Communities (CCC Project is a community-based cycling promotion program that included a range of community engagement and social marketing activities, such as organised bike rides and events, cycling skills courses, the distribution of cycling maps of the area and coverage in the local press. The aim of the study was to assess the effectiveness of this program designed to encourage the use of newly completed off-road cycle paths through south west Sydney, Australia. Methods The evaluation used a quasi-experimental design that consisted of a pre- and post-intervention telephone survey (24 months apart of a cohort of residents (n = 909 in the intervention area (n = 520 (Fairfield and Liverpool and a socio-demographically similar comparison area (n = 389 (Bankstown. Both areas had similar bicycle infrastructure. Four bicycle counters were placed on the main bicycle paths in the intervention and comparison areas to monitor daily bicycle use before and after the intervention. Results The telephone survey results showed significantly greater awareness of the Cycling Connecting Communities project (13.5% vs 8.0%, p Conclusion Despite relatively modest resources, the Cycling Connecting Communities project achieved significant increases in bicycle path use, and increased cycling in some sub-groups. However, this community based intervention with limited funding had very limited reach into the community and did not increase population cycling levels.

Analysis and design of Fuel Cycle Plant for natural phenomena hazards

International Nuclear Information System (INIS)

Horsager, B.K.

1985-01-01

A description of the Design Basis and the analysis and design methods used for natural phenomena at the Fuel Cycle Plant at Hanford, Washington is presented. A physical description of the main process facility and the auxiliary emergency and support facilities is given. The mission of the facility is presented and a brief description of the processes which will take place within the facility is given. The Design Criteria and design bases for natural phenomena including tornados, earthquakes and volcanic eruptions are described

Fuel cycle studies

International Nuclear Information System (INIS)

Anon.

1978-01-01

Programs are being conducted in the following areas: advanced solvent extraction techniques, accident consequences, fuel cycles for nonproliferation, pyrochemical and dry processes, waste encapsulation, radionuclide transport in geologic media, hull treatment, and analytical support for LWBR

Vehicle infrastructure integration proof of concept : technical description--vehicle : final report

Science.gov (United States)

2009-05-19

This report provides the technical description of the VII system developed for the Cooperative Agreement VII Program between the USDOT and the VII Consortium. The basic architectural elements are summarized and detailed descriptions of the hardware a...

Prolog as description and implementation language in computer science teaching

DEFF Research Database (Denmark)

Christiansen, Henning

population with uneven mathematical backgrounds. % Definitional interpreters, compilers, and other models of computation are defined in a systematic way as Prolog programs, and as a result, formal descriptions become running prototypes that can be tested and modified by the students. These programs can......Prolog is a powerful pedagogical instrument for theoretical elements of computer science when used as combined description language and experimentation tool. A teaching methodology based on this principle has been developed and successfully applied in a context with a heterogeneous student...

Involvement of the US Department of Defense in Civilian Assistance, Part I: a quantitative description of the projects funded by the Overseas Humanitarian, Disaster, and Civic Aid Program.

Science.gov (United States)

Bourdeaux, Margaret Ellis; Lawry, Lynn; Bonventre, Eugene V; Burkle, Frederick M

2010-03-01

To review the history and goals of the US Department of Defense's largest civilian assistance program, the Overseas Humanitarian, Disaster and Civic Aid Program and to describe the number, geographic regions, years, key words, countries, and types of projects carried out under this program since 2001. Using the program's central database, we reviewed all approved projects since 2001 and tabulated them by year, combatant command, country, and key word. We also reviewed the project descriptions of projects funded between January 1, 2006, and February 9, 2008, and examined how their activities varied by combatant command and year. Of the 5395 projects in the database, 2097 were funded. Projects took place in more than 90 countries, with Southern, Pacific, and Africa Command hosting the greatest number. The most common types of projects were school, health, disaster response, and water infrastructure construction, and disaster-response training. The "global war on terror" was the key word most frequently tagged to project descriptions. Project descriptions lacked stated goals as well as implementation and coordination strategies with potential partners, and did not report outcome or impact indicators. The geographic reach of the program is vast and projects take place in a wide variety of public sectors. Yet their security and civilian assistance value remains unclear given the lack of stated project goals, implementation strategies, or measures of effectiveness. To facilitate transparency and policy discussion, we recommend project proposals include hypotheses as to how they will enhance US security, their relevance to the public sector they address, and outcome and impact indicators that can assess their value and effectiveness.

Input description for BIOPATH

International Nuclear Information System (INIS)

Marklund, J.E.; Bergstroem, U.; Edlund, O.

1980-01-01

The computer program BIOPATH describes the flow of radioactivity within a given ecosystem after a postulated release of radioactive material and the resulting dose for specified population groups. The present report accounts for the input data necessary to run BIOPATH. The report also contains descriptions of possible control cards and an input example as well as a short summary of the basic theory.(author)

Management control system description

Energy Technology Data Exchange (ETDEWEB)

Bence, P. J.

1990-10-01

This Management Control System (MCS) description describes the processes used to manage the cost and schedule of work performed by Westinghouse Hanford Company (Westinghouse Hanford) for the US Department of Energy, Richland Operations Office (DOE-RL), Richland, Washington. Westinghouse Hanford will maintain and use formal cost and schedule management control systems, as presented in this document, in performing work for the DOE-RL. This MCS description is a controlled document and will be modified or updated as required. This document must be approved by the DOE-RL; thereafter, any significant change will require DOE-RL concurrence. Westinghouse Hanford is the DOE-RL operations and engineering contractor at the Hanford Site. Activities associated with this contract (DE-AC06-87RL10930) include operating existing plant facilities, managing defined projects and programs, and planning future enhancements. This document is designed to comply with Section I-13 of the contract by providing a description of Westinghouse Hanford's cost and schedule control systems used in managing the above activities. 5 refs., 22 figs., 1 tab.

Assessing Cycling Participation in Australia

Directory of Open Access Journals (Sweden)

Chris Rissel

2013-01-01

Full Text Available Planning and evaluating cycling programs at a national or state level requires accurate measures of cycling participation. However, recent reports of cycling participation have produced very different estimates. This paper examines the reported rates of cycling in five recent population surveys of cycling. Three surveys (one national and two from Sydney asking respondents when they last rode a bicycle generated cycling participation (cycled in the past year estimates of 29.7%, 34.1% and 28.9%. Two other national surveys which asked participants to recall (unprompted any physical activity done for exercise, recreation or sport in the previous 12 months, estimated cycling in the past year as 11.1% and 6.5%. While unprompted recall of cycling as a type of physical activity generates lower estimates of cycling participation than specific recall questions, both assessment approaches produced similar patterns of cycling by age and sex with both approaches indicating fewer women and older adults cycling. The different question styles most likely explain the substantial discrepancies between the estimates of cycling participation. Some differences are to be expected due to sampling variability, question differences, and regional variation in cycling.

Rapsodie: A closed fuel cycle

International Nuclear Information System (INIS)

Levallet, E.H.; Costa, L.; Mougniot, J.C.; Robin, J.

1977-01-01

The Fortissimo Version of the core of the RAPSODIE fast reactor produces 40 MWTh. Since its start up in May 1970 in the CEN-CADARACHE its availability has stayed around 85%. Some of the mixed oxyde fuel pins UO 2 - 30% PuO 2 have already reached 150.000 MWd/t. The reprocessing is done in the pilot plant located in the La Hague Center and the plutonium obtained has already been re-used in the reactor. The Rapsodie-Fortissimo cycle is therefore now a closed cycle. This cycle is quite representative of fast reactor cycle characteristics and thus provides a remarkable research and development tool for the study of fabrication, in-reactor performances, transport, storage and reprocessing. These studies concern in particular the evolution of fission products and heavy isotopes content in fuel which controls both reprocessing schemes and intensity of emitted radiations. A program for the analysis of irradiated fuel has been developed either using samples collected all along the cycle, or following the actual reprocessing subassemblies. A set of basic data and calculation models has been established with two objectives: to give a better interpretation of the experimental program on one hand, and to extrapolate these results to the fuel cycle of fast reactors in general on the other hand. The first results have been quite encouraging up to now [fr

Nuclear Fuel Cycle Technologies: Current Challenges and Future Plans - 12558

Energy Technology Data Exchange (ETDEWEB)

Griffith, Andrew [U.S. Department of Energy, Washington, DC (United States)

2012-07-01

The mission of the Office of Nuclear Energy's Fuel Cycle Technologies office (FCT program) is to provide options for possible future changes in national nuclear energy programs. While the recent draft report of the Blue Ribbon Commission on America's Nuclear Future stressed the need for organization changes, interim waste storage and the establishment of a permanent repository for nuclear waste management, it also recognized the potential value of alternate fuel cycles and recommended continued research and development in that area. With constrained budgets and great expectations, the current challenges are significant. The FCT program now performs R and D covering the entire fuel cycle. This broad R and D scope is a result of the assignment of new research and development (R and D) responsibilities to the Office of Nuclear Energy (NE), as well as reorganization within NE. This scope includes uranium extraction from seawater and uranium enrichment R and D, used nuclear fuel recycling technology, advanced fuel development, and a fresh look at a range of disposal geologies. Additionally, the FCT program performs the necessary systems analysis and screening of fuel cycle alternatives that will identify the most promising approaches and areas of technology gaps. Finally, the FCT program is responsible for a focused effort to consider features of fuel cycle technology in a way that promotes nonproliferation and security, such as Safeguards and Security by Design, and advanced monitoring and predictive modeling capabilities. This paper and presentation will provide an overview of the FCT program R and D scope and discuss plans to analyze fuel cycle options and support identified R and D priorities into the future. The FCT program is making progress in implanting a science based, engineering driven research and development program that is evaluating options for a sustainable fuel cycle in the U.S. Responding to the BRC recommendations, any resulting legislative

Idiosyncratic Uncertainty, Capacity Utilization and the Business Cycle

DEFF Research Database (Denmark)

Fragnart, Jean-Francois; Licandro, Omar; Portier, Franck

thus hides a diversity of microeconomic situations. The variablity of the capacity utilization allows for a good description of some of the main stylized facts of the busines cycle, propagates and magnifies aggregate technological shocks and generates endogenous persistence (i.e., the output growth...

IAEA programme on nuclear fuel cycle and materials technologies

International Nuclear Information System (INIS)

Killeen, J.

2006-01-01

In this paper a brief description and the main objectives of IAEA Programme B on Nuclear fuel cycle are given. The coordinated research project on Improvement of Models Used For Fuel Behaviour Simulation (FUMEX II) is also presented

Advanced Fuel Cycle Economic Sensitivity Analysis

Energy Technology Data Exchange (ETDEWEB)

David Shropshire; Kent Williams; J.D. Smith; Brent Boore

2006-12-01

A fuel cycle economic analysis was performed on four fuel cycles to provide a baseline for initial cost comparison using the Gen IV Economic Modeling Work Group G4 ECON spreadsheet model, Decision Programming Language software, the 2006 Advanced Fuel Cycle Cost Basis report, industry cost data, international papers, the nuclear power related cost study from MIT, Harvard, and the University of Chicago. The analysis developed and compared the fuel cycle cost component of the total cost of energy for a wide range of fuel cycles including: once through, thermal with fast recycle, continuous fast recycle, and thermal recycle.

TIBSO - A program system for the calculation of the production, transfer, life cycle and radiation of radionuclides in a compound nuclear reactor system

International Nuclear Information System (INIS)

Vertes, P.

1977-10-01

The goal of the program system TIBSO is the calculation of production, transfer, cumulation and filtration of radio isotopes in the cooling system of an atomic power plant. There is no restriction on the complexity of the cooling system, only the linearity and the time independence of technological parameters are assumed. The report contains the description of the basic idea of the method, the solution of the set of linear equations to be used and the description of the internal library files developed. (D.P.)

Effect of temperature and salinity on egg hatching and description of the life cycle of Lernanthropus latis (Copepoda: Lernanthropidae) infecting barramundi, Lates calcarifer.

Science.gov (United States)

Brazenor, Alexander K; Hutson, Kate S

2013-10-01

The parasite Lernanthropus latis (Copepoda: Lernanthropidae) is a major threat to the sustained mariculture of barramundi, Lates calcarifer (Perciformes: Latidae). We investigated the effect of water temperature and salinity on egg hatching success of L. latis and describe the life cycle for the first time. Wild and sea-caged L. calcarifer examined in tropical north Australia exhibited similar parasite prevalence (range: 80-100%) and mean parasite intensity (range: 3-6), whereas land-based maricultured fish were not infected. Hatching success and time to first and last hatch was determined for a range of water temperature (22, 30, 32 and 34°C) and salinity (0, 11, 22, 35 and 40‰) combinations representing current and predicted climate conditions. There was a significant interaction between water temperature and salinity on the hatching success of L. latis nauplii. Eggs hatched in all temperature treatments, with the greatest hatching success at 30°C and 32°C (98 and 92% success, respectively) in 35‰. Hatching did not occur at 0‰ and was severely reduced at 11‰ (1.6% success). Hatching began within 6h at all water temperatures with >95% of eggs hatched within 30h at 30, 32 and 34°C and within 60h at 22°C. Adult parasites differed from the original description by the presence of the parabasal flagellum, small setae on the legs and caudal rami and minor incongruences regarding morphological measurements. The life cycle of L. latis includes three free living stages and five parasitic stages. Although L. latis exhibits broad environmental tolerance, freshwater can be used as an effective management strategy to break the life cycle in aquaculture. Copyright © 2013 Elsevier Ireland Ltd. All rights reserved.

The bacterial cell cycle checkpoint protein Obg and its role in programmed cell death

Directory of Open Access Journals (Sweden)

Liselot Dewachter

2016-03-01

Full Text Available The phenomenon of programmed cell death (PCD, in which cells initiate their own demise, is not restricted to multicellular organisms. Unicellular organisms, both eukaryotes and prokaryotes, also possess pathways that mediate PCD. We recently identified a PCD mechanism in Escherichia coli that is triggered by a mutant isoform of the essential GTPase ObgE (Obg of E. coli. Importantly, the PCD pathway mediated by mutant Obg (Obg* differs fundamentally from other previously described bacterial PCD pathways and thus constitutes a new mode of PCD. ObgE was previously proposed to act as a cell cycle checkpoint protein able to halt cell division. The implication of ObgE in the regulation of PCD further increases the similarity between this protein and eukaryotic cell cycle regulators that are capable of doing both. Moreover, since Obg is conserved in eukaryotes, the elucidation of this cell death mechanism might contribute to the understanding of PCD in higher organisms. Additionally, if Obg*-mediated PCD is conserved among different bacterial species, it will be a prime target for the development of innovative antibacterials that artificially induce this pathway.

Bearing development program for a 25 kWe solar-powered organic Rankine-cycle engine

Science.gov (United States)

Nesmith, B.

1985-01-01

The bearing development program is summarized for a 25-kWe power conversion subsystem (PCS) consisting of an organic Rankine-cycle engine, and permanent magnetic alternator (PMA) and rectifier to be used in a 100-kWe point-focusing distributed receiver solar power plant. The engine and alternator were hermetically sealed and used toluene as the working fluid. The turbine, alternator, and feed pump (TAP) were mounted on a single shaft operating at speeds up to 60,000 rev/min. Net thermal-to-electric efficiencies in the range of 21 to 23% were demonstrated at the maximum working fluid temperature of 400 C (750 F). A chronological summary of the bearing development program is presented. The primary causes of bearing wear problems were traced to a combination of rotordynamic instability and electrodynamic discharge across the bearing surfaces caused by recirculating currents from the PMA. These problems were resolved by implementing an externally supplied, flooded-bearing lubrication system and by electrically insulating all bearings from the TAP housing. This program resulted in the successful development of a stable, high-speed, toluene-lubricated five-pad tilting-pad journal bearing and Rayleigh step thrust bearing system capable of operating at all inclinations between horizontal and vertical.

The IFR modern nuclear fuel cycle

International Nuclear Information System (INIS)

Hannum, W.H.

1991-01-01

Nuclear power is an essential component of the world's energy supply. The IFR program, by returning to fundamentals, offers a fresh approach to closing the nuclear fuel cycle. This closed fuel cycle represents the ultimate in efficient resource utilization and environmental accountability. 35 refs., 2 tabs

Staff training program of CANDU projects in Saskatoon

International Nuclear Information System (INIS)

Huterer, J.

1996-01-01

This paper describes the training process for a nuclear project on a new site. When AECL opened a project office Saskatoon, senior management recognized the need for large scale staff training and made the necessary commitments. Two types of training programs were initiated, general and technical. The general training plan included topics related to nuclear project life cycle. Technical training was discipline and task specific. Based on the job descriptions and staff qualifications, technical training requirements were documented for the entire staff. The training strategy was developed and implemented. Detailed records were maintained to monitor the progress, draw conclusions, and plan training for future nuclear facilities. (author)

Quality assurance program description. Topical report SDQAPD-1

International Nuclear Information System (INIS)

1975-01-01

The topical report presented describes the SDG and E QA Program that is applied to the design, procurement, construction, and preoperational testing of nuclear power plants. The QA plan describes the SDG and E organizational structure for quality assurance; identifies the functions, duties, and responsibilities of key departments and individuals; describes interrelationships and interfaces among internal groups and external organizations; delineates program requirements, and prescribes methods of implementation. SDG and E Procedures and Directives provide detailed direction for accomplishment of program requirements in consonance with the methods specified in the QA Plan

Effect on 12-week Intensive Dietary and Exercise Program on Weight Reduction and Maintenance in Obese Women with Weight Cycling History

OpenAIRE

Kwon, Ha Nui; Nam, Sang-Seok; Park, Yoo Kyoung

2017-01-01

This study examined the effect of 12-week intensive dietary and exercise intervention program on body composition and stress-related hormones in obese women and to examine the residual effect after the intervention. The participants of this study were 30 obese women who had a body mass index of over 25 kg/m2 and over 30% in body fat. They were classified into 2 groups depending on the history of weight cycling (WC); the WC group (? ?5% of the original body weight) and the non-weight cycling (...

Gas reactor international cooperative program interim report. Pebble bed reactor fuel cycle evaluation

International Nuclear Information System (INIS)

1978-09-01

Nuclear fuel cycles were evaluated for the Pebble Bed Gas Cooled Reactor under development in the Federal Republic of Germany. The basic fuel cycle specified for the HTR-K and PNP is well qualified and will meet the requirements of these reactors. Twenty alternate fuel cycles are described, including high-conversion cycles, net-breeding cycles, and proliferation-resistant cycles. High-conversion cycles, which have a high probability of being successfully developed, promise a significant improvement in resource utilization. Proliferation-resistant cycles, also with a high probability of successful development, compare very favorably with those for other types of reactors. Most of the advanced cycles could be adapted to first-generation pebble bed reactors with no significant modifications

Improving Defense Acquisition Management and Policy Through a Life-Cycle Affordability Framework

Science.gov (United States)

2014-02-04

14  Are the PBL Prophets Using Science or Alchemy to Create Life Cycle...or role (engineering, SCM, finance ). Two Select managers for baseline study. Select managers whose self-description and supervisor feedback...networks into value . Are the PBL Prophets Using Science or Alchemy to Create Life Cycle Affordability? Using Theory to Predict the Efficacy of

The IFR modern nuclear fuel cycle

Energy Technology Data Exchange (ETDEWEB)

Hannum, W.H.

1991-01-01

Nuclear power is an essential component of the world's energy supply. The IFR program, by returning to fundamentals, offers a fresh approach to closing the nuclear fuel cycle. This closed fuel cycle represents the ultimate in efficient resource utilization and environmental accountability. 35 refs., 2 tabs.

Energy research program 82

International Nuclear Information System (INIS)

1982-01-01

The energy research program 82 (EFP-82) is prepared by the Danish ministry of energy in order to continue the extension of the Danish energy research and development started through the former trade ministry's programs EM-1 (1976) and EM-2 (1978), and the energy ministry's programs EFP-80 and EFP-81. The new program is a continuation of the activities in the period 1982-84 with a total budget of 100 mio.Dkr. The program gives a brief description of background, principles, organization and financing, and a detailed description of each research area. (BP)

Summary description of the Fast Flux Test Facility

International Nuclear Information System (INIS)

Cabell, C.P.

