SEISRISK II; a computer program for seismic hazard estimation

Science.gov (United States)

Bender, Bernice; Perkins, D.M.

1982-01-01

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

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

International Nuclear Information System (INIS)

1982-08-01

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

75 FR 63480 - Medicaid Program: Implementation of Section 614 of the Children's Health Insurance Program...

Science.gov (United States)

2010-10-15

... Children's Health Insurance Program Reauthorization Act of 2009 for Adjustments to the Federal Medical... section 614 of the Children's Health Insurance Program Reauthorization Act of 2009 (CHIPRA), Public Law... Medicaid program and required by Section 614 of the Children's Health Insurance Program Reauthorization Act...

German NDE within PISC-II program

International Nuclear Information System (INIS)

Deuster, G.; Schmuelling, W.

1987-01-01

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

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)

Mark II containment lead plant program load evaluation and acceptance criteria

International Nuclear Information System (INIS)

1978-10-01

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

Section 609 Technician Training and Certification Programs

Science.gov (United States)

EPA-approved programs for technicians who service motor vehicle air conditioning (MVAC) systems. Any person who repairs or services a MVAC system for consideration must be certified under section 609 of the Clean Air Act by an EPA-approved program.

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

National Research Council Canada - National Science Library

2004-01-01

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

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

Science.gov (United States)

2010-07-01

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

Recent operating experiences and programs at EBR-II

International Nuclear Information System (INIS)

Lentz, G.L.

1984-01-01

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

Full-scale mark II CRT program facility description report

International Nuclear Information System (INIS)

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

1980-03-01

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

Continuity Between DSM-5 Section II and III Personality Disorders in a Dutch Clinical Sample.

Science.gov (United States)

Orbons, Irene M J; Rossi, Gina; Verheul, Roel; Schoutrop, Mirjam J A; Derksen, Jan L L; Segal, Daniel L; van Alphen, Sebastiaan P J

2018-05-14

The goal of this study was to evaluate the continuity across the Section II personality disorders (PDs) and the proposed Section III model of PDs in the Diagnostic and Statistical Manual of Mental Disorders (5th ed. [DSM-5]; American Psychiatric Association, 2013a ). More specifically, we analyzed association between the DSM-5 Section III pathological trait facets and Section II PDs among 110 Dutch adults (M age = 35.8 years, range = 19-60 years) receiving mental health care. We administered the Structured Clinical Interview for DSM-IV Axis II Disorders to all participants. Participants also completed the self-report Personality Inventory for DSM-5 (PID-5) as a measure of pathological trait facets. The distributions underlying the dependent variable were modeled as criterion counts, using negative binomial regression. The results provided some support for the validity of the PID-5 and the DSM-5 Section III Alternative Model, although analyses did not show a perfect match. Both at the trait level and the domain level, analyses showed mixed evidence of significant relationships between the PID-5 trait facets and domains with the traditional DSM-IV PDs.

Organic research section. 1984 review and 1985 programs

International Nuclear Information System (INIS)

Glass, R.W.

1985-02-01

This report reviews the major activities and accomplishments of the Organic Research Section in 1984 and presents the 1985 work program. The three major areas of the Section's research work are non-metallic materials which includes applications and uses of plastics, petroleum products, coatings and elastomers; reactor waste management; and activity transport/decontamination of nuclear systems. In 1984, 50% of the Section's resources were used on studies in support of nuclear generation, 13% on reactor waste, and 37% on general activities and work in support of utilization, transmission and distribution, and thermal and hydraulic programs. About 60% of the section's work was supported by transfer and revenue funds as a result of urgent short-term work requirements which resulted in 68% of the work falling into the technical investigation, consulting and testing categories

Alternative Teacher Preparation Programs. Title II News You Can Use

Science.gov (United States)

Office of Postsecondary Education, US Department of Education, 2015

2015-01-01

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

Relating DSM-5 section II and section III personality disorder diagnostic classification systems to treatment planning.

Science.gov (United States)

Morey, Leslie C; Benson, Kathryn T

2016-07-01

Beginning with DSM-III, the inclusion of a "personality" axis was designed to encourage awareness of personality disorders and the treatment-related implications of individual differences, but since that time there is little accumulated evidence that the personality disorder categories provide substantial treatment-related guidance. The DSM-5 Personality and Personality Disorders Work Group sought to develop an Alternative Model for personality disorder, and this study examined whether this model is more closely related to clinicians' decision-making processes than the traditional categorical personality disorder diagnoses. A national sample of 337 clinicians provided complete personality disorder diagnostic information and several treatment-related clinical judgments about one of their patients. The dimensional concepts of the DSM-5 Alternative Model for personality disorders demonstrated stronger relationships than categorical DSM-IV/DSM-5 Section II diagnoses to 10 of 11 clinical judgments regarding differential treatment planning, optimal treatment intensity, and long-term prognosis. The constructs of the DSM-5 Alternative Model for personality disorders may provide more clinically useful information for treatment planning than the official categorical personality disorder diagnostic system retained in DSM-5 Section II. Copyright © 2016 Elsevier Inc. All rights reserved.

Mission Plan for the Civilian Radioactive Waste Management Program. Volume I. Part I. Overview and current program plans; Part II. Information required by the Nuclear Waste Policy Act of 1982

International Nuclear Information System (INIS)

1985-06-01

The Misson Plan is divided into two parts. Part I describes the overall goals, objectives, and strategy for the disposal of spent nuclear fuel and high-level waste. It explains that, to meet the directives of the Nuclear Waste Policy Act, the DOE intends to site, design, construct, and start operating a mined geologic repository by January 31, 1998. The Act specifies that the costs of these activities will be borne by the owners and generators of the waste received at the repository. Part I further describes the other components of the waste-management program - monitored retrievable storage, Federal interim storage, and transportation - as well as systems integration activities. Also discussed are institutional plans and activities as well as the program-management system being implemented by the Office of Civilian Radioactive Waste Management. Part II of the Mission Plan presents the detailed information required by Section 301(a) of the Act - key issues and information needs; plans for obtaining the necessary information; potential financial, institutional, and legal issues; plans for the test and evaluation facility; the principal results obtained to date from site investigations; information on the site-characterization programs; information on the waste package; schedules; costs; and socioeconomic impacts. In accordance with Section 301(a) of the Act, Part II is concerned primarily with the repository program

Heavy-Section Steel Irradiation Program

International Nuclear Information System (INIS)

Corwin, W.R.