1980-12-01

This document has been compiled and issued to provide an illustrated engineering summary description of the FFTF. The document is limited to a description of the plant and its functions, and does not cover the extensive associated programs that have been carried out in the fields of design, design analysis, safety analysis, fuels development, equipment development and testing, quality assurance, equipment fabrication, plant construction, acceptance testing, operations planning and training, and the like

ORCENT-2, Full Load Steam Turbine Cycle Thermodynamics for LWR Power Plant

International Nuclear Information System (INIS)

Fuller, L.C.

1979-01-01

1 - Description of problem or function: ORCENT-2 performs heat and mass balance calculations at valves-wide-open design conditions, maximum guaranteed rating conditions, and an approximation of part-load conditions for steam turbine cycles supplied with throttle steam, characteristic of contemporary light-water reactors. The program handles both condensing and back-pressure turbine exhaust arrangements. Turbine performance calculations are based on the General Electric Company method for 1800-rpm large steam turbine- generators operating with light-water-cooled nuclear reactors. Output includes all information normally shown on a turbine-cycle heat balance diagram. 2 - Method of solution: The turbine performance calculations follow the procedures outlined in General Electric report GET-6020. ORCENT-2 utilizes the 1967 American Society of Mechanical Engineers (ASME) formulations and procedures for calculating the properties of steam, adapted for ORNL use by D.W. Altom. 3 - Restrictions on the complexity of the problem: Maxima of: 12 feed-water heaters, 5 moisture removal stages in the low-pressure turbine section. ORCENT-2 is limited to 1800-rpm tandem-compound turbine-generators with single- or double-flow high pressure sections and one, two, or three double-flow low-pressure turbine sections. Steam supply for LWR cycles should be between 900 and 1100 psia and slightly wet to 100 degrees F of initial superheat. Generator rating should be greater than 100 MVA

SMAFS, Steady-state analysis Model for Advanced Fuel cycle Schemes

International Nuclear Information System (INIS)

LEE, Kwang-Seok

2006-01-01

1 - Description of program or function: The model was developed as a part of the study, 'Advanced Fuel Cycles and Waste Management', which was performed during 2003-2005 by an ad-hoc expert group under the Nuclear Development Committee in the OECD/NEA. The model was designed for an efficient conduct of nuclear fuel cycle scheme cost analyses. It is simple, transparent and offers users the capability to track down the cost analysis results. All the fuel cycle schemes considered in the model are represented in a graphic format and all values related to a fuel cycle step are shown in the graphic interface, i.e., there are no hidden values embedded in the calculations. All data on the fuel cycle schemes considered in the study including mass flows, waste generation, cost data, and other data such as activities, decay heat and neutron sources of spent fuel and high-level waste along time are included in the model and can be displayed. The user can modify easily the values of mass flows and/or cost parameters and see the corresponding changes in the results. The model calculates: front-end fuel cycle mass flows such as requirements of enrichment and conversion services and natural uranium; mass of waste based on the waste generation parameters and the mass flow; and all costs. It performs Monte Carlo simulations with changing the values of all unit costs within their respective ranges (from lower to upper bounds). 2 - Methods: In Monte Carlo simulation, it is assumed that all unit costs follow a triangular probability distribution function, i.e., the probability that the unit cost has a value increases linearly from its lower bound to the nominal value and then decreases linearly to its upper bound. 3 - Restrictions on the complexity of the problem: The limit for the Monte Carlo iterations is the one of an Excel worksheet, i.e. 65,536

Super Phenix 1 fuel cycle, technical and economical outlooks

International Nuclear Information System (INIS)

Mougniot, J.C.; Baumier, J.; Duchatelle, L.

1982-01-01

An analysis of the costs of the various parts of the Super Phenix 1 fuel cycle is presented. The basis for calculating the mean levelized present unit cost used in French economic analyses is described. A description of the fuel cycle which follows includes the physical characteristics and management of the fuel and the costs of fuel services and raw materials. The results of calculations about Super Phenix mean levelized present fuel cycle unit cost are indicated and a comparison with two, four and six 1500 MWe units and PWR units is made. Finally conclusions are drawn about the economic possibility of FBR deployment. (U.K.)

Sea ice - Multiyear cycles and white ice

Science.gov (United States)

Ledley, T. S.

1985-01-01

The multiyear thickness cycles represent one of the interesting features of the sea ice studies performed by Semtner (1976) and Washington et al. (1976) with simple thermodynamic models of sea ice. In the present article, a description is given of results which show that the insulating effect of snow on the surface of the sea ice is important in producing these multiyear cycles given the physics included in the model. However, when the formation of white ice is included, the cycles almost disappear. White ice is the ice which forms at the snow-ice interface when the snow layer becomes thick enough to depress the ice below the water level. Water infiltrates the snow by coming through the ice at leads and generally freezes there, forming white ice.

Aspects of the fast reactors fuel cycle

International Nuclear Information System (INIS)

Zouain, D.M.

1982-06-01

The fuel cycle for fast reactors, is analysed, regarding the technical aspects of the developing of the reprocessing stages and the fuel fabrication. The environmental impact of LMFBRs and the waste management of this cycle are studied. The economic aspects of the fuel cycle, are studied too. Some coments about the Brazilian fast reactors programs are done. (E.G.) [pt

Chemical Engineering Division Fuel Cycle Programs: October--December 1976

International Nuclear Information System (INIS)

Steindler, M.J.; Ader, M.; Bernstein, G.; Flynn, K.; Gerding, T.; Jardine, L.; Kullen, B.; Mecham, W.; Saunders, B.; Seefeldt, W.; Seitz, M.; Siczek, A.; Trevorrow, L.

1977-01-01

Fuel-cycle studies reported for this period include pyrochemical separation of plutonium and americium oxides from contaminated materials of construction such as steel. The actinides are partitioned to a high degree into slags that are contacted by the molten metal. Studies of advanced solvent extraction techniques focussed on the development of centrifugal contactors for use in Purex processes. A miniature contactor is to be used for performance studies applicable to larger units. Review of literature on the process chemistry of zirconium and ruthenium has been carried out to aid in improving the process when fast contactors are used. A review of information on the dispersion of reagents during accidents in reprocessing has been initiated to develop systematic data useful in identifying source terms. A review and evaluation of the encapsulation of high level waste in a metal matrix has been initiated. The data will be used to identify the state of the art and the importance of selected features of this process. Criteria for the handling of hulls are being developed on the basis of past work on the pyrophoricity of zirconium alloys and related criteria from several sources. These suggested criteria will be assembled together with the necessary technical rationalization, into a package for review by interested parties. A brief program to explore the disposal of noble gas fission products by deep-well injection has been started

Description of the RZV and RZF programs

International Nuclear Information System (INIS)

Raevskaya, V.E.; Torlin, B.Z.

1980-01-01

An instruction for running the P3B and P3F programs intended for an implementation of a one-group calculation of the neutron field in a polycell with multizone ring blocks in the P 3 approximation. The program is written in the FORTRAN language for the BESM-6 computer. Time for the calculation of one variant constitutes about 20 s for a simple cell and for double lattices for uniform blocks and 40 s - for double lattices from 30-zone blocks. 4 minutes is the maximum time required for the calculation of the 8x8 polycell consisting from 20 nonequivalent 30-zone blocks of 20 kinds

Audit of Major Defense Acquisition Programs Cycle Time

National Research Council Canada - National Science Library

Ugone, Mary

2001-01-01

... (GPRA) as indicated in the FY 2000 Annual Report of the Secretary of Defense. Specifically, we assessed whether the process and factors, used to establish the metric goal of MDAP cycle time, were valid...

Evolutive Masing model, cycling plasticity, ageing and memory effects

International Nuclear Information System (INIS)

Sidoroff, F.

1987-01-01

Many models are proposed for the mechanical description of the cyclic behaviour of metals and used for structure analysis under cyclic loading. The evolutive Masing model has been proposed (Fougeres, Sidoroff, Vincent and Waille 1985) to combine - the accuracy of hereditary models for the description of hysteresis on each cycle, - the versatility of internal variables for the state description and evolution, - a sufficient microstructural basis to make the interaction easier with microstructural investigations. The purpose of the present work is to discuss this model and to compare different evolution assumptions with respect to some memory effects (cyclic hardening and softening, multilevel tests, ageing). Attention is limited to uniaxial, rate independent elasto-plastic behaviour. (orig./GL)

Structural Analysis of Treatment Cycles Representing Transitions between Nursing Organizational Units Inferred from Diabetes

Science.gov (United States)

Dehmer, Matthias; Kurt, Zeyneb; Emmert-Streib, Frank; Them, Christa; Schulc, Eva; Hofer, Sabine

2015-01-01

In this paper, we investigate treatment cycles inferred from diabetes data by means of graph theory. We define the term treatment cycles graph-theoretically and perform a descriptive as well as quantitative analysis thereof. Also, we interpret our findings in terms of nursing and clinical management. PMID:26030296

Assessing Program Learning Objectives to Improve Undergraduate Physics Education

Science.gov (United States)

Menke, Carrie

2014-03-01

Our physics undergraduate program has five program learning objectives (PLOs) focusing on (1) physical principles, (2) mathematical expertise, (3) experimental technique, (4) communication and teamwork, and (5) research proficiency. One PLO is assessed each year, with the results guiding modifications in our curriculum and future assessment practices; we have just completed our first cycle of assessing all PLOs. Our approach strives to maximize the ease and applicability of our assessment practices while maintaining faculty's flexibility in course design and delivery. Objectives are mapped onto our core curriculum with identified coursework collected as direct evidence. We've utilized mostly descriptive rubrics, applying them at the course and program levels as well as sharing them with the students. This has resulted in more efficient assessment that is also applicable to reaccreditation efforts, higher inter-rater reliability than with other rubric types, and higher quality capstone projects. We've also found that the varied quality of student writing can interfere with our assessment of other objectives. This poster outlines our processes, resources, and how we have used PLO assessment to strengthen our undergraduate program.

Report on architecture description for the INFLO prototype.

Science.gov (United States)

2014-01-01

This report documents the Architecture Description for the implementation of the Intelligent Network Flow Optimization : (INFLO) Prototype bundle within the Dynamic Mobility Applications (DMA) portion of the Connected Vehicle Program. The : intent is...

Surveillance strategy for an extended operating cycle in commercial nuclear reactors

International Nuclear Information System (INIS)

McHenry, R.S.; Moore, T.J.; Maurer, J.H.; Todreas, N.E.

1997-01-01

The impetus for improved economic performance of commercial nuclear power plants can be partially satisfied by increasing plant capacity factors through operating cycle extension. One aspect of an operating cycle extension effort is the modification of plant surveillance programs to complete required regulatory and investment protection surveillance activities within the extended planned outage schedule. The goal of this paper is to introduce a general strategy for existing power plants to transition their surveillance programs to an extended operating cycle up to 48 months in length, and to test the feasibility of this strategy through the complete analysis of the surveillance programs at operating BWR and PWR case study plants. The reconciliation of surveillances at these plants demonstrates that surveillance performance will not preclude 48 month operating cycles. Those surveillance activities that could not be resolved to an extended cycle are identified for further study. Finally, a number of general issues are presented that should be considered before implementing a cycle extension effort

Surveillance strategy for an extended operating cycle in commercial nuclear reactors

International Nuclear Information System (INIS)

McHenry, R.S.; Moore, T.J.; Maurer, J.H.; Todreas, N.E.

1997-01-01

The impetus for improved economic performance of commercial nuclear power plants can be partially satisfied by increasing plant capacity factors through operating cycle extension. One aspect of an operating cycle extension effort is the modification of plant surveillance programs to complete required regulatory and investment protection surveillance activities within the extended planned outage schedule. The goal is to introduce a general strategy for existing power plants to transition their surveillance programs to an extended operating cycle up to 48 months in length, and to test the feasibility of this strategy through the complete analysis of the surveillance programs at operating BWR and PWR case study plants. The reconciliation of surveillances at these plants demonstrates that surveillance performance will not preclude 48 month operating cycles. Those surveillance activities that could not be resolved to an extended cycle are identified for further study. Finally, a number of general issues are presented that should be considered before implementing a cycle extension effort

Economic aspects of Dukovany NPP fuel cycle

International Nuclear Information System (INIS)

Vesely, P.; Borovicka, M.

2001-01-01

The paper discusses some aspects of high burnup program implementation at Dukovany NPP and its influence on the fuel cycle costs. Dukovany internal fuel cycle is originally designed as a three years cycle of the Out-In-In fuel reloading patterns. These reloads are not only uneconomical but they additionally increased the radiation load of the reactor pressure vessel due to high neutron leakage typical for Out-In-In loading pattern. To avoid the high neutron leakage from the core a transition to 4-year fuel cycle is started in 1987. The neutron leakage from the core is sequentially decreased by insertion of older fuel assemblies at the core periphery. Other developments in fuel cycle are: 1) increasing of enrichment in control assemblies (3.6% of U-235); 2) improvement in fuel assembly design (reduce the assembly shroud thickness from 2.1 to 1.6 mm); 3) introduction of Zr spacer grid instead of stainless steel; 4) introduction of new type of assembly with profiled enrichment with average value of 3.82%. Due to increased reactivity of the new assemblies the transition to the partial 5-year fuel cycle is required. Typical fuel loading pattern for 3, 3.5, 4 and 5-year cycles are shown in the presented paper. An evaluation of fuel cost is also discussed by using comparative analysis of different fuel cycle options. The analysis shows that introduction of the high burnup program has decrease relative fuel cycle costs

Energy research program 84

International Nuclear Information System (INIS)

1984-01-01

The energy research program 84 (EFP-84) is prepared by the Danish Ministry of Energy in order to continue the extension of the Danish energy research and development started through the former Trade Ministry's programs EM-1 (1976) and EM-2 (1978), and the Ministry of Energy's programs EFP-80, EFP-81, EFP-82 and EFP-83. The new program is a continuation of the activities in the period 1984-86 with a total budget of 112 mio. DKK. The program gives a brief description of background, principles, organization and financing, and a detailed description of each research area. (ln)

Energy research program 83

International Nuclear Information System (INIS)

1983-01-01

The energy research program 83 (EFP-83) is prepared by the Danish Ministry of Energy in order to continue the extension of the Danish energy research and development started through the former Trade Ministry's programs EM-1 (1976) and EM-2 (1978), and the Ministry of Energy's programs EFP-80, EFP-81 and EFP-82. The new program is a continuation of the activities in the period 1983-85 with a total budget of 111 mio. DKK. The program gives a brief description of background, principles, organization and financing, and a detailed description of each research area. (ln)

Energy research program 85

International Nuclear Information System (INIS)

1985-01-01

The energy research program 85 (EFP-85) is prepared by the Danish Ministry of Energy in order to continue the extension of the Danish energy research and development started through the former Trade Ministry's programs EM-1 (1976) and EM-2 (1978), and Ministry of Energy's programs EFP-80, EFP-81, EFP-82, EFP-83, and EFP-84. The new program is a continuation of the activities in the period 1985-87 with a total budget of 110 mio. DKK. The program gives a brief description of background, principles, organization and financing, and a detailed description of each research area. (ln)

Actinide production in different HTR-fuel cycle concepts

International Nuclear Information System (INIS)

Filges, D.; Hecker, R.; Mirza, N.; Rueckert, M.

1978-01-01

At the 'Institut fuer Reaktorentwicklung der Kernforschungsanlage Juelich' the production of α-activities in the following HTR-OTTO cycle concepts were studied: 1. standard HTR cycle (U-Th); 2. low enriched HTR cycle (U-Pu); 3. near breeder HTR cycle (U-Th); 4. combined system (conventional and near breeder HTR). The production of α-activity in HTR Uranium-Thorium fuel cycles has been investigated and compared with the standard LWR cycles. The production of α-activity in HTR Uranium-Thorium fuel cycles has been investigated and compared with the standard LWR cycles. The calculations were performed by the short depletion code KASCO and the well-known ORIGEN program

Nuclear fuel cycle risk assessment: survey and computer compilation of risk-related literature

International Nuclear Information System (INIS)

Yates, K.R.; Schreiber, A.M.; Rudolph, A.W.

1982-10-01

The US Nuclear Regulatory Commission has initiated the Fuel Cycle Risk Assessment Program to provide risk assessment methods for assistance in the regulatory process for nuclear fuel cycle facilities other than reactors. Both the once-through cycle and plutonium recycle are being considered. A previous report generated by this program defines and describes fuel cycle facilities, or elements, considered in the program. This report, the second from the program, describes the survey and computer compilation of fuel cycle risk-related literature. Sources of available information on the design, safety, and risk associated with the defined set of fuel cycle elements were searched and documents obtained were catalogued and characterized with respect to fuel cycle elements and specific risk/safety information. Both US and foreign surveys were conducted. Battelle's computer-based BASIS information management system was used to facilitate the establishment of the literature compilation. A complete listing of the literature compilation and several useful indexes are included. Future updates of the literature compilation will be published periodically. 760 annotated citations are included

Energy research program 80

International Nuclear Information System (INIS)

1980-01-01

The energy research program 80 contains an extension of the activities for the period 1980-82 within a budget of 100 mio.kr., that are a part of the goverment's employment plan for 1980. The research program is based on a number of project proposals, that have been collected, analysed, and supplemented in October-November 1979. This report consists of two parts. Part 1: a survey of the program, with a brief description of the background, principles, organization and financing. Part 2: Detailed description of the different research programs. (LN)

Isochronous cyclotron closed equilibrium orbit calculation program description

International Nuclear Information System (INIS)

Kiyan, I.N.; Vorozhtsov, S.B.; Tarashkevich, R.

2003-01-01

The Equilibrium Orbit Research Program - EORP, written in C++ with the use of Visual C++ is described. The program is intended for the calculation of the particle rotation frequency and particle kinetic energy in the closed equilibrium orbits of an isochronous cyclotron, where the closed equilibrium orbits are described through the radius and particle momentum angle: r eo (θ) and φ p (θ). The program algorithm was developed on the basis of articles, lecture notes and original analytic calculations. The results of calculations by the EORP were checked and confirmed by using the results of calculations by the numerical methods. The discrepancies between the EORP results and the numerical method results for the calculations of the particle rotation frequency and particle kinetic energy are within the limits of ±1·10 -4 . The EORP results and the numerical method results for the calculations of r eo (θ) and φ p (θ) practically coincide. All this proves the accuracy of calculations by the EORP for the isochronous cyclotrons with the azimuthally varied fields. As is evident from the results of calculations, the program can be used for the calculations of both straight - sector and spiral-sector isochronous cyclotrons. (author)

The Role of Values, Moral Norms, and Descriptive Norms in Building Occupant Responses to an Energy-Efficiency Pilot Program and to Framing of Related Messages

Science.gov (United States)

Arpan, Laura M.; Barooah, Prabir; Subramany, Rahul

2015-01-01

This study examined building occupants' responses associated with an occupant-based energy-efficiency pilot in a university building. The influence of occupants' values and norms as well as effects of two educational message frames (descriptive vs. moral norms cues) on program support were tested. Occupants' personal moral norm to conserve energy…

TASAC a computer program for thermal analysis of severe accident conditions. Version 3/01, Dec 1991. Model description and user's guide

International Nuclear Information System (INIS)

Stempniewicz, M.; Marks, P.; Salwa, K.

1992-06-01

TASAC (Thermal Analysis of Severe Accident Conditions) is computer code developed in the Institute of Atomic Energy written in FORTRAN 77 for the digital computer analysis of PWR rod bundle behaviour during severe accident conditions. The code has the ability to model an early stage of core degradation including heat transfer inside the rods, convective and radiative heat exchange as well as cladding interactions with coolant and fuel, hydrogen generation, melting, relocations and refreezing of fuel rod materials with dissolution of UO 2 and ZrO 2 in liquid phase. The code was applied for the simulation of International Standard Problem number 28, performed on PHEBUS test facility. This report contains the program physical models description, detailed description of input data requirements and results of code verification. The main directions for future TASAC code development are formulated. (author). 20 refs, 39 figs, 4 tabs

Implementing risk-informed life-cycle design

International Nuclear Information System (INIS)

Hill, Ralph S.