1990-08-01

The primary goal of the Heavy-Section Steel Irradiation Program is to provide a thorough, quantitative assessment of the effects of neutron irradiation on the material behavior (particularly the fracture toughness properties) of typical pressure-vessel steels as they relate to light-water-reactor pressure-vessel integrity. The program includes direct continuation of irradiation studies previously conducted by the Heavy-Section Steel Technology Program augmented by enhanced examinations of the accompanying microstructural changes. Effects of specimen size; material chemistry; product form and microstructure; irradiation fluence, flux, temperature, and spectrum; and postirradiation annealing are examined on a wide range of fracture properties. Detailed statistical analyses of the fracture data on K Ic shift of high-copper welds were performed. Analysis of the first phase of irradiated crack-arrest testing on high-copper welds was completed. Final analysis and publication of the results of the second phase of the irradiation studies on stainless steel weld-overlay cladding were completed. Determinations were made of the variations in chemistry and unirradiated RT NDT of low upper-shelf weld metal from the Midland reactor. Final analyses were performed on the Charpy impact and tensile data from the Second and Third Irradiation series on low upper-shelf welds, and the report on the series was drafted. A detailed survey of existing data on microstructural models and data bases of irradiation damage was performed, and initial development of a reaction-rate-based model was completed. 40 refs., 7 figs., 4 tabs

Mississippi Curriculum Framework for Veterinary Technology (Program CIP: 51.0808--Veterinarian Asst./Animal Health). 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 veterinary technology program. Presented in the introductory section are a of the program and suggested course sequence. Section I lists baseline competencies, and section II consists of…

Neutron cross-section library for SAND-2 and its service program

International Nuclear Information System (INIS)

Berzonis, M.A.; Bondars, Kh.Ya.; Lapenas, A.A.

1978-01-01

The logical structure of the neutron cross-section library used in the SAND-2 program complex is considered. The organization of the DSIG01 program creating and servicing the neutron cross section library is described. The DSIG 01 program is written on FORTRAN and permits to create the neutron cross section library on the ES computer magnetic discs operating under the control of the ES operating system and to perform certain manipulations therewith

COMPAR, NJOY, GROUPIE, FLANGE-2, ETOG-3, XLACS Multigroup Cross-Sections General Comparison

International Nuclear Information System (INIS)

Anaf, Jaime; Chalhoub, E.S.

1990-01-01

1 - Description of program or function: A system for comparing multigroup cross sections generated by NJOY, GROUPIE, FLANGE-II, ETOG-3 and XLACS. This system comprises the COMPAR program and interface (auxiliary) programs developed for each of the programs under consideration. These are REDCOMP for GROUPIE, FLACOMP for FLANGE-II, ETOCOMP for ETOG-3 and XLACOMP for XLACS. For the NJOY program there is RGENDF, a program developed apart from this system. It is a modular system in which the inclusion of new multigroup cross section generating program requires no more than the development of a new interface module. 2 - Method of solution: Refer to comments in main routine. 3 - Restrictions on the complexity of the problem: Refer to comments in main routine

A Guide to Program Planning Vol. II.

Science.gov (United States)

Allen, Earl, Sr.

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

40 CFR 72.73 - State issuance of Phase II permits.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 16 2010-07-01 2010-07-01 false State issuance of Phase II permits. 72.73 Section 72.73 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) PERMITS REGULATION Acid Rain Phase II Implementation § 72.73 State issuance of Phase II permits...

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

International Nuclear Information System (INIS)

1978-01-01

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

DOG -II input generator program for DOT3.5 code

International Nuclear Information System (INIS)

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

1992-01-01

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

Full-Scale Mark II CRT Program data report, 1

International Nuclear Information System (INIS)

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

1979-12-01

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

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

International Nuclear Information System (INIS)

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

1980-03-01

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

40 CFR 73.20 - Phase II early reduction credits.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 16 2010-07-01 2010-07-01 false Phase II early reduction credits. 73.20 Section 73.20 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) SULFUR DIOXIDE ALLOWANCE SYSTEM Allowance Allocations § 73.20 Phase II early reduction credits...

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

International Nuclear Information System (INIS)

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

1984-01-01

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

Mathematics Programming on the Apple II and IBM PC.

Science.gov (United States)

Myers, Roy E.; Schneider, David I.

1987-01-01

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

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.

Heavy-section steel irradiation program summary

International Nuclear Information System (INIS)

Corwin, W.R.; Nanstad, R.K.; Iskander, S.K.; Haggag, F.M.

1992-01-01

Since a failure of the RPV carries the potential of major contamination release and severe accident, it is imperative to safe reactor operation to understand and be able to accurately predict failure models of the vessel material. For this reason, the Heavy-Section Steel Irradiation (HSSI) Program has been established with its primary goal to provide a thorough, quantitative assessment of the effects of neutron irradiation on the material behavior, and in particular the fracture toughness properties, of typical pressure vessel steels as they relate to light-water RPVs. The program includes the direct continuation of irradiation studies previously conducted within the Heavy-Section Steel Technology Program augmented by enhanced examinations of the accompanying microstructural changes. Effects of specimen size, material chemistry, product form and microstructure, irradiation fluence, flux, temperature and spectrum, and postirradiation annealing are being examined on a wide range of fracture properties including fracture toughness (K Ic and J Ic ), crack-arrest toughness (K Ia ), ductile tearing resistance (dJ/da), Charpy V-notch impact energy, dropweight nil-ductility temperature (NDT), and tensile properties. Models based on observations of radiation-induced microstructural changes using field ion and high-resolution transmission electron microscopy provide a firmer basis for extrapolating the measured changes in fracture properties to wider ranges of irradiation conditions. The principal materials examined within the HSSI Program are highcopper welds since their postirradiation properties are most frequently limiting in the continued safe operation of commercial RPVs. In addition, a limited effort will focus on stainless steel weld overlay cladding, typical of that used on the inner surface of RPVs, since its postirradiation fracture properties have the potential for strongly affecting the extension of small surface flaws during overcooling transients. (orig./GL)

Heavy-Section Steel Irradiation Program

Energy Technology Data Exchange (ETDEWEB)

Rosseel, T.M.

2000-04-01

Maintaining the integrity of the reactor pressure vessel (RPV) in a light-water-cooled nuclear power plant is crucial in preventing and controlling severe accidents that have the potential for major contamination release. Because the RPV is the only key safety-related component of the plant for which a redundant backup system does not exist, it is imperative to fully understand the degree of irradiation-induced degradation of the RPV's fracture resistance that occurs during service. For this reason, the Heavy-Section Steel Irradiation (HSSI) Program has been established.

Heavy-Section Steel Irradiation Program

International Nuclear Information System (INIS)

Rosseel, T.M.

2000-01-01

Maintaining the integrity of the reactor pressure vessel (RPV) in a light-water-cooled nuclear power plant is crucial in preventing and controlling severe accidents that have the potential for major contamination release. Because the RPV is the only key safety-related component of the plant for which a redundant backup system does not exist, it is imperative to fully understand the degree of irradiation-induced degradation of the RPV's fracture resistance that occurs during service. For this reason, the Heavy-Section Steel Irradiation (HSSI) Program has been established

Equipment qualification research program: program plan

International Nuclear Information System (INIS)

Dong, R.G.; Smith, P.D.

1982-01-01

The Lawrence Livermore National Laboratory (LLNL) under the sponsorship of the US Nuclear Regulatory Commission (NRC) has developed this program plan for research in equipment qualification (EQA). In this report the research program which will be executed in accordance with this plan will be referred to as the Equipment Qualification Research Program (EQRP). Covered are electrical and mechanical equipment under the conditions described in the OBJECTIVE section of this report. The EQRP has two phases; Phase I is primarily to produce early results and to develop information for Phase II. Phase I will last 18 months and consists of six projects. The first project is program management. The second project is responsible for in-depth evaluation and review of EQ issues and EQ processes. The third project is responsible for detailed planning to initiate Phase II. The remaining three projects address specific equipment; i.e., valves, electrical equipment, and a pump

Proceedings of the first analysis meeting on JUPITER-II Program

Energy Technology Data Exchange (ETDEWEB)

Shiradata, Keisho; Yamamoto, Masaaki [comps.

1984-12-31

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

Proceedings of the first analysis meeting on JUPITER-II Program

Energy Technology Data Exchange (ETDEWEB)

Shiradata, Keisho; Yamamoto, Masaaki [comps.

1985-12-31

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

Learn About the Water Pollution Control (Section 106) Grant Program

Science.gov (United States)

Under CWA Section 106, EPA is authorized to provide grants to states, eligible interstate agencies, and eligible tribes to establish and administer programs, including enforcement programs,for the prevention, reduction, and elimination of water pollution.

Seismic safety margin research program. Program plan, Revision II

International Nuclear Information System (INIS)

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

1978-01-01

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

Requirements and Guidelines for Dental Hygiene Education Programs.

Science.gov (United States)

American Dental Association, Chicago, IL. Council on Dental Education.

The purpose of this report is to serve as a guide for dental hygiene education program development, and to serve as a stimulus for improving established programs. The first section of the report discusses the function of the Council on Dental Education and the trends in hygiene program development. In section II the requirements for an accredited…

20 CFR 627.450 - Program income.

Science.gov (United States)

2010-04-01

... 20 Employees' Benefits 3 2010-04-01 2010-04-01 false Program income. 627.450 Section 627.450... PROGRAMS UNDER TITLES I, II, AND III OF THE ACT Administrative Standards § 627.450 Program income. (a) Definition of program income. (1) Program income means income received by the recipient or subrecipient that...

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

Directory of Open Access Journals (Sweden)

Jati Susilo

2015-03-01

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

Measurement of low $p_{T}$ $D^{0}$ meson production cross section at CDF II

Energy Technology Data Exchange (ETDEWEB)

Mussini, Manuel [Univ. of Bologna (Italy)

2011-05-01

In this thesis we present a study of the production of D⁰ meson in the low transverse momentum region. In particular the inclusive differential production cross section of the D⁰ meson (in the two-body decay channel D⁰ → K^-π⁺) is obtained extending the published CDF II measurement to p_T as low as 1.5 GeV/c. This study is performed at the Tevatron Collider at Fermilab with the CDF II detector.

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

International Nuclear Information System (INIS)

Chen, K.

2010-01-01

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

MXS cross-section preprocessor user's manual

International Nuclear Information System (INIS)

Parker, F.; Ishikawa, M.; Luck, L.

1987-03-01

The MXS preprocessor has been designed to reduce the execution time of programs using isotopic cross-section data and to both reduce the execution time and improve the accuracy of shielding-factor interpolation in the SIMMER-II accident analysis program. MXS is a dual-purpose preprocessing code to: (1) mix isotopes into materials and (2) fit analytic functions to the shelf-shielding data. The program uses the isotope microscopic neutron cross-section data from the CCCC standard interface file ISOTXS and the isotope Bondarenko self-shielding data from the CCCC standard interface file BRKOXS to generate cross-section and self-shielding data for materials. The materials may be a mixture of several isotopes. The self-shielding data for the materials may be the actual shielding factors or a set of coefficients for functions representing the background dependence of the shielding factors. A set of additional data is given to describe the functions necessary to interpolate the shielding factors over temperature

40 CFR 35.501 - Environmental programs covered by the subpart.

Science.gov (United States)

2010-07-01

... Stat. 2461, 2499; 42 U.S.C. 6908a). (i) Hazardous Waste Management Program Grants (Pub. L. 105-276; 112... management (section 319(h)). (5) Federal Insecticide, Fungicide, and Rodenticide Act. (i) Pesticide... Substances Control Act. (i) Lead-based paint program (section 404(g)). (ii) Indoor radon grants (section 306...

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

Energy Technology Data Exchange (ETDEWEB)

1979-09-01

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

20 CFR 628.540 - Volunteer program.

Science.gov (United States)

2010-04-01

... programs under this part to volunteer assistance, in the form of mentoring, tutoring, and other activities. ... 20 Employees' Benefits 3 2010-04-01 2010-04-01 false Volunteer program. 628.540 Section 628.540 Employees' Benefits EMPLOYMENT AND TRAINING ADMINISTRATION, DEPARTMENT OF LABOR PROGRAMS UNDER TITLE II OF...