2009-01-01

This paper describes a design process based on risk-informed probabilistic design methodologies that cover a facility's life-cycle from start of conceptual design through decontamination and decommissioning. The concept embodies use of probabilistic risk assessments to establish target reliabilities for facility systems and components. The target reliabilities are used for system based code margin exchange and performance simulation analyses to optimize design over all phases (design, construction, operation and decommissioning) of a facility's life-cycle. System based code margin exchange reduces excessive level of construction margins for passive components to appropriate levels resulting in a more flexible structure of codes and standards that improves facility reliability and cost. System and subsystem simulation analyses determine the optimum combination of initial system and component construction reliability, maintenance frequency, and inspection frequency for both active and passive components. The paper includes a description of these risk-informed life-cycle design processes, a summary of work being done, and a discussion of additional work needed to implement the process.

Descriptions of reference LWR facilities for analysis of nuclear fuel cycles. Appendixes

International Nuclear Information System (INIS)

Schneider, K.J.; Kabele, T.J.

1979-09-01

The appendixes present the calculations that were used to derive the release factors discussed for each fuel cycle facility in Volume I. Appendix A presents release factor calculations for a surface mine, underground mine, milling facility, conversion facility, diffusion enrichment facility, fuel fabrication facility, PWR, BWR, and reprocessing facility. Appendix B contains additional release factors calculated for a BWR, PWR, and a reprocessing facility. Appendix C presents release factors for a UO 2 fuel fabrication facility

Ontology learning from interpretations in lightweight description logics

CSIR Research Space (South Africa)

Klarman, S

2015-08-01

Full Text Available International Conference on Inductive Logic programming (ILP), Kyoto, Japan, 20-22 August 2015 Ontology Learning from Interpretations in Lightweight Description Logics Szymon Klarman1 and Katarina Britz2 1 Department of Computer Science, Brunel...

A report to Congress Nuclear Regulatory Research: Project descriptions for FY88

International Nuclear Information System (INIS)

1988-08-01

This report has been written in response to a request of the United States Congress that the Nuclear Regulatory Commission prepare and submit to the Congress a summary description of its research projects. Commercial contracts and research efforts at the Department of Energy (DOE) laboratories are assigned a five-digit financial number (FIN). This report provides a project descriptions for each FIN number. The project descriptions are divided into five major sections called program areas. These areas are: integrity of reactor components, prevent damage to reactor cores, reactor containment safety, confirming safety of nuclear waste disposal, and resolving safety issues and developing regulations. An explanation of each program area is given in an overview at the beginning of each section

Airbreathing combined cycle engine systems

Science.gov (United States)

Rohde, John

1992-01-01

The Air Force and NASA share a common interest in developing advanced propulsion systems for commercial and military aerospace vehicles which require efficient acceleration and cruise operation in the Mach 4 to 6 flight regime. The principle engine of interest is the turboramjet; however, other combined cycles such as the turboscramjet, air turborocket, supercharged ejector ramjet, ejector ramjet, and air liquefaction based propulsion are also of interest. Over the past months careful planning and program implementation have resulted in a number of development efforts that will lead to a broad technology base for those combined cycle propulsion systems. Individual development programs are underway in thermal management, controls materials, endothermic hydrocarbon fuels, air intake systems, nozzle exhaust systems, gas turbines and ramjet ramburners.

Energy research program 86

International Nuclear Information System (INIS)

1986-01-01

The energy research program 86 (EFP-86) is prepared by the Danish Ministry of Energy in order to continue the extension of the Danish energy research and development started through the former Trade Ministry's programs EM-1 (1976) and EM-2 (1978), and the Ministry of Energy's programs EFP-80, EFP-81, EFP-82, EFP-83, EFP-84, and EFP-85. The new program is a continuation of the activities in the period 1986-88 with a total budget of 116 mio. DKK. The program gives a brief description of background, principles, organization and financing, and a detailed description of each research area. (ln)

ARC System fuel cycle analysis capability, REBUS-2

International Nuclear Information System (INIS)

Hosteny, R.P.

1978-10-01

A detailed description is given of the ARC System fuel cycle modules FCI001, FCC001, FCC002, and FCC003 which form the fuel cycle analysis modules of the ARC System. These modules, in conjunction with certain other modules of the ARC System previously described in documents of this series, form the fuel cycle analysis system called REBUS-2. The physical model upon which the REBUS-2 fuel cycle modules are based and the calculational approach used in solving this model are discussed in detail. The REBUS-2 system either solves for the infinite time (i.e., equilibrium) operating conditions of a fuel recycle system under fixed fuel management conditions, or solves for the operating conditions during each of a series of explicitly specified (i.e., nonequilibrium) sequence of burn cycles. The code has the capability to adjust the fuel enrichment, the burn time, and the control poison requirements in order to satisfy user specified constraints on criticality, discharge fuel burnup, or to give the desired multiplication constant at some specified time during the reactor operation

ARC System fuel cycle analysis capability, REBUS-2

Energy Technology Data Exchange (ETDEWEB)

Hosteny, R.P.

1978-10-01

A detailed description is given of the ARC System fuel cycle modules FCI001, FCC001, FCC002, and FCC003 which form the fuel cycle analysis modules of the ARC System. These modules, in conjunction with certain other modules of the ARC System previously described in documents of this series, form the fuel cycle analysis system called REBUS-2. The physical model upon which the REBUS-2 fuel cycle modules are based and the calculational approach used in solving this model are discussed in detail. The REBUS-2 system either solves for the infinite time (i.e., equilibrium) operating conditions of a fuel recycle system under fixed fuel management conditions, or solves for the operating conditions during each of a series of explicitly specified (i.e., nonequilibrium) sequence of burn cycles. The code has the capability to adjust the fuel enrichment, the burn time, and the control poison requirements in order to satisfy user specified constraints on criticality, discharge fuel burnup, or to give the desired multiplication constant at some specified time during the reactor operation.

A multi-cycle optimization approach for low leakage in-core fuel management

International Nuclear Information System (INIS)

Cheng Pingdong; Shen Wei

1999-01-01

A new approach was developed to optimize pressurized waster reactor (PWR) low-leakage multi-cycle reload core design. The multi-cycle optimization process is carried out by the following three steps: The first step is a linear programming in search for an optimum power sharing distribution and optimum cycle length distribution for the successive several cycles to yield maximum multi-cycle total cycle length. In the second step, the fuel arrangement and burnable poison (BP) assignment are decoupled by using Haling power distribution and the optimum fuel arrangement is determined at the EOL in the absence of all BPs by employing a linear programming method or direct search method with objective function to force the calculated cycle length to be as close as possible to the optimum single cycle length obtained in the first step and with optimum power sharing distribution as additional constraints during optimization. In the third step, the BP assignment is optimized by the Flexible Tolerance Method (FTM) or linear programming method using the number of BP rods as control variable. The technology employed in the second and third steps was the usual decoupling method used in low-leakage core design. The first step was developed specially for multi-cycle optimization design and discussed in detail. Based on the proposed method a computer code MCYCO was encoded and tested for Qinshan Nuclear Power Plant (QNPP) low leakage reload core design. The multi-cycle optimization method developed, together with the program MCYCO, provides an applicable tool for solving the PWR low leakage reload core design problem

Monitored Retrievable Storage conceptual system studies: closed-cycle vault

International Nuclear Information System (INIS)

Washington, J.A.; Ganley, J.T.

1984-02-01

The Nuclear Waste Policy Act of 1982 requires the DOE to submit a proposal to Congress by June 1985 for the construction of one or more Monitored Retrieval Storage (MRS) facilities. In response, the DOE initiated studies to develop system descriptions and cost estimates for preconceptual designs of storage concepts suitable for use at MRS facilities. This report provides a system description and cost estimates for a Closed-Cycle Vault (CCV) MRS facility. The facility description is divided into four parts: (1) the R and H area, (2) the interface facility, (3) the on-site transport system, and (4) the storage system. The MRS facility has been designed to meet handling rates of 1800 and 3000 MTU/yr. The corresponding peak inventories are 15,000 and 72,000 MTU. Three types of cases were considered, based on the material to be stored: (1) Spent fuel only; (2) HLW and TRU waste; and (3) HLW only. For each of these three types, a cost estimate was done for a 15,000 and a 72,000 MTU facility, resulting in six different cost estimates. Section 4 presents the cost analysis of the CCV MRS system. Tables 4-2 through 4-7 give the construction or capital costs for the six cases. Tables 4-8 through 4-13 show the total discounted life-cycle costs for each of the six cases. These life-cycle costs include operating and decommissioning costs. These tables also show the time distribution of the capital costs. Table 2-1 summarizes the capital, operating, and discounted costs for the six cases studied. 2 references, 15 figures, 18 tables

Nuclear fuel cycle system analysis

International Nuclear Information System (INIS)

Ko, W. I.; Kwon, E. H.; Kim, S. G.; Park, B. H.; Song, K. C.; Song, D. Y.; Lee, H. H.; Chang, H. L.; Jeong, C. J.

2012-04-01

The nuclear fuel cycle system analysis method has been designed and established for an integrated nuclear fuel cycle system assessment by analyzing various methodologies. The economics, PR(Proliferation Resistance) and environmental impact evaluation of the fuel cycle system were performed using improved DB, and finally the best fuel cycle option which is applicable in Korea was derived. In addition, this research is helped to increase the national credibility and transparency for PR with developing and fulfilling PR enhancement program. The detailed contents of the work are as follows: 1)Establish and improve the DB for nuclear fuel cycle system analysis 2)Development of the analysis model for nuclear fuel cycle 3)Preliminary study for nuclear fuel cycle analysis 4)Development of overall evaluation model of nuclear fuel cycle system 5)Overall evaluation of nuclear fuel cycle system 6)Evaluate the PR for nuclear fuel cycle system and derive the enhancement method 7)Derive and fulfill of nuclear transparency enhancement method The optimum fuel cycle option which is economical and applicable to domestic situation was derived in this research. It would be a basis for establishment of the long-term strategy for nuclear fuel cycle. This work contributes for guaranteeing the technical, economical validity of the optimal fuel cycle option. Deriving and fulfillment of the method for enhancing nuclear transparency will also contribute to renewing the ROK-U.S Atomic Energy Agreement in 2014

Rapid freeze-drying cycle optimization using computer programs developed based on heat and mass transfer models and facilitated by tunable diode laser absorption spectroscopy (TDLAS).

Science.gov (United States)

Kuu, Wei Y; Nail, Steven L

2009-09-01

Computer programs in FORTRAN were developed to rapidly determine the optimal shelf temperature, T(f), and chamber pressure, P(c), to achieve the shortest primary drying time. The constraint for the optimization is to ensure that the product temperature profile, T(b), is below the target temperature, T(target). Five percent mannitol was chosen as the model formulation. After obtaining the optimal sets of T(f) and P(c), each cycle was assigned with a cycle rank number in terms of the length of drying time. Further optimization was achieved by dividing the drying time into a series of ramping steps for T(f), in a cascading manner (termed the cascading T(f) cycle), to further shorten the cycle time. For the purpose of demonstrating the validity of the optimized T(f) and P(c), four cycles with different predicted lengths of drying time, along with the cascading T(f) cycle, were chosen for experimental cycle runs. Tunable diode laser absorption spectroscopy (TDLAS) was used to continuously measure the sublimation rate. As predicted, maximum product temperatures were controlled slightly below the target temperature of -25 degrees C, and the cascading T(f)-ramping cycle is the most efficient cycle design. In addition, the experimental cycle rank order closely matches with that determined by modeling.

INTEGRATING ROUNDTABLE BRAINSTORMING INTO TEAM PAIR SOLO TECHNIQUE FOR IMPROVING STUDENTS’ PARTICIPATION IN WRITING OF DESCRIPTIVE TEXTS

Directory of Open Access Journals (Sweden)

author Sutarno

2015-01-01

Full Text Available The objectives of the study are to find out the application of integration of roundtable brainstorming into team pair solo technique in writing of descriptive texts and to investigate the improvement of students’ participation and achievement after taught by using the integration of the techniques. This study was an action research which was carried out through a preliminary study, first and second cycle activities. The subjects of this study were VII grade students of State Junior High School no.1 Semaka, Tanggamus, Lampung consisting of thirty two students. To collect the data, the researcher used instruments inform of interview, observation sheets, writing tests, and questionnaires. The findings of the research showed that students’ participation improved from the preliminary study, first and second cycle. In the preliminary study there were twenty six students classified as poor, six students classified as fair and no student classified as good in participation. While in the first cycle there were three students classified as fair and twenty nine students classified as good in participation and in the second cycle all students were classified as good in participation. The students’ writing also improved. The average score of students writing in the preliminary study was 53.31, first cycle was 64.41, and second cycle was 72.56.Key words: Roundtable Brainstorming, Team Pair Solo Technique, Students’ Participation, Writing Descriptive Texts

Unified description of structure and reactions: implementing the nuclear field theory program

International Nuclear Information System (INIS)

Broglia, R A; Bortignon, P F; Barranco, F; Vigezzi, E; Idini, A; Potel, G

2016-01-01

The modern theory of the atomic nucleus results from the merging of the liquid drop model of Niels Bohr and Fritz Kalckar, and of the shell model of Marie Goeppert Meyer and Hans Jensen. The first model contributed the concepts of collective excitations. The second, those of independent-particle motion. The unification of these apparently contradictory views in terms of the particle-vibration and particle-rotation couplings carried out by Aage Bohr and Ben Mottelson has allowed for an ever more complete, accurate and detailed description of nuclear structure. Nuclear field theory (NFT), developed by the Copenhagen–Buenos Aires collaboration, provided a powerful quantal embodiment of this unification. Reactions are not only at the basis of quantum mechanics (statistical interpretation, Max Born), but also the specific tools to probe the atomic nucleus. It is then natural that NFT is being extended to deal with processes which involve the continuum in an intrinsic fashion, so as to be able to treat them on an equal footing with those associated with bound states (structure). As a result, spectroscopic studies of transfer to continuum states could eventually make use of the NFT rules, properly extended to take care of recoil effects. In the present contribution we review the implementation of the NFT program of structure and reactions, setting special emphasis on open problems and outstanding predictions. (invited comment)

A review of pediatric dentistry program websites: what are applicants learning about our programs?

Science.gov (United States)

Lin, Jenn-Yih; Lee, Jung; Davidson, Bo; Farquharson, Kara; Shaul, Cheryl; Kim, Sara

2010-06-01

The purpose of this study was twofold: 1) to examine website content provided by U.S. and Canadian pediatric dentistry residency programs, and 2) to understand aspects of program websites that dental students report to be related to their interests. Sixty-eight program websites were reviewed by five interprofessional evaluators. A thirty-six-item evaluation form was organized into 1) program descriptive items listed on the American Academy of Pediatric Dentistry (AAPD) website (n=21); 2) additional program descriptive items not listed on the AAPD website but of interest (n=9); and 3) items related to website interface design (n=5). We also surveyed fifty-four dental students regarding their interest in various aspects of program descriptions. The results of this study suggest that pediatric dentistry residency programs in general tend to provide identical or less information than what is listed on the AAPD website. The majority of respondents (76 percent) reported that residency program websites would be their first source of information about advanced programs. The greatest gap between the available website information and students' interests exists in these areas: stipend and tuition information, state licensure, and program strengths. Pediatric dentistry residency programs underutilize websites as a marketing and recruitment tool and should incorporate more information in areas of students' priority interests.

Preliminary estimates of the total-system cost for the restructured program: An addendum to the May 1989 analysis of the total-system life cycle cost for the Civilian Radioactive Waste Management Program

International Nuclear Information System (INIS)

1990-12-01

The total-system life-cycle cost (TSLCC) analysis for the Department of Energy's (DOE) Civilian Radioactive Waste Management Program is an ongoing activity that helps determine whether the revenue-producing mechanism established by the Nuclear Waste Policy Act of 1982 - a fee levied on electricity generated and sold by commercial nuclear power plants - is sufficient to cover the cost of the program. This report provides cost estimates for the sixth annual evaluation of the adequacy of the fee. The costs contained in this report represent a preliminary analysis of the cost impacts associated with the Secretary of Energy's Report to Congress on Reassessment of the Civilian Radioactive Waste Management Program issued in November 1989. The major elements of the restructured program announced in this report which pertain to the program's life-cycle costs are: a prioritization of the scientific investigations program at the Yucca Mountain candidate site to focus on identification of potentially adverse conditions, a delay in the start of repository operations until 2010, the start of limited waste acceptance at the monitored retrievable storage (MRS) facility in 1998, and the start of waste acceptance at the full-capability MRS facility in 2,000. Based on the restructured program, the total-system cost for the system with a repository at the candidate site at Yucca Mountain in Nevada, a facility for monitored retrievable storage (MRS), and a transportation system is estimated at $26 billion (expressed in constant 1988 dollars). In the event that a second repository is required and is authorized by the Congress, the total-system cost is estimated at $34 to $35 billion, depending on the quantity of spent fuel and high-level waste (HLW) requiring disposal. 17 figs., 17 tabs

Replacing single frozen-thawed euploid embryos in a natural cycle in ovulatory women may increase live birth rates compared to medicated cycles in anovulatory women.

Science.gov (United States)

Melnick, Alexis P; Setton, Robert; Stone, Logan D; Pereira, Nigel; Xu, Kangpu; Rosenwaks, Zev; Spandorfer, Steven D

2017-10-01

The goal of this study was to compare pregnancy outcomes between natural frozen embryo transfer (FET) cycles in ovulatory women and programmed FET cycles in anovulatory women after undergoing in vitro fertilization with preimplantation genetic screening (IVF-PGS). This was a retrospective cohort study performed at an academic medical center. Patients undergoing single FET IVF-PGS cycles between October 2011 and December 2014 were included. Patients were stratified by type of endometrial replacement: programmed cycles with estrogen/progesterone replacement and natural cycles. IVF-PGS with 24-chromosome screening was performed on all included patients. Those patients with euploid embryos had single embryo transfer in a subsequent FET. The primary study outcome was live birth/ongoing pregnancy rate. Secondary outcomes included implantation, biochemical pregnancy, and miscarriage rates. One hundred thirteen cycles met inclusion criteria: 65 natural cycles and 48 programmed cycles. The programmed FET group was younger (35.9 ± 4.5 vs. 37.5 ± 3.7, P = 0.03) and had a higher AMH (3.95 ± 4.2 vs. 2.37 ± 2.4, P = 0.045). The groups were similar for BMI, gravidity, parity, history of uterine surgery, and incidence of Asherman's syndrome. There was also no difference in embryo grade at biopsy or transfer, and proportion of day 5 and day 6 transfers. Implantation rates were higher in the natural FET group (0.66 ± 0.48 vs. 0.44 ± 0.50, P = 0.02). There was no difference in the rates of biochemical pregnancy or miscarriage. After controlling for age, live birth/ongoing pregnancy rate was higher in natural FETs with an adjusted odds ratio of 2.68 (95% CI 1.22-5.87). Natural FET in ovulatory women after IVF-PGS is associated with increased implantation and live birth rates compared to programmed FET in anovulatory women. Further investigation is needed to determine whether these findings hold true in other patient cohorts.

Quality Assurance Requirements and Description

International Nuclear Information System (INIS)

Ram Murthy

2002-01-01

The Quality Assurance Requirements and Description (QARD) is the principal Quality Assurance (QA) document for the Civilian Radioactive Waste Management Program (Program). It establishes the minimum requirements for the QA program [INTRODUCTION :1p2s (NOT A REQUIREMENT)]. The QARD contains regulatory requirements and program commitments necessary for the development of an effective QA program [INTRODUCTION :1p3s (NOT A REQUIREMENT)]. Implementing documents must be based on, and be consistent with the QARD. The QARD applies to the following: (1) Acceptance of spent nuclear fuel and high-level waste. (2) Transport of spent nuclear fuel and high-level waste. (3) Storage of spent nuclear fuel through receipt of storage cask certification or a facility operating license. (4) Monitored Geologic Repository, including the site characterization activities [Exploratory Studies Facility (ESF) and surface based testing], through receipt of an operating license. (5) High-level waste form development through qualification, production, and acceptance. (6) Characterization of DOE spent nuclear fuel, and conditioning through acceptance of DOE spent nuclear fuel. Section 2.0, Quality Assurance Program, defines in greater detail criteria for determining work subject to the QARD

Assessment of the external costs of the coal fuel cycle and the wind energy cycle in Spain

International Nuclear Information System (INIS)

Linares, P.; Montes, J.; Saez, R.M.

1995-09-01

This study is part of the ExternE Project, a joint effort of the European Commission and the US Dept. of Energy to assess the externalities of different fuel cycles, and quantify them in monetary terms, as kWh price adders. For Spain, this assessment has been carried out for a coal plant hypothetically sited in Valdecaballeros, in Southwestern Spain, and for an existing farm in Cabo Villano, in the Northwestern corner. In this first stage, only environmental externalities have been assessed. The first section contains a description of the methodology used in the European project, based mostly on a damage function approach, and its adaptation to Spanish conditions. In the last section, this methodology has been applied to the fuel cycles mentioned. The impacts assessed have been, for the coal fuel cycle, health effects, agricultural and forest production losses, and global warming. For wind energy, the main impacts considered have been noise, loss of visual amenity, accidents and global warning. The results obtained can only be considered as underestimates, as there are still impacts that have not been assessed or quantified, specially for the coal fuel cycle. Thus, further research is needed for a complete assessment

Identification of low cycle fatigue parameters

Directory of Open Access Journals (Sweden)

Balda M.

2009-12-01

Full Text Available The article describes a new approach to the processing of experimental data coming from low-cycle fatigue (LCF tests. The data may be either tables from the standard tests, or a time series of loading processes and corresponding numbers of cycles to damage. A new method and a program for the evaluation of material parameters governing the material behavior under a low cycle loading have been developed. They exploit a minimization procedure for an appropriate criterion function based on differences of measured and evaluated damages.

Isochronous Cyclotron Closed Equilibrium Orbit Calculation Program Description

CERN Document Server

Kian, I N; Tarashkevich, R

2003-01-01

The Equilibrium Orbit Research Program - EORP, written in C++ with the use of Visual C++ is described. The program is intended for the calculation of the particle rotation frequency and particle kinetic energy in the closed equilibrium orbits of an isochronous cyclotron, where the closed equilibrium orbits are described through the radius and particle momentum angle: r_{eo}(\\theta) and \\varphi_{p}(\\theta). The program algorithm was developed on the basis of articles, lecture notes and original analytic calculations. The results of calculations by the EORP were checked and confirmed by using the results of calculations by the numerical methods. The discrepancies between the EORP results and the numerical method results for the calculations of the particle rotation frequency and particle kinetic energy are within the limits of \\pm1\\cdot10^{-4}. The EORP results and the numerical method results for the calculations of r_{eo}(\\theta) and \\varphi_{p}(\\theta) practically coincide. All this proves the accuracy of ca...

Office of radiation and indoor air: Program description

International Nuclear Information System (INIS)

1993-06-01

The goal of the Environmental Protection Agency's (EPA) Office of Radiation and Indoor Air is to protect the public and the environment from exposures to radiation and indoor air pollutants. The Office develops protection criteria, standards, and policies and works with other programs within EPA and other agencies to control radiation and indoor air pollution exposures; provides technical assistance to states through EPA's regional offices and other agencies having radiation and indoor air protection programs; directs an environmental radiation monitoring program; responds to radiological emergencies; and evaluates and assesses the overall risk and impact of radiation and indoor air pollution. The Office is EPA's lead office for intra- and interagency activities coordinated through the Committee for Indoor Air Quality. It coordinates with and assists the Office of Enforcement in enforcement activities where EPA has jurisdiction. The Office disseminates information and works with state and local governments, industry and professional groups, and citizens to promote actions to reduce exposures to harmful levels of radiation and indoor air pollutants

CANDU fuel cycle options in Korea

International Nuclear Information System (INIS)

Boczar, P. G.; Fehrenbach, P. J.; Meneley, D. A.

1996-01-01

There are many reasons for countries embarking on a CANDU R program to start with the natural uranium fuel cycle. Simplicity of fuel design, ease of fabrication, and ready availability of natural uranium all help to localize the technology and to reduce reliance on foreign technology. Nonetheless, at some point, the incentives for using natural uranium fuel may be outweighed by the advantages of alternate fuel cycles. The excellent neutron economy, on-line refuelling, and simple fuel-bundle design provide an unsurpassed degree of fuel-cycle flexibility in CANDU reactors. The easiest first step in CANDU fuel-cycle evolution may be the use of slightly enriched uranium (SEU), including recovered uranium from reprocessed LWR spent fuel. Relatively low enrichment (up to 1.2%) will result in a two- to three-fold reduction in the quantity of spent fuel per unit energy production, reductions in fuel-cycle costs, and greater flexibility in the design of new reactors. The CANFLEX (CANDU FLEXible) fuel bundle would be the optimal fuel carrier. A country that has both CANDU and PWR reactors can exploit the natural synergism between these two reactor types to minimize overall waste production, and maximize energy derived from the fuel. This synergism can be exploited through several different fuel cycles. A high burnup CANDU MOX fuel design could be used to utilize plutonium from conventional reprocessing or more advanced reprocessing options (such as co-processing). DUPIC (Direct Use of Spent PWR Fuel In CANDU) represents a recycle option that has a higher degree of proliferation resistance than dose conventional reprocessing, since it uses only dry processes for converting spent PWR fuel into CANDU fuel, without separating the plutonium. Good progress is being made in the current KAERI, AECL, and U. S. Department of State program in demonstrating the technical feasibility of DUPIC. In the longer term, CANDU reactors offer even more dramatic synergistic fuel cycles with PWR or

DETERMINING THE COMPOSITION OF HIGH TEMPERATURE COMBUSTION PRODUCTS OF FOSSIL FUEL BASED ON VARIATIONAL PRINCIPLES AND GEOMETRIC PROGRAMMING

Directory of Open Access Journals (Sweden)

Velibor V Vujović

2011-01-01

Full Text Available This paper presents the algorithm and results of a computer program for calculation of complex equilibrium composition for the high temperature fossil fuel combustion products. The method of determining the composition of high temperatures combustion products at the temperatures appearing in the open cycle MHD power generation is given. The determination of combustion product composition is based on minimization of the Gibbs free energy. The number of equations to be solved is reduced by using variational principles and a method of geometric programming and is equal to the sum of the numbers of elements and phases. A short description of the computer program for the calculation of the composition and an example of the results are also given.

Hybrid Combined Cycles with Biomass and Waste Fired Bottoming Cycle - a Literature Study

Energy Technology Data Exchange (ETDEWEB)

Petrov, Miroslav P.

2002-02-01

incinerators is probably the option with the greatest efficiency improvement potential, within the reasonable cost and scale limits. Furthermore, a State-of-Art report is included in the study as a separate chapter. Descriptions of existing hybrid combined cycle installations with biofuel-fired bottoming cycle in Sweden and its surrounding countries are compiled in it. The presentation shows that hybrid combined cycles are a standard technology in many respects. These specific configurations have been chosen as the most rewarding ones out of various alternatives and have proved their advantages in commercial operation. The major research project following this literature study will focus on investigation of possible efficiency improvement of biomass energy utilization by application of hybrid configurations with natural gas fired gas turbine and internal combustion engines as topping cyclesof curve fitting procedures)

Integrated Project Management System description

International Nuclear Information System (INIS)

1994-09-01

The Integrated Program Management System (IPMS) Description is a ''working'' document that describes the work processes of the Uranium Mill Tailings Remedial Action Project Office (UMTRA) and IPMS Group. This document has undergone many revisions since the UMTRA Project began; this revision not only updates the work processes but more clearly explains the relationships between the Project Office, contractors, and other participants. The work process flow style has been revised to better describe Project work and the relationships of participants. For each work process, more background and guidance on ''why'' and ''what is expected'' is given. For example, a description of activity data sheets has been added in the work organization and the Project performance and reporting processes, as well as additional detail about the federal budget process and funding management and improved flow charts and explanations of cost and schedule management. A chapter has been added describing the Cost Reduction/Productivity Improvement Program. The Change Control Board (CCB) procedures (Appendix A) have been updated. Project critical issues meeting (PCIM) procedures have been added as Appendix B. Budget risk assessment meeting procedures have been added as Appendix C. These appendices are written to act as stand-alone documentation for each process. As the procedures are improved and updated, the documentation can be updated separately

Quantifying Cost Risk Early in the Life Cycle

International Nuclear Information System (INIS)

Mar, B.

2004-01-01

A new method for analyzing life cycle cost risk on large programs is presented that responds to an increased emphasis on improving sustainability for long-term programs. This method provides better long-term risk assessment and risk management techniques. It combines standard Monte Carlo analysis of risk drivers and a new data-driven method developed by the BMDO. The approach permits quantification of risks throughout the entire life cycle without resorting to difficult to support subjective methods. The BMDO methodology is shown to be relatively straightforward to apply to a specific component or process within a project using standard technical risk assessment methods. The total impact on system is obtained using the program WBS, which allows for the capture of correlated risks shared by multiple WBS items. Once the correlations and individual component risks are captured, a Monte Carlo simulation can be run using a modeling tool such as ANALYTICA to produce the overall life cycle cost risk

Federal Geothermal Research Program Update, FY 2000

Energy Technology Data Exchange (ETDEWEB)

Renner, Joel Lawrence

2001-08-01

The Department of Energy's Geothermal Program serves two broad purposes: 1) to assist industry in overcoming near-term barriers by conducting cost-shared research and field verification that allows geothermal energy to compete in today's aggressive energy markets; and 2) to undertake fundamental research with potentially large economic payoffs. The four categories of work used to distinguish the research activities of the Geothermal Program during FY 2000 reflect the main components of real-world geothermal projects. These categories form the main sections of the project descriptions in this Research Update. Exploration Technology research focuses on developing instruments and techniques to discover hidden hydrothermal systems and to explore the deep portions of known systems. Research in geophysical and geochemical methods is expected to yield increased knowledge of hidden geothermal systems. Reservoir Technology research combines laboratory and analytical investigations with equipment development and field testing to establish practical tools for resource development and management for both hydrothermal reservoirs and enhanced geothermal systems. Research in various reservoir analysis techniques is generating a wide range of information that facilitates development of improved reservoir management tools. Drilling Technology focuses on developing improved, economic drilling and completion technology for geothermal wells. Ongoing research to avert lost circulation episodes in geothermal drilling is yielding positive results. Conversion Technology research focuses on reducing costs and improving binary conversion cycle efficiency, to permit greater use of the more abundant moderate-temperature geothermal resource, and on the development of materials that will improve the operating characteristics of many types of geothermal energy equipment. Increased output and improved performance of binary cycles will result from investigations in heat cycle research.

Cycle for Science: An informal outreach program connecting K-12 students with renewable energy and physics through miniature 3D-printed, solar-powered bicycles

Science.gov (United States)

Woods-Robinson, R.; Case, E.

2017-12-01

Engaging communities with renewable energy is key to fighting climate change. Cycle for Science, an innovative STEM outreach organization, has reached more than 3,000 K-12 students across the United States by bringing early-career female scientists into classrooms to teach basic physics and solar energy engineering through hands-on, DIY science activities. We designed a fleet of miniature, 3D-printed, solar-powered bicycles called "Sol Cycles" to use as teaching tools. Traveling by bicycle, Cycle for Science has brought them to rural and urban communities across the U.S. in two major efforts so far: one traversing the country (2015), and one through central California (2017). The program involves (1) introducing the scientists and why they value science, (2) running a skit to demonstrate how electrons and photons interact inside the solar panel, (3) assembling the Sol Cycles, (4) taking students outdoors to test the effects of variables (e.g. light intensity) on the Sol Cycles' movement, (5) and debriefing about the importance of renewable energy. In addition to physics and solar energy, the lessons teach the scientific process, provide tactile engagement with science, and introduce a platform to engage students with climate change impacts. By cycling to classrooms, we provide positive examples of low-impact transportation and a unique avenue for discussing climate action. It was important that this program extend beyond the trips, so the lesson and Sol Cycle design are open source to encourage teachers and students to play, change and improve the design, as well as incorporate new exercises (e.g. could you power the bicycle by wind?). Additionally, it has been permanently added to the XRaise Lending Library at Cornell University, so teachers across the world can implement the lesson. By sharing our project at AGU, we aim to connect with other scientists, educators, and concerned citizens about how to continue to bring renewable energy lessons into classrooms.

Regulatory research and support program for 1993/1994 - project descriptions

International Nuclear Information System (INIS)

1993-01-01

The Regulatory Research and Support Program (RSP) is intended to augment and extend the Atomic Energy Control Board's regulatory program beyond the capability of in-house resources. The overall objective of the research and support program is to produce pertinent and independent information that will assist the Board and its staff in making sound, timely and credible decisions on regulating nuclear facilities and materials. The program is divided into nine main areas of research (mission objects) covering the safety of nuclear facilities, radioactive waste management, health physics, physical security, the development of regulatory processes, and special services. In addition, for the first time in this year's program, sub-programs (collections of related projects) have been organized in some areas of study; these sub-programs may cut across several mission objects. More sub-programs will be introduced in future years. A total of 96 projects are planned for 1993/94, including a number which are ongoing from the previous fiscal year. Projects that are held in reserve in case funding becomes available are also listed and provisionally ranked. The spending estimates for the RSP were calculated on the basis of an expected budget of $3.85 M

Regulatory research and support program for 1993/1994 - project descriptions

Energy Technology Data Exchange (ETDEWEB)

NONE

1993-03-01

The Regulatory Research and Support Program (RSP) is intended to augment and extend the Atomic Energy Control Board`s regulatory program beyond the capability of in-house resources. The overall objective of the research and support program is to produce pertinent and independent information that will assist the Board and its staff in making sound, timely and credible decisions on regulating nuclear facilities and materials. The program is divided into nine main areas of research (mission objects) covering the safety of nuclear facilities, radioactive waste management, health physics, physical security, the development of regulatory processes, and special services. In addition, for the first time in this year`s program, sub-programs (collections of related projects) have been organized in some areas of study; these sub-programs may cut across several mission objects. More sub-programs will be introduced in future years. A total of 96 projects are planned for 1993/94, including a number which are ongoing from the previous fiscal year. Projects that are held in reserve in case funding becomes available are also listed and provisionally ranked. The spending estimates for the RSP were calculated on the basis of an expected budget of $3.85 M.

PECULIARITIES OF ORGANIZATION OF POST-SPEAKED ASSOCIATION OF ALUMNI STUDY TRAINING PROGRAMS IN THE CONTEXT OF LIFE CYCLE SUPPORT OF THE TEACHER PROFESSION

Directory of Open Access Journals (Sweden)

E. Y. Ilaltdinova

2017-01-01

Full Text Available The article reveals the peculiarities of the organization of graduate support of graduates of the targeted training program in the context of supporting the life cycle of the teacher's profession. Important stages of the life cycle of the pedagogical profession are described. The model of the teacher's special training and contract employment is offered, the mechanisms of its implementation in the context of the trajectory of the entrance, promotion and exit after the completion of the targeted training program are defined. The mechanism of graduate support of graduates as one of the elements of the model of targeted training of teachers is presented, its priority goals and tasks are described, as well as the fundamental principles that determine the logic of the graduate's graduate support process. The tools of the mechanism of postgraduate accompaniment are developed, among which the defining role is played by the electronic interactive multifunctional online support service. The article describes the results obtained during the approbation of the developed mechanism for graduate support of graduates of the targeted training program and their impact on the solution of the problem of updating the teaching staff.

TASAC a computer program for thermal analysis of severe accident conditions. Version 3/01, Dec 1991. Model description and user`s guide

Energy Technology Data Exchange (ETDEWEB)

Stempniewicz, M; Marks, P; Salwa, K

1992-06-01

TASAC (Thermal Analysis of Severe Accident Conditions) is computer code developed in the Institute of Atomic Energy written in FORTRAN 77 for the digital computer analysis of PWR rod bundle behaviour during severe accident conditions. The code has the ability to model an early stage of core degradation including heat transfer inside the rods, convective and radiative heat exchange as well as cladding interactions with coolant and fuel, hydrogen generation, melting, relocations and refreezing of fuel rod materials with dissolution of UO{sub 2} and ZrO{sub 2} in liquid phase. The code was applied for the simulation of International Standard Problem number 28, performed on PHEBUS test facility. This report contains the program physical models description, detailed description of input data requirements and results of code verification. The main directions for future TASAC code development are formulated. (author). 20 refs, 39 figs, 4 tabs.

Cycling biomechanics: a literature review.

Science.gov (United States)

Wozniak Timmer, C A

1991-01-01

Submitted in partial fulfillment for a Master of Science degree at the University of Pittsburgh, School of Health Related Professions, Pittsburgh, PA 1.5213 This review of current literature on cycling biomechanics emphasizes lower extremity muscle actions and joint excursions, seat height, pedal position, pedaling rate, force application, and pedaling symmetry. Guidelines are discussed for optimal seat height, pedal position, and pedaling rate. Force application in the power and recovery phases of cycling and the relationship of force application to pedaling symmetry are discussed. The need for a biomechanical approach to cycling exists since a great deal of the literature is primarily physiologic in nature. The purpose of this review is to make cyclists and their advisors aware of the biomechanics of cycling and guidelines to follow. This approach is also important because cycling is a very common form of exercise prescribed by physical therapists for clinic or home programs. Biomechanical aspects of cycling should be considered by cyclists at any level of participation and by physical therapists in order for goal-oriented, efficient cycling to occur. J Orthop Sports Phys Ther 1991;14(3):106-113.

NWTS waste package program plan. Volume I. Program strategy, description, and schedule

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

Optimization of life cycle management costs

International Nuclear Information System (INIS)

Banerjee, A.K.

1994-01-01

As can be seen from the case studies, a LCM program needs to address and integrate, in the decision process, technical, political, licensing, remaining plant life, component replacement cycles, and financial issues. As part of the LCM evaluations, existing plant programs, ongoing replacement projects, short and long-term operation and maintenance issues, and life extension strategies must be considered. The development of the LCM evaluations and the cost benefit analysis identifies critical technical and life cycle cost parameters. These open-quotes discoveriesclose quotes result from the detailed and effective use of a consistent, quantifiable, and well documented methodology. The systematic development and implementation of a plant-wide LCM program provides for an integrated and structured process that leads to the most practical and effective recommendations. Through the implementation of these recommendations and cost effective decisions, the overall power production costs can be controlled and ultimately lowered

Building Program Models Incrementally from Informal Descriptions.

Science.gov (United States)

1979-10-01

specified at each step. Since the user controls the interaction, the user may determine the order in which information flows into PMB. Information is received...until only ten years ago the term aautomatic programming" referred to the development of the assemblers, macro expanders, and compilers for these

Logical Characterisation of Ontology Construction using Fuzzy Description Logics

DEFF Research Database (Denmark)

Badie, Farshad; Götzsche, Hans

had the extension of ontologies with Fuzzy Logic capabilities which plan to make proper backgrounds for ontology driven reasoning and argumentation on vague and imprecise domains. This presentation conceptualises learning from fuzzy classes using the Inductive Logic Programming framework. Then......, employs Description Logics in characterising and analysing fuzzy statements. And finally, provides a conceptual framework describing fuzzy concept learning in ontologies using the Inductive Logic Programming....

LH2 three-phase pump control circuit description

International Nuclear Information System (INIS)

Pierce, W.

1977-05-01

A brief description and circuit drawings are given for a pump control system. The pump is used to circulate liquid hydrogen through the cell and heat exchanger of an LH 2 target. The pump is powered by three-phase 60 cycle power, and the control unit is powered from a positive and negative 24 V dc supply available in the NIM Bin. The control unit is packaged in a double-width NIM module. Drawings are given for the pump speed indicator, function generator, and power supply

47 CFR 79.3 - Video description of video programming.

Science.gov (United States)

2010-10-01

... television audience measurement service, based on television viewership in the counties that make up each DMA... other distributor of video programming for residential reception that delivers such programming directly... the national audience share during prime time of nonbroadcast networks, as determined by Nielsen Media...

Nonproliferation characteristics of advanced fuel cycle concepts

International Nuclear Information System (INIS)

Persiani, P.J.

1998-01-01

The purpose of this study is to comment on the proliferation characteristic profiles of some of the proposed fuel cycle alternatives to help ensure that nonproliferation concerns are introduced into the early stages of a fuel cycle concept development program, and to perhaps aid in the more effective implementation of the international nonproliferation regime initiatives and safeguards methods and systems. Alternative cycle concepts proposed by several countries involve the recycle of spent fuel without the separation of plutonium from uranium and fission products

Consumer involvement in the health technology assessment program.