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

Directory of Open Access Journals (Sweden)

Kristine Lykens

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

Do DSM-5 Section II personality disorders and Section III personality trait domains reflect the same genetic and environmental risk factors?

Science.gov (United States)

Reichborn-Kjennerud, T; Krueger, R F; Ystrom, E; Torvik, F A; Rosenström, T H; Aggen, S H; South, S C; Neale, M C; Knudsen, G P; Kendler, K S; Czajkowski, N O

2017-09-01

DSM-5 includes two conceptualizations of personality disorders (PDs). The classification in Section II is identical to the one found in DSM-IV, and includes 10 categorical PDs. The Alternative Model (Section III) includes criteria for dimensional measures of maladaptive personality traits organized into five domains. The degree to which the two conceptualizations reflect the same etiological factors is not known. We use data from a large population-based sample of adult twins from the Norwegian Institute of Public Health Twin Panel on interview-based DSM-IV PDs and a short self-report inventory that indexes the five domains of the DSM-5 Alternative Model plus a domain explicitly targeting compulsivity. Schizotypal, Paranoid, Antisocial, Borderline, Avoidant, and Obsessive-compulsive PDs were assessed at the same time as the maladaptive personality traits and 10 years previously. Schizoid, Histrionic, Narcissistic, and Dependent PDs were only assessed at the first interview. Biometric models were used to estimate overlap in genetic and environmental risk factors. When measured concurrently, there was 100% genetic overlap between the maladaptive trait domains and Paranoid, Schizotypal, Antisocial, Borderline, and Avoidant PDs. For OCPD, 43% of the genetic variance was shared with the domains. Genetic correlations between the individual domains and PDs ranged from +0.21 to +0.91. The pathological personality trait domains, which are part of the Alternative Model for classification of PDs in DSM-5 Section III, appears to tap, at an aggregate level, the same genetic risk factors as the DSM-5 Section II classification for most of the PDs.

WheelerLab: An interactive program for sequence stratigraphic analysis of seismic sections, outcrops and well sections and the generation of chronostratigraphic sections and dynamic chronostratigraphic sections

Science.gov (United States)

Amosu, Adewale; Sun, Yuefeng

WheelerLab is an interactive program that facilitates the interpretation of stratigraphic data (seismic sections, outcrop data and well sections) within a sequence stratigraphic framework and the subsequent transformation of the data into the chronostratigraphic domain. The transformation enables the identification of significant geological features, particularly erosional and non-depositional features that are not obvious in the original seismic domain. Although there are some software products that contain interactive environments for carrying out chronostratigraphic analysis, none of them are open-source codes. In addition to being open source, WheelerLab adds two important functionalities not present in currently available software: (1) WheelerLab generates a dynamic chronostratigraphic section and (2) WheelerLab enables chronostratigraphic analysis of older seismic data sets that exist only as images and not in the standard seismic file formats; it can also be used for the chronostratigraphic analysis of outcrop images and interpreted well sections. The dynamic chronostratigraphic section sequentially depicts the evolution of the chronostratigraphic chronosomes concurrently with the evolution of identified genetic stratal packages. This facilitates a better communication of the sequence-stratigraphic process. WheelerLab is designed to give the user both interactive and interpretational control over the transformation; this is most useful when determining the correct stratigraphic order for laterally separated genetic stratal packages. The program can also be used to generate synthetic sequence stratigraphic sections for chronostratigraphic analysis.

WheelerLab: An interactive program for sequence stratigraphic analysis of seismic sections, outcrops and well sections and the generation of chronostratigraphic sections and dynamic chronostratigraphic sections

Directory of Open Access Journals (Sweden)

Adewale Amosu

2017-01-01

Full Text Available WheelerLab is an interactive program that facilitates the interpretation of stratigraphic data (seismic sections, outcrop data and well sections within a sequence stratigraphic framework and the subsequent transformation of the data into the chronostratigraphic domain. The transformation enables the identification of significant geological features, particularly erosional and non-depositional features that are not obvious in the original seismic domain. Although there are some software products that contain interactive environments for carrying out chronostratigraphic analysis, none of them are open-source codes. In addition to being open source, WheelerLab adds two important functionalities not present in currently available software: (1 WheelerLab generates a dynamic chronostratigraphic section and (2 WheelerLab enables chronostratigraphic analysis of older seismic data sets that exist only as images and not in the standard seismic file formats; it can also be used for the chronostratigraphic analysis of outcrop images and interpreted well sections. The dynamic chronostratigraphic section sequentially depicts the evolution of the chronostratigraphic chronosomes concurrently with the evolution of identified genetic stratal packages. This facilitates a better communication of the sequence-stratigraphic process. WheelerLab is designed to give the user both interactive and interpretational control over the transformation; this is most useful when determining the correct stratigraphic order for laterally separated genetic stratal packages. The program can also be used to generate synthetic sequence stratigraphic sections for chronostratigraphic analysis.

Enforcement/certification program for appliance efficiency standards. Task II, report

Energy Technology Data Exchange (ETDEWEB)

1979-09-28

The research and analysis program at Vitro Labs. in support of the appliance certification and enforcement program provides Vitro's recommended approach to appliance certification and enforcement (C/E). The approach established the C/E program framework, general criteria, and procedures for assuring a specified level of energy-efficiency performance for 13 categories of consumer products (furnaces, humidifiers, dehumidifiers, dishwashers, television, clothes washers, freezers, air conditioners, stoves, refrigerators, water heaters). Section 2 summarizes the recommended approach. Section 3 contains detailed evaluations and comparisons for four independent alternative approaches considered (minimal government intevention, strong certification control, strong enforcement audit, and mixed certification/enforcement). The fifth C/E approach (strong remedy/deterrent) involves the remedies available to the government should non-compliance be discovered and could affect the choice among the approaches, but this approach has not been evaluated. Section 4 summarizes the analysis methodology used to select the recommended approach. Additional information is provided in 6 appendices.

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

Science.gov (United States)

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

Comparing the utility of DSM-5 Section II and III antisocial personality disorder diagnostic approaches for capturing psychopathic traits.