Science.gov (United States)

Royle, Jane; Oliver, Sandy

2004-01-01

This study aims to describe a cycle of development leading to sustainable methods for involving consumers in the management of a program commissioning health technology assessment. Staff time was dedicated to developing procedures for recruiting and briefing consumers to participate in prioritizing, commissioning, and reporting research. Resources and support were developed in light of early feedback from consumers and those working with them. These were piloted and amended before being used routinely. Over 4 years, procedures and resources have been developed to support six consumers attending seven to eight prioritization meetings a year; thirty to forty-five consumers each year commenting on research need for particular topics; thirty consumers a year commenting on research proposals, and twenty a year commenting on research reports. The procedures include clear job descriptions, induction and development days, clear briefing materials, payment for substantial tasks, and regularly seeking feedback to improve procedures. Explicit, inclusive, and reproducible methods for supporting consumer involvement that satisfy National Health Service policy recommendations for involving consumers in research require dedicated staff time to support a cycle of organizational development.

Impact on environmental qualification from a longer fuel cycle

International Nuclear Information System (INIS)

Sanwarwalla, M.H.; Akhtar, S.; Drankhan, D.A.

1996-01-01

There is a general trend in the nuclear industry towards longer fuel cycles because of the economic benefits. The economic benefits for increasing the fuel cycle from eighteen to twenty four months is estimated by the industry to be about $5.05 million per unit year based on a two week mid-cycle maintenance outage. Equipment with a unique characteristic may require maintenance and/or inspection more frequently than can be accommodated in a longer cycle. The maintenance and surveillance (M ampersand S) requirements for these equipment need to be reviewed to accommodate a longer cycle and avoid any unplanned outage. ComEd's LaSalle Station is considering a move to a longer fuel cycle. A study was done to determine the impact of a longer fuel cycle on their current environmental qualification (EQ) program, and the feasibility of implementing changes to their program to accommodate a longer fuel cycle. This paper discusses (1) the impact, if any, the longer fuel cycle will have on the maintenance and surveillance requirements of the 50.49 or environmentally qualified equipment at LaSalle Station, (2) the various techniques, i.e., partial testing, performance based monitoring etc., employed to extend the existing maintenance and surveillance requirements, and (3) the estimated economic savings, if any, from the extended M ampersand S interval

Math Description Engine Software Development Kit

Science.gov (United States)

Shelton, Robert O.; Smith, Stephanie L.; Dexter, Dan E.; Hodgson, Terry R.

2010-01-01

The Math Description Engine Software Development Kit (MDE SDK) can be used by software developers to make computer-rendered graphs more accessible to blind and visually-impaired users. The MDE SDK generates alternative graph descriptions in two forms: textual descriptions and non-verbal sound renderings, or sonification. It also enables display of an animated trace of a graph sonification on a visual graph component, with color and line-thickness options for users having low vision or color-related impairments. A set of accessible graphical user interface widgets is provided for operation by end users and for control of accessible graph displays. Version 1.0 of the MDE SDK generates text descriptions for 2D graphs commonly seen in math and science curriculum (and practice). The mathematically rich text descriptions can also serve as a virtual math and science assistant for blind and sighted users, making graphs more accessible for everyone. The MDE SDK has a simple application programming interface (API) that makes it easy for programmers and Web-site developers to make graphs accessible with just a few lines of code. The source code is written in Java for cross-platform compatibility and to take advantage of Java s built-in support for building accessible software application interfaces. Compiled-library and NASA Open Source versions are available with API documentation and Programmer s Guide at http:/ / prim e.jsc.n asa. gov.

BIPR-5 program

International Nuclear Information System (INIS)

Petrunin, D.M.; Belyaeva, E.D.; Kireeva, I.L.

1975-01-01

The BIPR-5 program, which solves the relevant one-group equation in a three-dimensional inhomogeneous WWER reactor, makes it possible to simulate all the principal states of the core, including the maintenance of the critical state by means of rods or a liquid absorber on fuel burn-up or in transitional processes on xenon and samarium. The present paper includes a brief description of the program structure and a detailed description of input data and actually represents maintenance instructions

Rocket-Based Combined Cycle Activities in the Advanced Space Transportation Program Office

Science.gov (United States)

Hueter, Uwe; Turner, James

1999-01-01

NASA's Office of Aero-Space Technology (OAST) has established three major goals, referred to as, "The Three Pillars for Success". The Advanced Space Transportation Program Office (ASTP) at the NASA's Marshall Space Flight Center (MSFC) in Huntsville, Ala. focuses on future space transportation technologies Under the "Access to Space" pillar. The Core Technologies Project, part of ASTP, focuses on the reusable technologies beyond those being pursued by X-33. One of the main activities over the past two and a half years has been on advancing the rocket-based combined cycle (RBCC) technologies. In June of last year, activities for reusable launch vehicle (RLV) airframe and propulsion technologies were initiated. These activities focus primarily on those technologies that support the decision to determine the path this country will take for Space Shuttle and RLV. This year, additional technology efforts in the reusable technologies will be awarded. The RBCC effort that was completed early this year was the initial step leading to flight demonstrations of the technology for space launch vehicle propulsion.

A Life-Cycle Overlapping-Generations Model of the Small Open Economy

NARCIS (Netherlands)

Heijdra, Ben J.; Romp, Ward E.

2005-01-01

In this paper we construct an overlapping generations model for the small open economy incorporating a realistic description of the mortality process. With agedependent mortality, the typical life-cycle pattern of consumption and saving results from the maximizing behaviour of individual households.

Description of the DLL regulation interface in HAWC

DEFF Research Database (Denmark)

Larsen, Torben J.

2001-01-01

This report contains a description of the external regulation interface between the aeroelastic code HAWC and a separate regulation unit programmed as a DLL (Dynamic Link Library). Specific HAWC commands used with the regulation as well as simple DLLexamples written in Delphi, Fortran and C...

Chemical Oceanography and the Marine Carbon Cycle

Science.gov (United States)

Emerson, Steven; Hedges, John

The principles of chemical oceanography provide insight into the processes regulating the marine carbon cycle. The text offers a background in chemical oceanography and a description of how chemical elements in seawater and ocean sediments are used as tracers of physical, biological, chemical and geological processes in the ocean. The first seven chapters present basic topics of thermodynamics, isotope systematics and carbonate chemistry, and explain the influence of life on ocean chemistry and how it has evolved in the recent (glacial-interglacial) past. This is followed by topics essential to understanding the carbon cycle, including organic geochemistry, air-sea gas exchange, diffusion and reaction kinetics, the marine and atmosphere carbon cycle and diagenesis in marine sediments. Figures are available to download from www.cambridge.org/9780521833134. Ideal as a textbook for upper-level undergraduates and graduates in oceanography, environmental chemistry, geochemistry and earth science and a valuable reference for researchers in oceanography.

Advanced fuel cycles options for LWRs and IMF benchmark definition

International Nuclear Information System (INIS)

Breza, J.; Darilek, P.; Necas, V.

2008-01-01

In the paper, different advanced nuclear fuel cycles including thorium-based fuel and inert-matrix fuel are examined under light water reactor conditions, especially VVER-440, and compared. Two investigated thorium based fuels include one solely plutonium-thorium based fuel and the second one plutonium-thorium based fuel with initial uranium content. Both of them are used to carry and burn or transmute plutonium created in the classical UOX cycle. The inert-matrix fuel consist of plutonium and minor actinides separated from spent UOX fuel fixed in Yttria-stabilised zirconia matrix. The article shows analysed fuel cycles and their short description. The conclusion is concentrated on the rate of Pu transmutation and Pu with minor actinides cumulating in the spent advanced thorium fuel and its comparison to UOX open fuel cycle. Definition of IMF benchmark based on presented scenario is given. (authors)

Description Fuel Cycle Spanish. Technical Visits; Descripcion del Ciclo de Combustible Espanol. VisitasTecnicas

Energy Technology Data Exchange (ETDEWEB)

Ochoa Valero, R.; Vinuesa Carretero, A.

2014-07-01

The nuclear fuel cycle includes all processes and operations from the mining of uranium to the management of radioactive waste generated. These processes include the manufacture of nuclear fuel, the operation of the plants and the storage of radioactive waste in the corresponding temporary stores. (Author)

International Nuclear Fuel Cycle Fact Book

Energy Technology Data Exchange (ETDEWEB)

Leigh, I.W.; Patridge, M.D.

1991-05-01

As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need has developed for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book was compiled to meet that need. The information contained in the International Nuclear Fuel Cycle Fact Book has been obtained from many unclassified sources: nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECN/NEA activities reports; not reflect any one single source but frequently represent a consolidation/combination of information.

Supermarket Defrost Cycles As Flexible Reserve

DEFF Research Database (Denmark)

Pedersen, Rasmus; Sloth, Christoffer; Wisniewski, Rafal

2015-01-01

This work analyses how supermarket defrost cycles can be used as flexible reserve in a smart grid context. The consumption flexibility originates from being able to shift defrost cycles in time, while adhering to the underlying refrigeration systems constraints. It is shown how this time...... constrained behavior can be modeled and used by a defrost planner to optimally schedule defrost start times for several defrost cycles, according to electricity price. Because the defrost planning problem is a boolean programming problem a method of relaxing it is proposed. While the relaxed problem requires...... less computational effort, convexity is dependent on properties of the price signal. Simulation study show that the optimal planning strategy can reduce cost of defrost cycles with 31.7%, compared to a current strategy of executing all defrost cycles at the same time each day. Copyright ©2015 by IEEE...

40 CFR 70.4 - State program submittals and transition.

Science.gov (United States)

2010-07-01

... description in narrative form of the scope, structure, coverage, and processes of the State program. (ii) A description of the organization and structure of the agency or agencies that will have responsibility for... strategies). (5) A complete description of the State's compliance tracking and enforcement program or...

The Life Cycle Analysis Toolbox

International Nuclear Information System (INIS)

Bishop, L.; Tonn, B.E.; Williams, K.A.; Yerace, P.; Yuracko, K.L.

1999-01-01

The life cycle analysis toolbox is a valuable integration of decision-making tools and supporting materials developed by Oak Ridge National Laboratory (ORNL) to help Department of Energy managers improve environmental quality, reduce costs, and minimize risk. The toolbox provides decision-makers access to a wide variety of proven tools for pollution prevention (P2) and waste minimization (WMin), as well as ORNL expertise to select from this toolbox exactly the right tool to solve any given P2/WMin problem. The central element of the toolbox is a multiple criteria approach to life cycle analysis developed specifically to aid P2/WMin decision-making. ORNL has developed numerous tools that support this life cycle analysis approach. Tools are available to help model P2/WMin processes, estimate human health risks, estimate costs, and represent and manipulate uncertainties. Tools are available to help document P2/WMin decision-making and implement programs. Tools are also available to help track potential future environmental regulations that could impact P2/WMin programs and current regulations that must be followed. An Internet-site will provide broad access to the tools

A comparison of improved power plant technologies on lignite with (PFBC) and (IGCC) cycles

International Nuclear Information System (INIS)

Cherepnalkovski, Ilija

1997-01-01

Technologies and process diagrams descriptions for PFBC (Pressurised Fluidized Bed Combustion) and IGCC (Integrated Gasification Combined Cycle) are presented as for improved cycles with modern clean coal technologies, the most popular currently. A special attention is paid to the possibilities for Macedonian lignites use on the power plants with PFBC and IGCC cycles. The comparison of the above mention technologies has been done particularly on the desulfurization, NO x reduction, ash elimination and its use in the building and construction industries. A comparison between the power plants with PFBC and IGCC cycles is made by the following criteria: cycle efficiency, desulfurization and nitrogen oxides reduction, power plant complexity and their cost, as well as plant reliability. (Author)

A simulation program for electronics experiments

International Nuclear Information System (INIS)

Brun, R.; Hagelberg, R.; Hansroul, M.; Lassalle, Jc.

1978-01-01

A general description of the GEANT program is given. The GEANT program has been designed to cover a wide variety of particle detectors. The program is separated into 4 independent parts: kinematics generation, trackina in space, tracks intersection with detectors and digitization of detector information. The tracking requires the introduction of the experimental set-up description in terms of media. The detectors are described independently of the media in a separate way. The media and detector description have to be furnished by the user. The implementation of the GEANT program is based on 2 sets of subprograms: a fixed set of subprograms, which are independent of the experimental situation and thus transparent to the user; a set of user subprograms which should be written by the user. The GEANT program produces results stored in data banks, which the user can convert into his own format. In addition the GEANT program provides printed and graphical outputs

Nuclear weapons data for use in carbon cycle modelling

International Nuclear Information System (INIS)

Enting, I.G.

1982-01-01

This report contains tables of atmospheric explosions for use in carbon cycle modelling studies. Descriptions of the sources of the data and the manner in which it can be used are given. The essential requirement is for a specification of the amount of 14 C injected into the atmosphere as a function of time, height, latitude and longitude

Integrated Data Collection Analysis (IDCA) Program: FY2011 Project Descriptions

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); Warner, Kirstin F. [Naval Surface Warfare Center (NSWC-IHD), Indian Head, MD (United States). Indian Head Division; Remmers, Daniel L. [Naval Surface Warfare Center (NSWC-IHD), Indian Head, MD (United States). Indian Head Division; Whinnery, LeRoy L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Shelley, Timothy J. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Reyes, Jose A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hsu, Peter C. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Reynolds, John G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2012-02-03

This document provides brief descriptions of research topics for consideration by the IDCA for potential funding in funding in FY 2011. The topics include the utilization of the results from the Proficiency Test developed during FY 2010 to start populating the small-scale safety and thermal testing (SSST) Testing Compendium and revising results from methods modifications. Other research topics were also developed for FY 2011 from issues that arose in the Proficiency Test.

The solar activity cycle physical causes and consequences

CERN Document Server

Hudson, Hugh; Petrovay, Kristóf; Steiger, Rudolf

2015-01-01

A collection of papers edited by four experts in the field, this book sets out to describe the way solar activity is manifested in observations of the solar interior, the photosphere, the chromosphere, the corona and the heliosphere. The 11-year solar activity cycle, more generally known as the sunspot cycle, is a fundamental property of the Sun.  This phenomenon is the generation and evolution of magnetic fields in the Sun’s convection zone, the photosphere.  It is only by the careful enumeration and description of the phenomena and their variations that one can clarify their interdependences.   The sunspot cycle has been tracked back about four centuries, and it has been recognized that to make this data set a really useful tool in understanding how the activity cycle works and how it can be predicted, a very careful and detailed effort is needed to generate sunspot numbers.  This book deals with this topic, together with several others that present related phenomena that all indicate the physical pr...

Cycle accurate and cycle reproducible memory for an FPGA based hardware accelerator

Science.gov (United States)

Asaad, Sameh W.; Kapur, Mohit

2016-03-15

A method, system and computer program product are disclosed for using a Field Programmable Gate Array (FPGA) to simulate operations of a device under test (DUT). The DUT includes a device memory having a number of input ports, and the FPGA is associated with a target memory having a second number of input ports, the second number being less than the first number. In one embodiment, a given set of inputs is applied to the device memory at a frequency Fd and in a defined cycle of time, and the given set of inputs is applied to the target memory at a frequency Ft. Ft is greater than Fd and cycle accuracy is maintained between the device memory and the target memory. In an embodiment, a cycle accurate model of the DUT memory is created by separating the DUT memory interface protocol from the target memory storage array.

World Perspective Case Descriptions on Educational Programs for Adults: India.

Science.gov (United States)

Jayagopal, R.; Burns, E. P.

Four adult education programs being conducted in India are described in the case studies in this packet. Two of the projects involve literacy; the third promotes literacy as one part of its community development program, and the fourth trains workers in hotel management and catering technology. The literacy programs are (1) development of a…

Federal Geothermal Research Program Update Fiscal Year 2000

Energy Technology Data Exchange (ETDEWEB)

Renner, J.L.

2001-08-15

The Department of Energy's Geothermal Program serves two broad purposes: (1) to assist industry in overcoming near-term barriers by conducting cost-shared research and field verification that allows geothermal energy to compete in today's aggressive energy markets; and (2) to undertake fundamental research with potentially large economic payoffs. The four categories of work used to distinguish the research activities of the Geothermal Program during FY 2000 reflect the main components of real-world geothermal projects. These categories form the main sections of the project descriptions in this Research Update. Exploration Technology research focuses on developing instruments and techniques to discover hidden hydrothermal systems and to explore the deep portions of known systems. Research in geophysical and geochemical methods is expected to yield increased knowledge of hidden geothermal systems. Reservoir Technology research combines laboratory and analytical investigations with equipment development and field testing to establish practical tools for resource development and management for both hydrothermal reservoirs and enhanced geothermal systems. Research in various reservoir analysis techniques is generating a wide range of information that facilitates development of improved reservoir management tools. Drilling Technology focuses on developing improved, economic drilling and completion technology for geothermal wells. Ongoing research to avert lost circulation episodes in geothermal drilling is yielding positive results. Conversion Technology research focuses on reducing costs and improving binary conversion cycle efficiency, to permit greater use of the more abundant moderate-temperature geothermal resource, and on the development of materials that will improve the operating characteristics of many types of geothermal energy equipment. Increased output and improved performance of binary cycles will result from investigations in heat cycle research.

CONTRIBUTIONS FOR DEVELOPING OF A COMPUTER AIDED LEARNING ENVIRONMENT OF DESCRIPTIVE GEOMETRY

Directory of Open Access Journals (Sweden)

Antonescu Ion

2009-07-01

Full Text Available The paper presents the authors’ contributions for developing a computer code for teaching of descriptive geometry using the computer aided learning techniques. The program was implemented using the programming interface and the 3D modeling capabilities of the AutoCAD system.

Strategic environmental safety inspection for the National disposal program. Description of the inspection volume. Documentation for the scoping team; Strategische Umweltpruefung zum Nationalen Entsorgungsprogramm. Beschreibung des Untersuchungsumfangs. Unterlage fuer den Scoping-Termin

Energy Technology Data Exchange (ETDEWEB)

NONE

2015-01-06

The Strategic environmental safety inspection for the National disposal program covers the following topics: Legal framework: determination of the requirement for an environmental inspection program, coordination of the scoping team into the overall context; environmental targets; approach for assessment and evaluation of environmental impact, description of the inspection targets for the strategic environmental inspection; consideration of alternatives.

Optimal cure cycle design of a resin-fiber composite laminate

Science.gov (United States)

Hou, Jean W.; Sheen, Jeenson

1987-01-01

A unified computed aided design method was studied for the cure cycle design that incorporates an optimal design technique with the analytical model of a composite cure process. The preliminary results of using this proposed method for optimal cure cycle design are reported and discussed. The cure process of interest is the compression molding of a polyester which is described by a diffusion reaction system. The finite element method is employed to convert the initial boundary value problem into a set of first order differential equations which are solved simultaneously by the DE program. The equations for thermal design sensitivities are derived by using the direct differentiation method and are solved by the DE program. A recursive quadratic programming algorithm with an active set strategy called a linearization method is used to optimally design the cure cycle, subjected to the given design performance requirements. The difficulty of casting the cure cycle design process into a proper mathematical form is recognized. Various optimal design problems are formulated to address theses aspects. The optimal solutions of these formulations are compared and discussed.