Science.gov (United States)

Few, Lauren R; Lynam, Donald R; Maples, Jessica L; MacKillop, James; Miller, Joshua D

2015-01-01

The current study compares the 2 diagnostic approaches (Section II vs. Section III) included in the Diagnostic and Statistical Manual for Mental Disorders-5 (DSM-5; American Psychiatric Association, 2013) for diagnosis of antisocial personality disorder (ASPD) in terms of their relations with psychopathic traits and externalizing behaviors (EBs). The Section III approach to ASPD, which is more explicitly trait-based than the Section II approach, also includes a psychopathy specifier (PS) that was created with the goal of making the diagnosis of ASPD more congruent with psychopathy. In a community sample of individuals currently receiving mental health treatment (N = 106), ratings of the 2 DSM-5 diagnostic approaches were compared in relation to measures of psychopathy, as well as indices of EBs. Both DSM-5 ASPD approaches were significantly related to the psychopathy scores, although the Section III approach accounted for almost twice the amount of variance when compared with the Section II approach. Relatively little of this predictive advantage, however, was due to the PS, as these traits manifested little evidence of incremental validity in relation to existing psychopathy measures and EBs, with the exception of a measure of fearless dominance. Overall, the DSM-5 Section III diagnostic approach for ASPD is more convergent with the construct of psychopathy, from which ASPD was originally derived. These improvements, however, are due primarily to the new trait-based focus in the Section III ASPD diagnosis rather than the assessment of personality dysfunction or the inclusion of additional "psychopathy-specific" traits. (PsycINFO Database Record (c) 2015 APA, all rights reserved).

Implementasi Program Pembinaan Napi di Lapas Kelas II B Metro

Directory of Open Access Journals (Sweden)

Narsidi Narsidi

2004-01-01

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

NSF-RANN Trace Contaminants Program directory

International Nuclear Information System (INIS)

Purnell, P.A.; Smith, S.K.; Wilkes, C.F.

1976-10-01

This directory is designed to aid effective communication throughout the National Science Foundation's Trace Contaminants Program, Research Applied to National Needs. The majority of the participants in the Program are represented by name, address, telephone number, and a very brief description of research interest. The directory has five major divisions to facilitate its use. Section I contains a listing of the program managers associated with the NSF-RANN Trace Contaminants Program. Section II lists the principal investigators, co-principal investigators, and coordinators of each of the research grants in the Program. Section III lists the personnel by individual projects. Section IV contains a total alphabetic listing complete with project titles and Section V contains a keyword index. This directory is maintained by the Toxic Materials Information Center as part of the Environmental Resource Center of the Information Center Complex, Information Division, Oak Ridge National Laboratory

WheelerLab: An interactive program for sequence stratigraphic analysis of seismic sections, outcrops and well sections and the generation of chronostratigraphic sections and dynamic chronostratigraphic sections

OpenAIRE

Adewale Amosu; Yuefeng Sun

2017-01-01

WheelerLab is an interactive program that facilitates the interpretation of stratigraphic data (seismic sections, outcrop data and well sections) within a sequence stratigraphic framework and the subsequent transformation of the data into the chronostratigraphic domain. The transformation enables the identification of significant geological features, particularly erosional and non-depositional features that are not obvious in the original seismic domain. Although there are some software produ...

Heavy-section steel technology program. Semiannual progress report, October 1994--March 1995

International Nuclear Information System (INIS)

Pennell, W.E.

1996-07-01

The Heavy-Section Steel Technology (HSST) Program is conducted for the Nuclear Regulatory Commission (NRC) by Oak Ridge National Laboratory (ORNL). The program focus is on the development and validation of technology for the assessment of fracture-prevention margins in commercial nuclear reactor pressure vessels. The HSST Program is organized in seven tasks: (1) program management (2) constraint effects analytical development and validation, (3) evaluation of cladding effects, (4) ductile-to-cleavage fracture-mode conversion, (5) fracture analysis methods development and applications, (6) material property data and test methods, and (7) integration of results. The program tasks have been structured to place emphasis on the resolution of fracture issues with near-term licensing significance. Resources to execute the research tasks are drawn from ORNL with subcontract support from universities and other research laboratories. Close contact is maintained with the sister Heavy-Section Steel Irradiation Program at ORNL and with related research programs both in the United States and abroad. This report provides an overview of principal developments in each of the seven program tasks from October 1994-March 1995

Heavy-section steel technology program. Semiannual progress report, October 1994--March 1995

Energy Technology Data Exchange (ETDEWEB)

Pennell, W.E.

1996-07-01

The Heavy-Section Steel Technology (HSST) Program is conducted for the Nuclear Regulatory Commission (NRC) by Oak Ridge National Laboratory (ORNL). The program focus is on the development and validation of technology for the assessment of fracture-prevention margins in commercial nuclear reactor pressure vessels. The HSST Program is organized in seven tasks: (1) program management (2) constraint effects analytical development and validation, (3) evaluation of cladding effects, (4) ductile-to-cleavage fracture-mode conversion, (5) fracture analysis methods development and applications, (6) material property data and test methods, and (7) integration of results. The program tasks have been structured to place emphasis on the resolution of fracture issues with near-term licensing significance. Resources to execute the research tasks are drawn from ORNL with subcontract support from universities and other research laboratories. Close contact is maintained with the sister Heavy-Section Steel Irradiation Program at ORNL and with related research programs both in the United States and abroad. This report provides an overview of principal developments in each of the seven program tasks from October 1994-March 1995.

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

OpenAIRE

Lee, Eun-Ok; Olga, Kozyreva

2013-01-01

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

Steam generator tube integrity program: Phase II, Final report

Energy Technology Data Exchange (ETDEWEB)

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

1988-08-01

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

Steam generator tube integrity program: Phase II, Final report

International Nuclear Information System (INIS)

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

1988-08-01

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

SARP-II: Safeguards Accounting and Reports Program, Revised

International Nuclear Information System (INIS)

Kempf, C.R.

1994-01-01

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

MEKS: A program for computation of inclusive jet cross sections at hadron colliders

Science.gov (United States)

Gao, Jun; Liang, Zhihua; Soper, Davison E.; Lai, Hung-Liang; Nadolsky, Pavel M.; Yuan, C.-P.

2013-06-01

EKS is a numerical program that predicts differential cross sections for production of single-inclusive hadronic jets and jet pairs at next-to-leading order (NLO) accuracy in a perturbative QCD calculation. We describe MEKS 1.0, an upgraded EKS program with increased numerical precision, suitable for comparisons to the latest experimental data from the Large Hadron Collider and Tevatron. The program integrates the regularized patron-level matrix elements over the kinematical phase space for production of two and three partons using the VEGAS algorithm. It stores the generated weighted events in finely binned two-dimensional histograms for fast offline analysis. A user interface allows one to customize computation of inclusive jet observables. Results of a benchmark comparison of the MEKS program and the commonly used FastNLO program are also documented. Program SummaryProgram title: MEKS 1.0 Catalogue identifier: AEOX_v1_0 Program summary URL:http://cpc.cs.qub.ac.uk/summaries/AEOX_v1_0.html Program obtainable from: CPC Program Library, Queen's University, Belfast, N. Ireland. Licensing provisions: Standard CPC licence, http://cpc.cs.qub.ac.uk/licence/licence.html No. of lines in distributed program, including test data, etc.: 9234 No. of bytes in distributed program, including test data, etc.: 51997 Distribution format: tar.gz Programming language: Fortran (main program), C (CUBA library and analysis program). Computer: All. Operating system: Any UNIX-like system. RAM: ˜300 MB Classification: 11.1. External routines: LHAPDF (https://lhapdf.hepforge.org/) Nature of problem: Computation of differential cross sections for inclusive production of single hadronic jets and jet pairs at next-to-leading order accuracy in perturbative quantum chromodynamics. Solution method: Upon subtraction of infrared singularities, the hard-scattering matrix elements are integrated over available phase space using an optimized VEGAS algorithm. Weighted events are generated and filled

Mark II containment program load evaluation and acceptance criteria; Generic Technical Activity A-8

International Nuclear Information System (INIS)

Anderson, C.J.

1981-08-01

The report provides a discussion of LOCA-related suppression pool hydrodynamic loads in boiling water reactor (BWR) facilities with the Mark II pressure-suppression containment design. This report concludes NRC Generic Technical Activity A-8, 'Mark II Containment Pool Dynamic Loads,' which has been designated an 'Unresolved Safety Issue' pursuant to Section 210 of the Energy Reorganization Act of 1974

Impulsivity-related traits and their relation to DSM-5 section II and III personality disorders.

Science.gov (United States)

Few, Lauren R; Lynam, Donald R; Miller, Joshua D

2015-07-01

Difficulties with impulse control are considered a core feature of personality disorders (PDs) as assessed by the Diagnostic and Statistical Manual of Mental Disorders (5th edition [DSM-5]; American Psychiatric Association, 2013). Despite this, there has been relatively little examination of the manner in which DSM-5 PDs are characterized by multidimensional models of impulsivity that parse this broad umbrella construct into smaller, more unidimensional constructs. Using the UPPS model and measure of impulsivity (Whiteside & Lynam, 2001), the relations between 4 impulsivity-related traits and interview-rated scores on both DSM-5 Section II and III PDs and PD traits were examined in a community sample of individuals currently receiving psychological or psychiatric care (N = 106). As expected, the UPPS traits manifested correlations with the new Section III trait model that were generally consistent with the assertion that this new DSM-5 trait model reflects a pathological variant of the Five-Factor Model (FFM; e.g., UPPS traits associated with FFM conscientiousness were most strongly related to DSM-5 disinhibition traits). Overall, the UPPS traits accounted best for variance in DSM-5 Section II and III Cluster B PDs, consistent with these PDs being characterized, in part, by emotionally and cognitively based forms of impulsivity. (c) 2015 APA, all rights reserved).

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

International Nuclear Information System (INIS)

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

1982-11-01

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

76 FR 55720 - BB&T Capital Partners Mezzanine Fund II, L.P.; Notice Seeking Exemption Under Section 312 of the...

Science.gov (United States)

2011-09-08

... approval under section 312 of the Act and Section 107.730 (a)(4), Provide Financing to a Small Business to... SMALL BUSINESS ADMINISTRATION [License No. 04/04-0311] BB&T Capital Partners Mezzanine Fund II, L.P.; Notice Seeking Exemption Under Section 312 of the Small Business Investment Act, Conflicts of...

On semidefinite programming relaxations of maximum k-section

NARCIS (Netherlands)

de Klerk, E.; Pasechnik, D.V.; Sotirov, R.; Dobre, C.

2012-01-01

We derive a new semidefinite programming bound for the maximum k -section problem. For k=2 (i.e. for maximum bisection), the new bound is at least as strong as a well-known bound by Poljak and Rendl (SIAM J Optim 5(3):467–487, 1995). For k ≥ 3the new bound dominates a bound of Karisch and Rendl

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

International Nuclear Information System (INIS)

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

1982-01-01

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

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

International Nuclear Information System (INIS)

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

1982-01-01

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

Status update on the NIFFTE high precision fission cross section measurement program

International Nuclear Information System (INIS)

Laptev, Alexander B.; Tovesson, Fredrik; Burgett, Eric; Greife, Uwe; Grimes, Steven; Heffner, Michael D.; Hertel, Nolan E.; Hill, Tony; Isenhower, Donald; Klay, Jennifer L.; Kornilov, Nickolay; Kudo, Ryuho; Loveland, Walter; Massey, Thomas; McGrath, Chris; Pickle, Nathan; Qu, Hai; Sharma, Sarvagya; Snyder, Lucas; Thornton, Tyler; Towell, Rusty S.; Watson, Shon

2010-01-01

The Neutron Induced Fission Fragment Tracking Experiment (NIFFTE) program has been underway for nearly two years. The program's mission is to measure fission cross sections of the primary fissionable and fissile materials ( 235 U, 239 Pu, 238 U) as well as the minor actinides across energies from approximately 50 keV up to 20 MeV with an absolute uncertainty of less than one percent while investigating energy ranges from below an eV to 600 MeV. This basic nuclear physics data is being reinvestigated to support the next generation power plants and a fast burner reactor program. Uncertainties in the fast, resolved and unresolved resonance regions in plutonium and other transuranics are extremely large, dominating safety margins in the next generation nuclear power plants and power plants of today. This basic nuclear data can be used to support all aspects of the nuciear renaissance. The measurement campaign is utilizing a Time Projection Chamber or TPC as the tool to measure these cross sections to these unprecedented levels. Unlike traditional fission cross section measurements using time-of-flight and a multiple fission foil configurations in which fission cross sections in relation to that of 235 U are performed, the TPC project uses time-of-flight and hydrogen as the benchmark cross section. Using the switch to hydrogen, a simple, smooth cross section that can be used which removes the uncertainties associated with the resolved and unresolved resonances in 235 U.