Implementing risk-informed life-cycle design

International Nuclear Information System (INIS)

Hill, Ralph S. III

2007-01-01

This paper describes a design process based on risk-informed probabilistic methodologies that cover a facility's life-cycle from start of conceptual design through decontamination and decommissioning. The concept uses probabilistic risk assessments to identify target reliabilities for facility systems and components. Target reliabilities are used in system and subsystem simulation analyses to determine the optimum combination of initial system and component construction reliability, maintenance frequency, and inspection frequency for both active and passive components. The target reliabilities are also used for system based code margin exchange to reduce excessive level of margins to appropriate levels resulting in a more flexible structure of codes and standards that improves facility reliability and cost. The paper includes a description of a risk informed life-cycle design process, a summary of work being done, and a discussion of work needed to implement the process. (author)

EVALUATION OF ENERGY PERFORMANCE USING DOE-2 ENERGY SIMULATION PROGRAM IN SINGAPORE

Directory of Open Access Journals (Sweden)

Po Seng Kian

2000-01-01

Full Text Available Recently, due to worldwide energy cost rising significantly, there has been an essential need to minimize the energy consumption. This global warning address many countries including Singapore realizing the important of energy efficiency in industries and buildings. This paper deals with analyzing the energy consumption of an 11-storey commercial building in Singapore using DOE-2 Energy Simulation Program. A study is made on the benefits derived from modifying the building envelope, space system setting, air-conditioning plant, and lighting. This encompasses a description of its quantitative impact on cooling load, energy consumption and energy saving achieved as compared with the original building. Following this, a life cycle costing is done to determine the economic benefits attained from this modification. This study shows that some alternative solutions can be achieved using energy simulation program to conserve the energy consumption.

Analysis of the total system life cycle cost for the Civilian Radioactive Waste Management Program

International Nuclear Information System (INIS)

1989-05-01

The total-system life-cycle cost (TSLCC) analysis for the Department of Energy's (DOE) Civilian Radioactive Waste Management Program is an ongoing activity that helps determine whether the revenue-producing mechanism established by the Nuclear Waste Policy Act of 1982 -- a fee levied on electricity generated in commercial nuclear power plants -- is sufficient to cover the cost of the program. This report provides cost estimates for the sixth annual evaluation of the adequacy of the fee and is consistent with the program strategy and plans contained in the DOE's Draft 1988 Mission Plan Amendment. The total-system cost for the system with a repository at Yucca Mountain, Nevada, a facility for monitored retrievable storage (MRS), and a transportation system is estimated at $24 billion (expressed in constant 1988 dollars). In the event that a second repository is required and is authorized by the Congress, the total-system cost is estimated at $31 to $33 billion, depending on the quantity of spent fuel to be disposed of. The $7 billion cost savings for the single-repository system in comparison with the two-repository system is due to the elimination of $3 billion for second-repository development and $7 billion for the second-repository facility. These savings are offset by $2 billion in additional costs at the first repository and $1 billion in combined higher costs for the MRS facility and transportation. 55 refs., 2 figs., 24 tabs

Joy, Exercise, Enjoyment, Getting out: A Qualitative Study of Older People's Experience of Cycling in Sydney, Australia

OpenAIRE

Alexis Zander; Erin Passmore; Chloe Mason; Chris Rissel

2013-01-01

Introduction. Cycling can be an enjoyable way to meet physical activity recommendations and is suitable for older people; however cycling participation by older Australians is low. This qualitative study explored motivators, enablers, and barriers to cycling among older people through an age-targeted cycling promotion program. Methods. Seventeen adults who aged 50–75 years participated in a 12-week cycling promotion program which included a cycling skills course, mentor, and resource pack...

Analysis of the total system life cycle cost for the Civilian Radioactive Waste Management Program: executive summary

International Nuclear Information System (INIS)

1985-04-01

The total-system life-cycle cost (TSLCC) analysis for the Department of Energy's Civilian Radioactive Waste Management Progrram is an ongoing activity that helps determine whether the revenue-producing mechanism established by the Nuclear Waste Policy Act of 1982 is sufficient to cover the cost of the program. This report is an input into the third evaluation of the adequacy of the fee. The total-system cost for the reference waste-management program in this analysis is estimated to be 24 to 30 billion (1984) dollars. For the sensitivity cases studied in this report, the costs could be as high as 35 billion dollars and as low as 21 billion dollars. Because factors like repository location, the quantity of waste generated, transportation-cask technology, and repository startup dates exert substantial impacts on total-system costs, there are several tradeoffs between these factors, and these tradeoffs can greatly influence the total cost of the program. The total-system cost for the reference program described in this report is higher by 3 to 5 billion dollars, or 15 to 20%, than the cost for the reference program of the TSLCC analysis of April 1984. More than two-thirds of this increase is in the cost of repository construction and operation. These repository costs have increased because of changing design concepts, different assumptions about the effort required to perform the necessary activities, and a change in the source data on which the earlier analysis was based. Development and evaluation costs have similarly increased because of a net addition to the work content. Transportation costs have increased because of different assumptions about repository locations and several characteristics of the transportation system. It is expected that the estimates of total-system costs will continue to change in response to both an evolving program strategy and better definition of the work required to achieve the program objectives

Romanian nuclear fuel cycle development

International Nuclear Information System (INIS)

Rapeanu, S.N.; Comsa, Olivia

1998-01-01

Romanian decision to introduce nuclear power was based on the evaluation of electricity demand and supply as well as a domestic resources assessment. The option was the introduction of CANDU-PHWR through a license agreement with AECL Canada. The major factors in this choice have been the need of diversifying the energy resources, the improvement the national industry and the independence of foreign suppliers. Romanian Nuclear Power Program envisaged a large national participation in Cernavoda NPP completion, in the development of nuclear fuel cycle facilities and horizontal industry, in R and D and human resources. As consequence, important support was being given to development of industries involved in Nuclear Fuel Cycle and manufacturing of equipment and nuclear materials based on technology transfer, implementation of advanced design execution standards, QA procedures and current nuclear safety requirements at international level. Unit 1 of the first Romanian nuclear power plant, Cernavoda NPP with a final profile 5x700 Mw e, is now in operation and its production represents 10% of all national electricity production. There were also developed all stages of FRONT END of Nuclear Fuel Cycle as well as programs for spent fuel and waste management. Industrial facilities for uranian production, U 3 O 8 concentrate, UO 2 powder and CANDU fuel bundles, as well as heavy water plant, supply the required fuel and heavy water for Cernavoda NPP. The paper presents the Romanian activities in Nuclear Fuel Cycle and waste management fields. (authors)

Answering Key Fuel Cycle Questions

International Nuclear Information System (INIS)

Piet, S.J.; Dixon, B.W.; Bennett, R.G.; Smith, J.D.; Hill, R.N.

2004-01-01

Given the range of fuel cycle goals and criteria, and the wide range of fuel cycle options, how can the set of options eventually be narrowed in a transparent and justifiable fashion? It is impractical to develop all options. We suggest an approach that starts by considering a range of goals for the Advanced Fuel Cycle Initiative (AFCI) and then posits seven questions, such as whether Cs and Sr isotopes should be separated from spent fuel and, if so, what should be done with them. For each question, we consider which of the goals may be relevant to eventually providing answers. The AFCI program has both ''outcome'' and ''process'' goals because it must address both waste already accumulating as well as completing the fuel cycle in connection with advanced nuclear power plant concepts. The outcome objectives are waste geologic repository capacity and cost, energy security and sustainability, proliferation resistance, fuel cycle economics, and safety. The process objectives are rea diness to proceed and adaptability and robustness in the face of uncertainties

Interim reliability-evaluation program: analysis of the Browns Ferry, Unit 1, nuclear plant. Appendix B - system descriptions and fault trees

International Nuclear Information System (INIS)

Mays, S.E.; Poloski, J.P.; Sullivan, W.H.; Trainer, J.E.; Bertucio, R.C.; Leahy, T.J.

1982-07-01

This report describes a risk study of the Browns Ferry, Unit 1, nuclear plant. The study is one of four such studies sponsored by the NRC Office of Research, Division of Risk Assessment, as part of its Interim Reliability Evaluation Program (IREP), Phase II. This report is contained in four volumes: a main report and three appendixes. Appendix B provides a description of Browns Ferry, Unit 1, plant systems and the failure evaluation of those systems as they apply to accidents at Browns Ferry. Information is presented concerning front-line system fault analysis; support system fault analysis; human error models and probabilities; and generic control circuit analyses

The detection and stabilisation of limit cycle for deterministic finite automata

Science.gov (United States)

Han, Xiaoguang; Chen, Zengqiang; Liu, Zhongxin; Zhang, Qing

2018-04-01

In this paper, the topological structure properties of deterministic finite automata (DFA), under the framework of the semi-tensor product of matrices, are investigated. First, the dynamics of DFA are converted into a new algebraic form as a discrete-time linear system by means of Boolean algebra. Using this algebraic description, the approach of calculating the limit cycles of different lengths is given. Second, we present two fundamental concepts, namely, domain of attraction of limit cycle and prereachability set. Based on the prereachability set, an explicit solution of calculating domain of attraction of a limit cycle is completely characterised. Third, we define the globally attractive limit cycle, and then the necessary and sufficient condition for verifying whether all state trajectories of a DFA enter a given limit cycle in a finite number of transitions is given. Fourth, the problem of whether a DFA can be stabilised to a limit cycle by the state feedback controller is discussed. Criteria for limit cycle-stabilisation are established. All state feedback controllers which implement the minimal length trajectories from each state to the limit cycle are obtained by using the proposed algorithm. Finally, an illustrative example is presented to show the theoretical results.

Simulation of a combined-cycle engine

Science.gov (United States)

Vangerpen, Jon

1991-01-01

A FORTRAN computer program was developed to simulate the performance of combined-cycle engines. These engines combine features of both gas turbines and reciprocating engines. The computer program can simulate both design point and off-design operation. Widely varying engine configurations can be evaluated for their power, performance, and efficiency as well as the influence of altitude and air speed. Although the program was developed to simulate aircraft engines, it can be used with equal success for stationary and automative applications.

Modelling of environmental impacts of solid waste landfilling within the life-cycle analysis program EASEWASTE.

Science.gov (United States)

Kirkeby, Janus T; Birgisdottir, Harpa; Bhander, Gurbakash Singh; Hauschild, Michael; Christensen, Thomas H

2007-01-01

A new computer-based life-cycle assessment model (EASEWASTE) has been developed to evaluate resource and environmental consequences of solid waste management systems. This paper describes the landfilling sub-model used in the life-cycle assessment program EASEWASTE, and examines some of the implications of this sub-model. All quantities and concentrations of leachate and landfill gas can be modified by the user in order to bring them in agreement with the actual landfill that is assessed by the model. All emissions, except the generation of landfill gas, are process specific. The landfill gas generation is calculated on the basis of organic matter in the landfilled waste. A landfill assessment example is provided. For this example, the normalised environmental effects of landfill gas on global warming and photochemical smog are much greater than the environmental effects for landfill leachate or for landfill construction. A sensitivity analysis for this example indicates that the overall environmental impact is sensitive to the gas collection efficiency and the use of the gas, but not to the amount of leachate generated, or the amount of soil or liner material used in construction. The landfill model can be used for evaluating different technologies with different liners, gas and leachate collection efficiencies, and to compare the environmental consequences of landfilling with alternative waste treatment options such as incineration or anaerobic digestion.

Modelling of environmental impacts of solid waste landfilling within the life-cycle analysis program EASEWASTE

International Nuclear Information System (INIS)

Kirkeby, Janus T.; Birgisdottir, Harpa; Bhander, Gurbakash Singh; Hauschild, Michael; Christensen, Thomas H.

2007-01-01

A new computer-based life-cycle assessment model (EASEWASTE) has been developed to evaluate resource and environmental consequences of solid waste management systems. This paper describes the landfilling sub-model used in the life-cycle assessment program EASEWASTE, and examines some of the implications of this sub-model. All quantities and concentrations of leachate and landfill gas can be modified by the user in order to bring them in agreement with the actual landfill that is assessed by the model. All emissions, except the generation of landfill gas, are process specific. The landfill gas generation is calculated on the basis of organic matter in the landfilled waste. A landfill assessment example is provided. For this example, the normalised environmental effects of landfill gas on global warming and photochemical smog are much greater than the environmental effects for landfill leachate or for landfill construction. A sensitivity analysis for this example indicates that the overall environmental impact is sensitive to the gas collection efficiency and the use of the gas, but not to the amount of leachate generated, or the amount of soil or liner material used in construction. The landfill model can be used for evaluating different technologies with different liners, gas and leachate collection efficiencies, and to compare the environmental consequences of landfilling with alternative waste treatment options such as incineration or anaerobic digestion

The industrial nuclear fuel cycle in Argentina

International Nuclear Information System (INIS)

Koll, J.H.; Kittl, J.E.; Parera, C.A.; Coppa, R.C.; Aguirre, E.J.

1977-01-01

The nuclear power program of Argentina for the period 1976-85 is described, as a basis to indicate fuel requirements and the consequent implementation of a national fuel cycle industry. Fuel cycle activities in Argentina were initiated as soon as 1951-2 in the prospection and mining activities through the country. Following this step, yellow-cake production was initiated in plants of limited capacity. National production of uranium concentrate has met requirements up to the present time, and will continue to do so until the Sierra Pintada Industrial Complex starts operation in 1979. Presently, there is a gap in local production of uranium dioxide and fuel elements for the Atucha power station, which are produced abroad using Argentine uranium concentrate. With its background, the argentine program for the installation of nuclear fuel cycle industries is described, and the techno-economical implications considered. Individual projects are reviewed, as well as the present and planned infrastructure needed to support the industrial effort [es

Overdeterminacy and endogenous cycles: Trygve Haavelmo’s business cycle model and its implications for monetary policy

OpenAIRE

Kallåk Anundsen , André; Sigurd Holmsen Krogh, Tord; Nymoen, Ragnar; Vislie, Jon

2011-01-01

This paper presents the business cycle model that Trygve Haavelmo developed as part of his research program in macroeconomic and monetary theory. Driven by a mismatch between the marginal return to capital and the rate of return required by capital owners, this model generates endogenous cycles. The theory leads to a distinct analysis of the scope and limitations of monetary policy. A main message of the model is that care should be taken when conducting 'autonomous' monetary policy and that ...

Power cycle heat balance software for personal computer (PC)2TM

International Nuclear Information System (INIS)

Bockh, P. von; Rodriguez, H.

1996-01-01

This paper describes the PC-based power cycle balance of plant software (PC)trademark (Power Cycle on Personal Computer). It is designed to assist nuclear, fossil, and industrial power plants so that steam cycles can be simulated, analyzed and optimized. First, the cycle model is developed on the screen. The elements of the power cycle are taken from a tool box containing all components of a modern power cycle. The elements are connected by using a mouse. The next step is the input of the design values of the components or data taken from performance tests. This entire input sequence is guided by the program. Based on the input data, the physical behavior of each component is simulated according to established physical rules. Part load operation or other off-design conditions can be calculated. The program is designed for use by power plant engineers and power engineering firms to optimize new power cycles, perform problem-solving analyses, optimize component retrofit, and train power plant engineers and operators. It also can be used by universities to educate engineering students

French views on the nuclear fuel cycle

International Nuclear Information System (INIS)

Chavardes, D.

1986-01-01

Fuel cycle activities are viewed in France as a very important and indissociable part of our nuclear program. Supply of material and services are firmly assured for domestic needs and overcapacities provide opportunities for industry to compete on the international market. A permanent and consistent R and D effort is continuously undertaken, aiming to apply new advanced technologies improving safety, economy and reliability of fuel cycle installations

Cell mass and cell cycle dynamics of an asynchronous budding yeast population

DEFF Research Database (Denmark)

Lencastre Fernandes, Rita; Carlquist, Magnus; Lundin, Luisa

2013-01-01

of model predictions for cell property distributions against experimental data is scarce. This study focuses on the experimental and mathematical description of the dynamics of cell size and cell cycle position distributions, of a population of Saccharomyces cerevisiae, in response to the substrate...

Evaluation of a workplace intervention to promote commuter cycling: a RE-AIM analysis.

Science.gov (United States)

Dubuy, Veerle; De Cocker, Katrien; De Bourdeaudhuij, Ilse; Maes, Lea; Seghers, Jan; Lefevre, Johan; De Martelaer, Kristine; Cardon, Greet

2013-06-17

Originating from the interdisciplinary collaboration between public health and the transportation field a workplace intervention to promote commuter cycling, 'Bike to Work: cyclists are rewarded', was implemented. The intervention consisted of two cycling contests, an online loyalty program based on earning 'cycling points' and the dissemination of information through folders, newsletters, posters and a website. The study purpose was to evaluate the dissemination efforts of the program and to gain insights in whether free participation could persuade small and middle-sized companies to sign up. The RE-AIM framework was used to guide the evaluation. Two months after the start of the intervention a questionnaire was send to 4880 employees. At the end of the intervention each company contact person (n = 12) was interviewed to obtain information on adoption, implementation and maintenance.Comparison analyses between employees aware and unaware of the program were conducted using independent-samples t-tests for quantitative data and chi-square tests for qualitative data. Difference in commuter cycling frequency was assessed using an ANOVA test. Non-parametric tests were used for the comparison analyses between the adopting and non-adopting companies. In total seven of the twelve participating companies adopted the program and all adopting companies implemented all intervention components. No significant differences were found in the mean number of employees (p = 0.15) or in the type of business sector (p = 0.92) between adopting and non-adopting companies. Five out of seven companies had the intention to continue the program. At the individual level, a project awareness of 65% was found. Employees aware of the program had a significantly more positive attitude towards cycling and reported significantly more commuter cycling than those unaware of the program (both p sustainability of the intervention is needed.

Is Home-Based, High-Intensity Interval Training Cycling Feasible and Safe for Patients With Knee Osteoarthritis?: Study Protocol for a Randomized Pilot Study.

Science.gov (United States)

Keogh, Justin W L; Grigg, Josephine; Vertullo, Christopher J

2017-03-01

Osteoarthritis (OA) is a degenerative joint disease affecting the knee joint of many middle-aged and older adults. As OA symptoms typically involve knee pain and stiffness, individuals with knee OA are often insufficiently physically active, have low levels of physical function, and are at increased risk of other comorbidities and reduced quality of life. While moderate-intensity continuous training (MICT) cycling is often recommended, little is known about the feasibility, safety, and benefits of high-intensity interval training (HIIT) cycling for this population, even though the feasibility, safety, and benefits of HIIT have been demonstrated in other chronic disease groups. The primary objective of this pilot study was to examine the feasibility and safety of home-based HIIT and MICT cycling in middle-aged and older adults with knee OA. A secondary objective was to gain some insight into the relative efficacy of HIIT and MICT for improving health status (pain, stiffness, and disability), muscle function, and body composition in this population. This study protocol is being published separately to allow a detailed description of the research methods, explain the rationale for choosing the methodological details, and to stimulate consideration of the best means to simulate a research protocol that is relevant to a real-life treatment environment. Randomized pilot study protocol. This trial sought to recruit 40 middle-aged and older adults with knee OA. Participants were randomly allocated to either continuous (MICT) or HIIT home-based cycle training programs, with both programs requiring the performance of 4 cycling sessions (approximately 25 minutes per session) each week. Participants were measured at baseline and postintervention (8 weeks). Feasibility and safety were assessed by adherence rate, dropout rate, and number of adverse events. The relative efficacy of the cycling programs was investigated by 2 knee OA health status questionnaires (Western Ontario

Clean Coal Technology Programs: Completed Projects (Volume 2)

Energy Technology Data Exchange (ETDEWEB)

Assistant Secretary for Fossil Energy

2003-12-01

Annual report on the Clean Coal Technology Demonstration Program (CCTDP), Power Plant Improvement Initiative (PPII), and Clean Coal Power Initiative (CCPI). The report addresses the roles of the programs, implementation, funding and costs, project descriptions, legislative history, program history, environmental aspects, and project contacts. The project descriptions describe the technology and provides a brief summary of the demonstration results.

The advanced controls program at Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Knee, H.E.; White, J.D.

1990-01-01

The Oak Ridge National Laboratory (ORNL), under sponsorship of the US Department of Energy (DOE), is conducting research that will lead to advanced, automated control of new liquid-metal-reactor (LMR) nuclear power plants. Although this program of research (entitled the ''Advanced Controls Program'') is focused on LMR technology, it will be capable of providing control design, test, and qualification capability for other advanced reactor designs (e.g., the advanced light water reactor [ALWR] and high temperature gas-cooled reactor [HTGR] designs), while also benefiting existing nuclear plants. The Program will also have applicability to complex, non-nuclear process control environments (e.g., petrochemical, aerospace, etc.). The Advanced Controls Program will support capabilities throughout the entire plant design life cycle, i.e., from the initial interactive first-principle dynamic model development for the process, systems, components, and instruments through advanced control room qualification. The current program involves five principal areas of research activities: (1) demonstrations of advanced control system designs, (2) development of an advanced controls design environment, (3) development of advanced control strategies, (4) research and development (R ampersand D) in human-system integration for advanced control system designs, and (5) testing and validation of advanced control system designs. Discussion of the research in these five areas forms the basis of this paper. Also included is a description of the research directions of the program. 8 refs

The Arnon-Buchanan cycle: a retrospective, 1966-2016.