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

Science.gov (United States)

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

40 CFR 76.8 - Early election for Group 1, Phase II boilers.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 16 2010-07-01 2010-07-01 false Early election for Group 1, Phase II boilers. 76.8 Section 76.8 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) ACID RAIN NITROGEN OXIDES EMISSION REDUCTION PROGRAM § 76.8 Early election for Group 1...

EMPIRE-II 2.18, Comprehensive Nuclear Model Code, Nucleons, Ions Induced Cross-Sections

International Nuclear Information System (INIS)

Herman, Michal Wladyslaw; Panini, Gian Carlo

2003-01-01

1 - Description of program or function: EMPIRE-II is a flexible code for calculation of nuclear reactions in the frame of combined optical, Multi-step Direct (TUL), Multi-step Compound (NVWY) and statistical (Hauser-Feshbach) models. Incident particle can be a nucleon or any nucleus(Heavy Ion). Isomer ratios, residue production cross sections and emission spectra for neutrons, protons, alpha-particles, gamma-rays, and one type of Light Ion can be calculated. The energy range starts just above the resonance region for neutron induced reactions and extends up to several hundreds of MeV for the Heavy Ion induced reactions. IAEA1169/06: This version corrects an error in the Absoft compile procedure. 2 - Method of solution: For projectiles with A<5 EMPIRE calculates fusion cross section using spherical optical model transmission coefficients. In the case of Heavy Ion induced reactions the fusion cross section can be determined using various approaches including simplified coupled channels method (code CCFUS). Pre-equilibrium emission is treated in terms of quantum-mechanical theories (TUL-MSD and NVWY-MSC). MSC contribution to the gamma emission is taken into account. These calculations are followed by statistical decay with arbitrary number of subsequent particle emissions. Gamma-ray competition is considered in detail for every decaying compound nucleus. Different options for level densities are available including dynamical approach with collective effects taken into account. EMPIRE contains following third party codes converted into subroutines: - SCAT2 by O. Bersillon, - ORION and TRISTAN by H. Lenske and H. Wolter, - CCFUS by C.H. Dasso and S. Landowne, - BARMOM by A. Sierk. 3 - Restrictions on the complexity of the problem: The code can be easily adjusted to the problem by changing dimensions in the dimensions.h file. The actual limits are set by the available memory. In the current formulation up to 4 ejectiles plus gamma are allowed. This limit can be relaxed

PROSID - a program to evaluate SIMMER-II results

International Nuclear Information System (INIS)

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

1990-02-01

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

NSF-RANN Trace Contaminants Program directory. [Personnel directory

Energy Technology Data Exchange (ETDEWEB)

Purnell, P.A.; Smith, S.K.; Wilkes, C.F.

1976-10-01

This directory is designed to aid effective communication throughout the National Science Foundation's Trace Contaminants Program, Research Applied to National Needs. The majority of the participants in the Program are represented by name, address, telephone number, and a very brief description of research interest. The directory has five major divisions to facilitate its use. Section I contains a listing of the program managers associated with the NSF-RANN Trace Contaminants Program. Section II lists the principal investigators, co-principal investigators, and coordinators of each of the research grants in the Program. Section III lists the personnel by individual projects. Section IV contains a total alphabetic listing complete with project titles and Section V contains a keyword index. This directory is maintained by the Toxic Materials Information Center as part of the Environmental Resource Center of the Information Center Complex, Information Division, Oak Ridge National Laboratory.

The relative absorption cross-sections of photosystem I and photosystem II in chloroplasts from three types of Nicotiana tabacum.

Science.gov (United States)

Melis, A; Thielen, A P

1980-02-08

In the present study we used three types of Nicotiana tabacum, cv John William's Broad Leaf (the wild type and two mutants, the yellow-green Su/su and the yellow Su/su var. Aurea) in order to correlat functional properties of Photosystem II and Photosystem I with the structural organization of their chloroplasts. The effective absorption cross-section of Photosystem II and Photosystem I centers was measured by means of the rate constant of their photoconversion under light-limiting conditions. In agreement with earlier results (Okabe, K., Schmid, G.H. and Straub, J. (1977) Plant Physiol. 60, 150--156) the photosynthetic unit size for both System II and System I in the two mutants was considerably smaller as compared to the wild type. We observed biphasic kinetics in the photoconversion of System II in all three types of N. tabacum. However, the photoconversion of System I occurred with monophasic and exponential kinetics. Under our experimental conditions, the effective cross-section of Photosystem I was comparable to that of the fast System II component (alpha centers). The relative amplitude of the slow System II component (beta centers) varied between 30% in the wild type to 70% in the Su/su var. Aurea mutant. The increased fraction of beta centers is correlated with the decreased fraction of appressed photosynthetic membranes in the chloroplasts of the two mutants. As a working hypothesis, it is suggested that beta centers are located on photosynthetic membranes directly exposed to the stroma medium.

Experimental system to measure excitation cross-sections by electron impact. Measurements for ArI and ArII

International Nuclear Information System (INIS)

Blanco, F.; Sanchez, J.A.; Aguilera, J.A.; Campos, J.

1989-01-01

An experimental set-up to measure excitation cross-section of atomic and molecular levels by electron impact based on the optical method is reported. We also present some measurements on the excitation cross-section for ArI 5p'(1/2)0 level, and for simultaneous ionization and excitation of Ar leading to ArII levels belonging to the 3p 4 4p and 3p 4 4d configurations. (Author)

Measurement of the inclusive jet cross section using the midpoint algorithm in Run II at CDF

Energy Technology Data Exchange (ETDEWEB)

Group, Robert Craig [Univ. of Florida, Gainesville, FL (United States)

2006-01-01

A measurement is presented of the inclusive jet cross section using the Midpoint jet clustering algorithm in five different rapidity regions. This is the first analysis which measures the inclusive jet cross section using the Midpoint algorithm in the forward region of the detector. The measurement is based on more than 1 fb^-1 of integrated luminosity of Run II data taken by the CDF experiment at the Fermi National Accelerator Laboratory. The results are consistent with the predictions of perturbative quantum chromodynamics.