Science.gov (United States)

Buchanan, Bob B; Sirevåg, Reidun; Fuchs, Georg; Ivanovsky, Ruslan N; Igarashi, Yasuo; Ishii, Masaharu; Tabita, F Robert; Berg, Ivan A

2017-11-01

For the first decade following its description in 1954, the Calvin-Benson cycle was considered the sole pathway of autotrophic CO 2 assimilation. In the early 1960s, experiments with fermentative bacteria uncovered reactions that challenged this concept. Ferredoxin was found to donate electrons directly for the reductive fixation of CO 2 into alpha-keto acids via reactions considered irreversible. Thus, pyruvate and alpha-ketoglutarate could be synthesized from CO 2 , reduced ferredoxin and acetyl-CoA or succinyl-CoA, respectively. This work opened the door to the discovery that reduced ferredoxin could drive the Krebs citric acid cycle in reverse, converting the pathway from its historical role in carbohydrate breakdown to one fixing CO 2 . Originally uncovered in photosynthetic green sulfur bacteria, the Arnon-Buchanan cycle has since been divorced from light and shown to function in a variety of anaerobic chemoautotrophs. In this retrospective, colleagues who worked on the cycle at its inception in 1966 and those presently working in the field trace its development from a controversial reception to its present-day inclusion in textbooks. This pathway is now well established in major groups of chemoautotrophic bacteria, instead of the Calvin-Benson cycle, and is increasingly referred to as the Arnon-Buchanan cycle. In this retrospective, separate sections have been written by the authors indicated. Bob Buchanan wrote the abstract and the concluding comments.

Heavy water reactors on the once-through uranium cycle

International Nuclear Information System (INIS)

1978-05-01

This paper presents preliminary technical and economic data to INFCE on the once-through uranium fuel cycle for use in early comparisons of alternate nuclear systems. The denatured thorium fuel cycle is discussed in a companion paper. Information for this paper was developed under an ongoing program, and more complete reporting of the evaluation of the heavy water reactor and its fuel cycles is planned toward the end of the year

EZLP: An Interactive Computer Program for Solving Linear Programming Problems. Final Report.

Science.gov (United States)

Jarvis, John J.; And Others

Designed for student use in solving linear programming problems, the interactive computer program described (EZLP) permits the student to input the linear programming model in exactly the same manner in which it would be written on paper. This report includes a brief review of the development of EZLP; narrative descriptions of program features,…

Technical baseline description for in situ vitrification laboratory test equipment

International Nuclear Information System (INIS)

Beard, K.V.; Bonnenberg, R.W.; Watson, L.R.

1991-09-01

IN situ vitrification (ISV) has been identified as possible waste treatment technology. ISV was developed by Pacific Northwest Laboratory (PNL), Richland, Washington, as a thermal treatment process to treat contaminated soils in place. The process, which electrically melts and dissolves soils and associated inorganic materials, simultaneously destroys and/or removes organic contaminants while incorporating inorganic contaminants into a stable, glass-like residual product. This Technical Baseline Description has been prepared to provide high level descriptions of the design of the Laboratory Test model, including all design modifications and safety improvements made to data. Furthermore, the Technical Baseline Description provides a basic overview of the interface documents for configuration management, program management interfaces, safety, quality, and security requirements. 8 figs

RELAP4/MOD5: a computer program for transient thermal-hydraulic analysis of nuclear reactors and related systems. User's manual. Volume II. Program implementation

International Nuclear Information System (INIS)

1976-06-01

A discussion is presented of the use of the RELAP4/MOD5 computer program in simulating the thermal-hydraulic behavior of light-water reactor systems when subjected to postulated transients such as a LOCA, pump failure, or nuclear excursion. The volume is divided into main sections which cover: (1) program description, (2) input data, (3) problem initialization, (4) user guidelines, (5) output discussion, (6) source program description, (7) implementation requirements, (8) data files, (9) description of PLOTR4M, (10) description of STH20, (11) summary flowchart, (12) sample problems, (13) problem definition, and (14) problem input

GetData Digitizing Program Code: Description, Testing, Training

International Nuclear Information System (INIS)

Taova, S.

2013-01-01

90 percents of compilation in our center is obtained by data digitizing. So we are rather interested in the development of different techniques of data digitizing. Plots containing a great amount of points and solid lines are most complicated for digitizing. From our point of view including to the Exfor-Digitizer procedures of automatic or semi-automatic digitizing will allow to simplify significantly this process. We managed to test some free available program codes. Program GETDATA Graph Digitizer (www.getdata- graph-digitizer.com) looks more suitable for our purposes. GetData Graph Digitizer is a program for digitizing graphs, plots and maps. Main features of GetData Graph Digitizer are: - supported graphics formats are TIFF, JPEG, BMP and PCX; - two algorithms for automatic digitizing; - convenient manual digitizing; - reorder tool for easy points reordering; - save/open workspace, which allows to save the work and return to it later; - obtained data can be exported to the clipboard; - export to the formats: TXT (text file), XLS (MS Excel), XML, DXF (AutoCAD) and EPS (PostScript). GetData Graph Digitizer includes two algorithms for automatic digitizing. Auto trace lines: This method is designed to digitize solid lines. Choose the starting point, and the program will trace the line, stopping at it's end. To trace the line use Operations =>Auto trace lines menu or context menu ('Auto trace lines' item). To choose starting point click left mouse button, or click right mouse button to additionally choose direction for line tracing. Digitize area: The second way is to set digitizing area. This method works for any type of lines, including dashed lines. Data points are set at the intersection of grid with the line. You can choose the type of grid (X grid or Y grid), and set the distance between grid lines. You can also make the grid be shifted in such a way, that it will pass through a specific X (or Y) value. To digitize area use Operations →Digitize area menu

Ecology and Life Cycle Patterns of Echinococcus Species.

Science.gov (United States)

Romig, T; Deplazes, P; Jenkins, D; Giraudoux, P; Massolo, A; Craig, P S; Wassermann, M; Takahashi, K; de la Rue, M

2017-01-01

The genus Echinococcus is composed of eight generally recognized species and one genotypic cluster (Echinococcus canadensis cluster) that may in future be resolved into one to three species. For each species, we review existing information on transmission routes and life cycles in different geographical contexts and - where available - include basic biological information of parasites and hosts (e.g., susceptibility of host species). While some Echinococcus spp. are transmitted in life cycles that involve predominantly domestic animals (e.g., dog - livestock cycles), others are wildlife parasites that do or do not interact with domestic transmission. In many cases, life cycle patterns of the same parasite species differ according to geography. Simple life cycles contrast with transmission patterns that are highly complex, involving multihost systems that may include both domestic and wild mammals. Wildlife transmission may be primary or secondary, i.e., resulting from spillovers from domestic animals. For most of the species and regions, existing information does not yet permit a conclusive description of transmission systems. Such data, however, would be highly relevant, e.g., for anticipation of geographical changes of the presence and frequency of these parasites in a warming world, or for initiating evidence-based control strategies. Copyright © 2017 Elsevier Ltd. All rights reserved.

Modeling the Nuclear Fuel Cycle

International Nuclear Information System (INIS)

Jacobson, Jacob J.; Dunzik-Gougar, Mary Lou; Juchau, Christopher A.

2010-01-01

A review of existing nuclear fuel cycle systems analysis codes was performed to determine if any existing codes meet technical and functional requirements defined for a U.S. national program supporting the global and domestic assessment, development and deployment of nuclear energy systems. The program would be implemented using an interconnected architecture of different codes ranging from the fuel cycle analysis code, which is the subject of the review, to fundamental physical and mechanistic codes. Four main functions are defined for the code: (1) the ability to characterize and deploy individual fuel cycle facilities and reactors in a simulation, while discretely tracking material movements, (2) the capability to perform an uncertainty analysis for each element of the fuel cycle and an aggregate uncertainty analysis, (3) the inclusion of an optimization engine able to optimize simultaneously across multiple objective functions, and (4) open and accessible code software and documentation to aid in collaboration between multiple entities and facilitate software updates. Existing codes, categorized as annualized or discrete fuel tracking codes, were assessed according to the four functions and associated requirements. These codes were developed by various government, education and industrial entities to fulfill particular needs. In some cases, decisions were made during code development to limit the level of detail included in a code to ease its use or to focus on certain aspects of a fuel cycle to address specific questions. The review revealed that while no two of the codes are identical, they all perform many of the same basic functions. No code was able to perform defined function 2 or several requirements of functions 1 and 3. Based on this review, it was concluded that the functions and requirements will be met only with development of a new code, referred to as GENIUS.

Cycle 24 COS FUV Internal/External Wavelength Scale Monitor

Science.gov (United States)

Fischer, William J.

2018-02-01

We report on the monitoring of the COS FUV wavelength scale zero-points during Cycle 24 in program 14855. Select cenwaves were monitored for all FUV gratings at Lifetime Position 3. The target and cenwaves have remained the same since Cycle 21, with a change only to the target acquisition sequence. All measured offsets are within the error goals, although the G140L cenwaves show offsets at the short-wavelength end of segment A that are approaching the tolerance. This behavior will be closely monitored in subsequent iterations of the program.

Policy paper no. 1 : Pedestrians and cycling

Energy Technology Data Exchange (ETDEWEB)

Zbogar, H. [City of Brampton, ON (Canada)

2004-06-01

The City of Brampton's Transportation and Transit Master Plan includes a workable plan to promote walking and cycling facilities in the area. This paper reviewed existing policies, programs and practices in the City of Brampton that pertain to cycling and walking. Walking and cycling issues and trends were also reviewed with reference to the principles that improve the pedestrian and cycling environment, such as safety, security, convenience, continuity, comfort, coherence and attractiveness. The recreation, health and fitness benefits of walking and cycling were also outlined along with transportation, environmental, and economic benefits. The official plan for the city was included with reference to walking and cycling sections in the city. It was noted that effective pathways should be customer driven and respond to the needs of residents. They should also accommodate all uses, including walking, jogging, cycling and in-line skating. Experience of other jurisdictions in Ontario in providing walking and cycling facilities were also reviewed. It was noted that walking and cycling are significant elements of an intermodal transportation system and have a strong bearing on a city's vision for urban street design. 11 refs., 2 tabs., 3 figs.

Educating change agents: a qualitative descriptive study of graduates of a Master's program in evidence-based practice.

Science.gov (United States)

Hole, Grete Oline; Brenna, Sissel Johansson; Graverholt, Birgitte; Ciliska, Donna; Nortvedt, Monica Wammen

2016-02-25

Health care professionals are expected to build decisions upon evidence. This implies decisions based on the best available, current, valid and relevant evidence, informed by clinical expertise and patient values. A multi-professional master's program in evidence-based practice was developed and offered. The aims of this study were to explore how students in this program viewed their ability to apply evidence-based practice and their perceptions of what constitute necessary conditions to implement evidence-based practice in health care organizations, one year after graduation. A qualitative descriptive design was chosen to examine the graduates' experiences. All students in the first two cohorts of the program were invited to participate. Six focus-group interviews, with a total of 21 participants, and a telephone interview of one participant were conducted. The data was analyzed thematically, using the themes from the interview guide as the starting point. The graduates reported that an overall necessary condition for evidence-based practice to occur is the existence of a "readiness for change" both at an individual level and at the organizational level. They described that they gained personal knowledge and skills to be "change-agents" with "self-efficacy, "analytic competence" and "tools" to implement evidence based practice in clinical care. An organizational culture of a "learning organization" was also required, where leaders have an "awareness of evidence- based practice", and see the need for creating "evidence-based networks". One year after graduation the participants saw themselves as "change agents" prepared to improve clinical care within a learning organization. The results of this study provides useful information for facilitating the implementation of EBP both from educational and health care organizational perspectives.

75 FR 52010 - Land and Water Conservation Fund Description and Notification, Performance Reports, Agreements...

Science.gov (United States)

2010-08-24

... DEPARTMENT OF THE INTERIOR National Park Service Land and Water Conservation Fund Description and.... SUPPLEMENTARY INFORMATION: The Land and Water Conservation Fund Act of 1965 (LWCF Act) (16 U.S.C 4601-4 et seq... for this program: 1. Description and Notification Form Title: Land and Water Conservation Fund...

Mississippi Curriculum Framework for Computer Information Systems Technology. Computer Information Systems Technology (Program CIP: 52.1201--Management Information Systems & Business Data). Computer Programming (Program CIP: 52.1201). Network Support (Program CIP: 52.1290--Computer Network Support Technology). Postsecondary Programs.

Science.gov (United States)

Mississippi Research and Curriculum Unit for Vocational and Technical Education, State College.

This document, which is intended for use by community and junior colleges throughout Mississippi, contains curriculum frameworks for two programs in the state's postsecondary-level computer information systems technology cluster: computer programming and network support. Presented in the introduction are program descriptions and suggested course…

Description of the KEEP Reading Curriculum, 1975-76. Technical Report No. 43.

Science.gov (United States)

Au, Kathryn H.

The Kamehameha Early Education Program (KEEP) is a research and development program designed to develop, demonstrate, and disseminate methods for improving the education of Hawaiian and part-Hawaiian children; this report contains a description of the reading curriculum used in the KEEP demonstration school during the 1975-76 school year. The…

Nuclear fuel cycle facility accident analysis handbook

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-03-01

The purpose of this Handbook is to provide guidance on how to calculate the characteristics of releases of radioactive materials and/or hazardous chemicals from nonreactor nuclear facilities. In addition, the Handbook provides guidance on how to calculate the consequences of those releases. There are four major chapters: Hazard Evaluation and Scenario Development; Source Term Determination; Transport Within Containment/Confinement; and Atmospheric Dispersion and Consequences Modeling. These chapters are supported by Appendices, including: a summary of chemical and nuclear information that contains descriptions of various fuel cycle facilities; details on how to calculate the characteristics of source terms for releases of hazardous chemicals; a comparison of NRC, EPA, and OSHA programs that address chemical safety; a summary of the performance of HEPA and other filters; and a discussion of uncertainties. Several sample problems are presented: a free-fall spill of powder, an explosion with radioactive release; a fire with radioactive release; filter failure; hydrogen fluoride release from a tankcar; a uranium hexafluoride cylinder rupture; a liquid spill in a vitrification plant; and a criticality incident. Finally, this Handbook includes a computer model, LPF No.1B, that is intended for use in calculating Leak Path Factors. A list of contributors to the Handbook is presented in Chapter 6. 39 figs., 35 tabs.

Nuclear fuel cycle facility accident analysis handbook

International Nuclear Information System (INIS)

1998-03-01

The purpose of this Handbook is to provide guidance on how to calculate the characteristics of releases of radioactive materials and/or hazardous chemicals from nonreactor nuclear facilities. In addition, the Handbook provides guidance on how to calculate the consequences of those releases. There are four major chapters: Hazard Evaluation and Scenario Development; Source Term Determination; Transport Within Containment/Confinement; and Atmospheric Dispersion and Consequences Modeling. These chapters are supported by Appendices, including: a summary of chemical and nuclear information that contains descriptions of various fuel cycle facilities; details on how to calculate the characteristics of source terms for releases of hazardous chemicals; a comparison of NRC, EPA, and OSHA programs that address chemical safety; a summary of the performance of HEPA and other filters; and a discussion of uncertainties. Several sample problems are presented: a free-fall spill of powder, an explosion with radioactive release; a fire with radioactive release; filter failure; hydrogen fluoride release from a tankcar; a uranium hexafluoride cylinder rupture; a liquid spill in a vitrification plant; and a criticality incident. Finally, this Handbook includes a computer model, LPF No.1B, that is intended for use in calculating Leak Path Factors. A list of contributors to the Handbook is presented in Chapter 6. 39 figs., 35 tabs

The NEWS Water Cycle Climatology

Science.gov (United States)

Rodell, M.; Beaudoing, H. K.; L'Ecuyer, T.; Olson, W. S.

2012-12-01

NASA's Energy and Water Cycle Study (NEWS) program fosters collaborative research towards improved quantification and prediction of water and energy cycle consequences of climate change. In order to measure change, it is first necessary to describe current conditions. The goal of the first phase of the NEWS Water and Energy Cycle Climatology project was to develop "state of the global water cycle" and "state of the global energy cycle" assessments based on data from modern ground and space based observing systems and data integrating models. The project was a multi-institutional collaboration with more than 20 active contributors. This presentation will describe the results of the water cycle component of the first phase of the project, which include seasonal (monthly) climatologies of water fluxes over land, ocean, and atmosphere at continental and ocean basin scales. The requirement of closure of the water budget (i.e., mass conservation) at various scales was exploited to constrain the flux estimates via an optimization approach that will also be described. Further, error assessments were included with the input datasets, and we examine these in relation to inferred uncertainty in the optimized flux estimates in order to gauge our current ability to close the water budget within an expected uncertainty range.

The NEWS Water Cycle Climatology

Science.gov (United States)

Rodell, Matthew; Beaudoing, Hiroko Kato; L'Ecuyer, Tristan; William, Olson

2012-01-01

NASA's Energy and Water Cycle Study (NEWS) program fosters collaborative research towards improved quantification and prediction of water and energy cycle consequences of climate change. In order to measure change, it is first necessary to describe current conditions. The goal of the first phase of the NEWS Water and Energy Cycle Climatology project was to develop "state of the global water cycle" and "state of the global energy cycle" assessments based on data from modern ground and space based observing systems and data integrating models. The project was a multi-institutional collaboration with more than 20 active contributors. This presentation will describe the results of the water cycle component of the first phase of the project, which include seasonal (monthly) climatologies of water fluxes over land, ocean, and atmosphere at continental and ocean basin scales. The requirement of closure of the water budget (i.e., mass conservation) at various scales was exploited to constrain the flux estimates via an optimization approach that will also be described. Further, error assessments were included with the input datasets, and we examine these in relation to inferred uncertainty in the optimized flux estimates in order to gauge our current ability to close the water budget within an expected uncertainty range.

Development of computer software for pavement life cycle cost analysis.

Science.gov (United States)

1988-01-01

The life cycle cost analysis program (LCCA) is designed to automate and standardize life cycle costing in Virginia. It allows the user to input information necessary for the analysis, and it then completes the calculations and produces a printed copy...

Federal Geothermal Research Program Update Fiscal Year 2000; ANNUAL

International Nuclear Information System (INIS)

Renner, J.L.

2001-01-01

The Department of Energy's Geothermal Program serves two broad purposes: (1) to assist industry in overcoming near-term barriers by conducting cost-shared research and field verification that allows geothermal energy to compete in today's aggressive energy markets; and (2) to undertake fundamental research with potentially large economic payoffs. The four categories of work used to distinguish the research activities of the Geothermal Program during FY 2000 reflect the main components of real-world geothermal projects. These categories form the main sections of the project descriptions in this Research Update. Exploration Technology research focuses on developing instruments and techniques to discover hidden hydrothermal systems and to explore the deep portions of known systems. Research in geophysical and geochemical methods is expected to yield increased knowledge of hidden geothermal systems. Reservoir Technology research combines laboratory and analytical investigations with equipment development and field testing to establish practical tools for resource development and management for both hydrothermal reservoirs and enhanced geothermal systems. Research in various reservoir analysis techniques is generating a wide range of information that facilitates development of improved reservoir management tools. Drilling Technology focuses on developing improved, economic drilling and completion technology for geothermal wells. Ongoing research to avert lost circulation episodes in geothermal drilling is yielding positive results. Conversion Technology research focuses on reducing costs and improving binary conversion cycle efficiency, to permit greater use of the more abundant moderate-temperature geothermal resource, and on the development of materials that will improve the operating characteristics of many types of geothermal energy equipment. Increased output and improved performance of binary cycles will result from investigations in heat cycle research

Effect on 12-week Intensive Dietary and Exercise Program on Weight Reduction and Maintenance in Obese Women with Weight Cycling History.

Science.gov (United States)

Kwon, Ha Nui; Nam, Sang-Seok; Park, Yoo Kyoung

2017-07-01

This study examined the effect of 12-week intensive dietary and exercise intervention program on body composition and stress-related hormones in obese women and to examine the residual effect after the intervention. The participants of this study were 30 obese women who had a body mass index of over 25 kg/m 2 and over 30% in body fat. They were classified into 2 groups depending on the history of weight cycling (WC); the WC group (≥ ±5% of the original body weight) and the non-weight cycling (NWC) group. Both groups were subject to a nutritional intervention program every 2 weeks with a mandatory exercise intervention for 12 weeks. Thereafter, the nutrition/exercise interventions were ceased for 12 weeks, after which the participants' levels of the hormones relating to energy metabolism and stress, meal intakes, dietary habits, level of knowledge on sodium intake, frequency of sodium intake, and quality of life (QOL) were checked. The changes of body weight were 71.3 ± 5.5 kg (week 0) vs. 65.0 ± 6.6 kg (week 12) vs. 65.6 ± 7.1 kg (week 24) in WC group and 71.6 ± 8.6 kg (week 0) vs. 68.8 ± 9.7 kg (week 12) vs. 70.3 ± 9.4 kg (week 24) in the NWC group. The levels of hormones, meal intakes, and QOL scores were better in the WC group, as adherence to the nutritional intervention was higher. We suggest that that adherence to dietary habits heavily influences weight loss and maintenance in individuals who frequently attempt to lose weight and consequently go through a vicious cycle of weight recycling.

International Nuclear Fuel Cycle Fact Book

International Nuclear Information System (INIS)

Leigh, I.W.

1992-05-01

As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need exists costs for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book has been compiled to meet that need. The information contained in the International Nuclear Fuel Cycle Fact Book has been obtained from many unclassified sources: nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NMEA activities reports; and proceedings of conferences and workshops. The data listed typically do not reflect any single source but frequently represent a consolidation/combination of information

International Nuclear Fuel Cycle Fact Book

International Nuclear Information System (INIS)

Leigh, I.W.; Mitchell, S.J.

1990-01-01

As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need has developed for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book was compiled to meet that need. The information contained in the International Nuclear Fuel Cycle Fact Book has been obtained from many unclassified sources: nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NEA activities reports; proceedings of conferences and workshops, etc. The data listed do not reflect any one single source but frequently represent a consolidation/combination of information

International Nuclear Fuel Cycle Fact Book

Energy Technology Data Exchange (ETDEWEB)

Leigh, I W; Mitchell, S J

1990-01-01

As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need has developed for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book was compiled to meet that need. The information contained in the International Nuclear Fuel Cycle Fact Book has been obtained from many unclassified sources: nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NEA activities reports; proceedings of conferences and workshops, etc. The data listed do not reflect any one single source but frequently represent a consolidation/combination of information.

Proceedings of the of the Tenth Workshop on Language Descriptions, Tools and Applications (LDTA 2010)

DEFF Research Database (Denmark)

Brabrand, Claus

2010-01-01

-Louis Giavitto ("A Domain Specific Language for Complex Natural & Artificial Systems Simulations") and the 11 contributed papers that were selected for presentation and the proceedings by the programme committee from 30 submissions (i.e., 37% acceptance rate). Every submission was reviewed by at least three......This volume contains the proceedings of the Tenth Workshop on Language Descriptions, Tools and Applications (LDTA 2010), held in Paphos, Cyprus on March 28--29, 2010. LDTA is a two-day satellite event of ETAPS (European Joint Conferences on Theory and Practice of Software) organized in cooperation...... with ACM Sigplan. LDTA is an application and tool-oriented forum on meta programming in a broad sense. A meta program is a program that takes other programs as input or output. The focus of LDTA is on generated or otherwise efficiently implemented meta programs, possibly using high level descriptions...

Life Cycle Assessment - Theory and Practice

DEFF Research Database (Denmark)

This book is a uniquely pedagogical while still comprehensive state-of-the-art description of LCA-methodology and its broad range of applications. The five parts of the book conveniently provide: I) the history and context of Life Cycle Assessment (LCA) with its central role as quantitative and s...... needed to perform an LCA. V) An appendix with an LCA report template, a full example LCA report serving as inspiration for students who write their first LCA report, and a more detailed overview of existing LCIA methods and their similarities and differences....

Barnwell Nuclear Fuels Plant applicability study. Volume III. Appendices

International Nuclear Information System (INIS)

1978-03-01

Volume III suppliees supporting information to assist Congress in making a decision on the optimum utilization of the Barnwell Nuclear Fuels Plant. Included are applicable fuel cycle policies; properties of reference fuels; description and evaluation of alternative operational (flue cycle) modes; description and evaluation of safeguards systems and techniques; description and evaluation of spiking technology; waste and waste solidification evaluation; and Department of Energy programs relating to nonproliferation

Spectral shift controlled reactor, UO2 once-through cycle optimized

International Nuclear Information System (INIS)

1978-05-01

This paper presents technical and economic data on the SSCR which may be of use in the International Fuel Cycle Evaluation Program to intercompare alternative nuclear systems. Included in this data is information on the optimized UO 2 once-through fuel cycle. The ''optimized'' cycle refers to a UO 2 once-through cycle which has better fuel resource utilization than the conventional UO 2 cycle employed in current design PWRs. This fuel cycle uses more in-core batches and a higher discharge exposure than current PWR fuel management schemes. The proposed cycle is not optimal in a mathematical sense, however, since additional resource savings can be obtained if the discharge exposure is extended to even higher values and the number of in-core fuel batches is increased further. The present cycle was selected as ''optimal'' based on the assumption that it can be achieved with only an extension of fuel design technology and can therefore be deployed in a relatively short time frame. In the longer term, modification to reactor geometry as well as further extensions of discharge burnup might be considered to realize additional reduction in uranium resource requirements. The data contained in this paper has been developed by an ongoing program which at the present time is only 50% complete. The data presented here should therefore be considered preliminary and will be updated in the future as required

CANDU fuel cycle options in Korea

International Nuclear Information System (INIS)

Boczar, P.G.; Fehrenbach, P.J.; Meneley, D.A.

1996-04-01

The easiest first step in CANDU fuel-cycle evolution may be the use of slightly enriched uranium (SEU), including recovered uranium from reprocessed LWR spent fuel. Relatively low enrichment (up to 1.2%) will result in a twoto three-fold reduction in the quantity of spent fuel per unit energy production, reductions in fuel-cycle costs, and greater flexibility in the design of new reactors. The CANFLEX (CANDU FLEXible) fuel bundle would be the optimal fuel carrier. A country that has both CANDU and PWR reactors can exploit the natural synergism between these two reactor types to minimize overall waste production, and maximize energy derived from the fuel. This synergism can be exploited through several different fuel cycles. A high burnup CANDU MOX fuel design could be used to utilize plutonium from conventional reprocessing or more advanced reprocessing options (such as co-processing). DUPIC (Direct Use of Spent PWR Fuel In CANDU) represents a recycle option that has a higher degree of proliferation resistance than does conventional reprocessing, since it uses only dry processes for converting spent PWR fuel into CANDU fuel, without separating the plutonium. Good progress is being made in the current KAERI, AECL, and U.S. Department of State program in demonstrating the technical feasibility of DUPIC. In the longer term, CANDU reactors offer even more dramatic synergistic fuel cycles with PWR or FBR reactors. If the objective of a national fuel-cycle program is the minimization of actinide waste or destruction of long-lived fission products, then studies have shown the superiority of CANDU reactors in meeting this objective. Long-term energy security can be assured either through the thorium cycle or through a CANDU 1 FBR system, in which the FBR would be operated as a 'fuel factory,' providing the fissile material to power a number of lower-cost, high efficiency CANDU reactors. In summary, the CANDU reactor's simple fuel design, high neutron economy, and on

An advanced conceptual Tokamak fusion power reactor utilizing closed cycle helium gas turbines

International Nuclear Information System (INIS)

Conn, R.W.

1976-01-01

UWMAK-III is a conceptual Tokamak reactor designed to study the potential and the problems associated with an advanced version of Tokamaks as power reactors. Design choices have been made which represent reasonable extrapolations of present technology. The major features are the noncircular plasma cross section, the use of TZM, a molybdenum based alloy, as the primary structural material, and the incorporation of a closed-cycle helium gas turbine power conversion system. A conceptual design of the turbomachinery is given together with a preliminary heat exchanger analysis that results in relatively compact designs for the generator, precooler, and intercooler. This paper contains a general description of the UWMAK-III system and a discussion of those aspects of the reactor, such as the burn cycle, the blanket design and the heat transfer analysis, which are required to form the basis for discussing the power conversion system. The authors concentrate on the power conversion system and include a parametric performance analysis, an interface and trade-off study and a description of the reference conceptual design of the closed-cycle helium gas turbine power conversion system. (Auth.)

Advisory processes and their descriptive data

Directory of Open Access Journals (Sweden)

Milan Mišovič

2005-01-01

Full Text Available Processes are regarded as a representative of all firm activities what is valid for Web-based Advisory Systems, too. Interpretation of processes from the both sides managers and informaticians is naturally different what is given by their scientific platforms and observed objectives. Managers have connected all firm processes with the firm prosperity and firm competition ability. Therefore they have followed understanding, modeling and regular improving of all processes what should stimulate and evoke using of process revisions (reengineering. The main role in such process understanding is thus committed to the firm management.The most professional computer process implementations are dominant objectives of Informaticians. In this conception all processes have been understood as real sequences of partial transactions (elementary firm activities and data processed by them regardless of using of a structural or object process approach modeling. The process and transaction models, submitted by informaticians, are connected with process content orientation. This content has to be programmed. The firm management represents the main resource of the process knowledge used by informaticians.In addition to these two process conceptions there is a different approach based on a process description by a descriptive data. The descriptive data are not oriented to a process content but to its theoretical conception and real implementation. The descriptive data processing inside special algebra operations can bring a lot of very important and easily economically interpreted results.

Mississippi Curriculum Framework for Welding and Cutting Programs (Program CIP: 48.0508--Welder/Welding Technologist). Postsecondary Programs.

Science.gov (United States)

Mississippi Research and Curriculum Unit for Vocational and Technical Education, State College.

This document, which is intended for use by community and junior colleges throughout Mississippi, contains curriculum frameworks for the course sequences in the welding and cutting programs cluster. Presented in the introductory section are a description of the program and suggested course sequence. Section I lists baseline competencies, and…

Conceptual modular description of the high-level waste management system for system studies model development

International Nuclear Information System (INIS)

McKee, R.W.; Young, J.R.; Konzek, G.J.

1992-08-01

This document presents modular descriptions of possible alternative components of the federal high-level radioactive waste management system and the procedures for combining these modules to obtain descriptions for alternative configurations of that system. The 20 separate system component modules presented here can be combined to obtain a description of any of the 17 alternative system configurations (i.e., scenarios) that were evaluated in the MRS Systems Studies program (DOE 1989a). First-approximation descriptions of other yet-undefined system configurations could also be developed for system study purposes from this database. The descriptions include, in a modular format, both functional descriptions of the processes in the waste management system, plus physical descriptions of the equipment and facilities necessary for performance of those functions

Graphic Interface for LCP2 Optimization Program

DEFF Research Database (Denmark)

Nicolae, Taropa Laurentiu; Gaunholt, Hans

1998-01-01

This report provides information about the software interface that is programmed for the Optimization Program LCP2. The first part is about the general description of the program followed by a guide for using the interface. The last chapters contain a discussion about problems or futute extension...... of the project. The program is written in Visual C++5.0 on a Windows NT4.0 operating system.......This report provides information about the software interface that is programmed for the Optimization Program LCP2. The first part is about the general description of the program followed by a guide for using the interface. The last chapters contain a discussion about problems or futute extensions...

FY 1996 solid waste integrated life-cycle forecast characteristics summary. Volumes 1 and 2

Energy Technology Data Exchange (ETDEWEB)

Templeton, K.J.

1996-05-23

For the past six years, a waste volume forecast has been collected annually from onsite and offsite generators that currently ship or are planning to ship solid waste to the Westinghouse Hanford Company`s Central Waste Complex (CWC). This document provides a description of the physical waste forms, hazardous waste constituents, and radionuclides of the waste expected to be shipped to the CWC from 1996 through the remaining life cycle of the Hanford Site (assumed to extend to 2070). In previous years, forecast data has been reported for a 30-year time period; however, the life-cycle approach was adopted this year to maintain consistency with FY 1996 Multi-Year Program Plans. This document is a companion report to two previous reports: the more detailed report on waste volumes, WHC-EP-0900, FY1996 Solid Waste Integrated Life-Cycle Forecast Volume Summary and the report on expected containers, WHC-EP-0903, FY1996 Solid Waste Integrated Life-Cycle Forecast Container Summary. All three documents are based on data gathered during the FY 1995 data call and verified as of January, 1996. These documents are intended to be used in conjunction with other solid waste planning documents as references for short and long-term planning of the WHC Solid Waste Disposal Division`s treatment, storage, and disposal activities over the next several decades. This document focuses on two main characteristics: the physical waste forms and hazardous waste constituents of low-level mixed waste (LLMW) and transuranic waste (both non-mixed and mixed) (TRU(M)). The major generators for each waste category and waste characteristic are also discussed. The characteristics of low-level waste (LLW) are described in Appendix A. In addition, information on radionuclides present in the waste is provided in Appendix B. The FY 1996 forecast data indicate that about 100,900 cubic meters of LLMW and TRU(M) waste is expected to be received at the CWC over the remaining life cycle of the site. Based on

FY 1996 solid waste integrated life-cycle forecast characteristics summary. Volumes 1 and 2

International Nuclear Information System (INIS)

Templeton, K.J.

1996-01-01

For the past six years, a waste volume forecast has been collected annually from onsite and offsite generators that currently ship or are planning to ship solid waste to the Westinghouse Hanford Company's Central Waste Complex (CWC). This document provides a description of the physical waste forms, hazardous waste constituents, and radionuclides of the waste expected to be shipped to the CWC from 1996 through the remaining life cycle of the Hanford Site (assumed to extend to 2070). In previous years, forecast data has been reported for a 30-year time period; however, the life-cycle approach was adopted this year to maintain consistency with FY 1996 Multi-Year Program Plans. This document is a companion report to two previous reports: the more detailed report on waste volumes, WHC-EP-0900, FY1996 Solid Waste Integrated Life-Cycle Forecast Volume Summary and the report on expected containers, WHC-EP-0903, FY1996 Solid Waste Integrated Life-Cycle Forecast Container Summary. All three documents are based on data gathered during the FY 1995 data call and verified as of January, 1996. These documents are intended to be used in conjunction with other solid waste planning documents as references for short and long-term planning of the WHC Solid Waste Disposal Division's treatment, storage, and disposal activities over the next several decades. This document focuses on two main characteristics: the physical waste forms and hazardous waste constituents of low-level mixed waste (LLMW) and transuranic waste (both non-mixed and mixed) (TRU(M)). The major generators for each waste category and waste characteristic are also discussed. The characteristics of low-level waste (LLW) are described in Appendix A. In addition, information on radionuclides present in the waste is provided in Appendix B. The FY 1996 forecast data indicate that about 100,900 cubic meters of LLMW and TRU(M) waste is expected to be received at the CWC over the remaining life cycle of the site. Based on

XML Translator for Interface Descriptions

Science.gov (United States)

Boroson, Elizabeth R.

2009-01-01

A computer program defines an XML schema for specifying the interface to a generic FPGA from the perspective of software that will interact with the device. This XML interface description is then translated into header files for C, Verilog, and VHDL. User interface definition input is checked via both the provided XML schema and the translator module to ensure consistency and accuracy. Currently, programming used on both sides of an interface is inconsistent. This makes it hard to find and fix errors. By using a common schema, both sides are forced to use the same structure by using the same framework and toolset. This makes for easy identification of problems, which leads to the ability to formulate a solution. The toolset contains constants that allow a programmer to use each register, and to access each field in the register. Once programming is complete, the translator is run as part of the make process, which ensures that whenever an interface is changed, all of the code that uses the header files describing it is recompiled.

The possibilities of application of programmed instruction in the sixth grade of the second cycle of education in accordance with standards

Directory of Open Access Journals (Sweden)

Milošević Dragana

2016-01-01

Full Text Available The subject of the work is to determine the possibilities of application of programmed instruction in the teaching of geography in the case of the sixth grade students of the second cycle of education. On the basis of an experimental research the rationale for the use of this form of acquiring knowledge during the classes of processing new material is presented. The primary task of the research functioning is to determine the degree of benefits of programmed instruction when adopting new geographical teaching contents and what is the extent of applicability of this method of learning with the aim of improving teaching. The second task of the work is the application of the experiment in two classes, the control (C and experimental (E, based on which it is established which vision of learning, programmed or conventional, achieves the best results in processing geographical contents in primary school.

SITE: a methodology for assessment of energy facility siting patterns. Regional studies program

International Nuclear Information System (INIS)

Frigerio, N.A.; Habegger, L.J.; King, R.F.; Hoover, L.J.; Clark, N.A.; Cobian, J.M.

1975-08-01

The timely development of the nation's energy production capacity in a manner that minimizes potential adverse local and regional impacts associated with energy facilities requires the use of sophisticated techniques for evaluation of siting alternatives and fuel cycle options. This report is a documentation of the computerized SITE methodology that has been developed for evaluating health, environmental, and socioeconomic impacts related to utilization of alternate sites for energy production within a region of interest. The cost, impact, and attribute vectors, which are generated and displayed on density maps, can be used in a multiparameter overlay process to identify preferable siting areas. The assessment of clustered facilities in energy centers is also possible within the SITE analysis framework. An application of the SITE methodology to Northern Illinois is presented. Also included is a description of the ongoing extension of SITE for the accumulative evaluation of alternative regional energy siting patterns and fuel cycle options. An appendix provides documentation and user information for the SITE computer program

Atmospheric Science Program. Summaries of research in FY 1994

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-06-01

This report provides descriptions for all projects funded by ESD under annual contracts in FY 1994. Each description contains the project`s title; three-year funding history (in thousands of dollars); the contract period over which the funding applies; the name(s) of the principal investigator(s); the institution(s) conducting the projects; and the project`s objectives, products, approach, and results to date (for most projects older than one year). Project descriptions are categorized within the report according to program areas: atmospheric chemistry, atmospheric dynamics, and support operations. Within these categories, the descriptions are ordered alphabetically by principal investigator. Each program area is preceded by a brief text that defines the program area, states it goals and objectives, lists principal research questions, and identifies program managers. Appendixes provide the addresses and telephone numbers of the principal investigators and define the acronyms used.

The application of systems engineering principles to the prioritization of sustainable nuclear fuel cycle options

International Nuclear Information System (INIS)

Price, Robert R.; Singh, Bhupinder P.; MacKinnon, Robert J.; David Sevougian, S.

2013-01-01

We investigate the implementation of the principles of systems engineering in the U.S. Department of Energy’s Fuel Cycle Technologies (FCT) Program to provide a framework for achieving its long-term mission of demonstrating and deploying sustainable nuclear fuel cycle options. A fuel cycle “screening” methodology is introduced that provides a systematic, objective, and traceable method for evaluating and categorizing nuclear fuel cycles according to their performance in meeting sustainability objectives. The goal of the systems engineering approach is to transparently define and justify the research and development (R and D) necessary to deploy sustainable fuel cycle technologies for a given set of national policy objectives. The approach provides a path for more efficient use of limited R and D resources and facilitates dialog among a variety of stakeholder groups interested in U.S. energy policy. Furthermore, the use of systems engineering principles will allow the FCT Program to more rapidly adapt to future policy changes, including any decisions based on recommendations of the Blue Ribbon Commission on America’s Nuclear Future. Specifically, if the relative importance of policy objectives changes, the FCT Program will have a structured process to rapidly determine how this impacts potential fuel cycle performance and the prioritization of needed R and D for associated technologies. - Highlights: ► Systems engineering principles applied in U.S. DOE-NE Fuel Cycle Technology Program. ► Use of decision analysis methods for determining promising nuclear fuel cycles. ► A new screening methodology to help communicate and prioritize U.S. DOE R and D needs. ► Fuel cycles categorized by performance/risk in meeting FCT Program objectives. ► Systems engineering allows DOE-NE to more rapidly adapt to future policy changes

Descriptive Research