The vacuum system for the PEP II high energy ring straight sections

International Nuclear Information System (INIS)

Wienands, U.; Daly, E.; Heifets, S.A.; Kulikov, A.; Kurita, N.; Nordby, M.; Perkins, C.; Reuter, E.; Seeman, J.T.; Belser, F.C.; Berg, J.; Holdener, F.R.; Kerns, J.A.; McDaniel, M.R.; Stoeffl, W.

1995-01-01

The six straight sections of the PEP II High Energy Ring (HER) serve various functions: lattice tuning, beam injection and abort, providing space for rf cavities, longitudinal and transverse feedback, beam diagnostics and the interaction point. A stainless steel vacuum system has been designed; prototypes are currently being built. Cooling is required due to radiation coming from the last arc dipole and resistive losses in the vacuum chamber. Although the nominal beam current of the HER is 1 A the vacuum system is designed for 3 A to provide margin and an upgrade path. 5 refs., 7 figs

78 FR 25291 - Announcement of Funding Awards; Section 3 Program Coordination and Implementation; Fiscal Year 2010

Science.gov (United States)

2013-04-30

... funding under the Notice of Funding Availability (NOFA) for the Section 3 Program Coordination and.... (The Catalog of Federal Domestic Assistance Number for currently funded Initiatives under the Section 3... Valentine Reid, 816-777-2390. 7 50,000.00 East Armour Boulevard, Jackson, MO 64112-1254. Section 3 Program...

CREST : a computer program for the calculation of composition dependent self-shielded cross-sections

International Nuclear Information System (INIS)

Kapil, S.K.

1977-01-01

A computer program CREST for the calculation of the composition and temperature dependent self-shielded cross-sections using the shielding factor approach has been described. The code includes the editing and formation of the data library, calculation of the effective shielding factors and cross-sections, a fundamental mode calculation to generate the neutron spectrum for the system which is further used to calculate the effective elastic removal cross-sections. Studies to explore the sensitivity of reactor parameters to changes in group cross-sections can also be carried out by using the facility available in the code to temporarily change the desired constants. The final self-shielded and transport corrected group cross-sections can be dumped on cards or magnetic tape in a suitable form for their direct use in a transport or diffusion theory code for detailed reactor calculations. The program is written in FORTRAN and can be accommodated in a computer with 32 K work memory. The input preparation details, sample problem and the listing of the program are given. (author)

TRUPACT-II container maintenance program plan

International Nuclear Information System (INIS)

1990-11-01

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

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

Science.gov (United States)

2010-07-01

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

Liquefied gaseous fuels safety and environmental control assessment program: third status report

Energy Technology Data Exchange (ETDEWEB)

1982-03-01

This Status Report contains contributions from all contractors currently participating in the DOE Liquefied Gaseous Fuels (LG) Safety and Environmental Control Assessment Program and is presented in two principal sections. Section I is an Executive Summary of work done by all program participants. Section II is a presentation of fourteen individual reports (A through N) on specific LGF Program activities. The emphasis of Section II is on research conducted by Lawrence Livermore National Laboratory (Reports A through M). Report N, an annotated bibliography of literature related to LNG safety and environmental control, was prepared by Pacific Northwest Laboratory (PNL) as part of its LGF Safety Studies Project. Other organizations who contributed to this Status Report are Aerojet Energy Conversion Company; Applied Technology Corporation; Arthur D. Little, Incorporated; C/sub v/ International, Incorporated; Institute of Gas Technology; and Massachusetts Institute of Technology. Separate abstracts have been prepared for Reports A through N for inclusion in the Energy Data Base.

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

International Nuclear Information System (INIS)

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

1980-03-01

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

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-09-01

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

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

National Research Council Canada - National Science Library

Bolkcom, Christopher; Murch, Anthony

2008-01-01

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

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

National Research Council Canada - National Science Library

Murch, Anthony; Bolkcom, Christopher

2007-01-01

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

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

National Research Council Canada - National Science Library

Bolkcom, Christopher

2009-01-01

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

TRUPACT-II Container Maintenance Program Plan

International Nuclear Information System (INIS)

1991-05-01

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

The NLM evaluation lecture series: introduction to the special section on evaluating health communication programs.

Science.gov (United States)

Logan, Robert A; Kreps, Gary L

2014-12-01

This article introduces the Journal of Health Communication's special section, Evaluating Health Communication Programs. This special section is based on a public lecture series supported by the National Library of Medicine titled "Better Health: Evaluating Health Communication Programs" designed to share best practices for using evaluation research to develop, implement, refine, and institutionalize the best health communication programs for promoting public health. This introduction provides an overview to the series, summarizes the major presentations in the series, and describe implications from the series for translational health communication research, interventions, and programs that can enhance health outcomes.

Cross-section crushing behaviour of hat-sections (Part II: Analytical modelling)

NARCIS (Netherlands)

Hofmeyer, H.

2005-01-01

Hat-sections are often used to experimentally investigate building sheeting subject to a concentrated load and bending. In car doors, hat-sections are used for side-impact protection. Their crushing behaviour can partly be explained by only observing their cross-sectional behaviour [1]. This

Class II obese and healthy pregnant controls exhibit indistinguishable pro‐ and anti‐inflammatory immune responses to Caesarian section

Science.gov (United States)

Graham, Caroline; Thorleifson, Mullein; Stefura, William P.; Funk, Duane J.

2017-01-01

Abstract Introduction Obesity during pregnancy is associated with meta‐inflammation and an increased likelihood of clinical complications. Surgery results in intense, acute inflammatory responses in any individual. Because obese individuals exhibit constitutive inflammatory responses and high rates of Caesarian section, it is important to understand the impact of surgery in such populations. Whether more pronounced pro‐inflammatory cytokine responses and/or counterbalancing changes in anti‐inflammatory immune modulators occurs is unknown. Here we investigated innate immune capacity in vivo and in vitro in non‐obese, term‐pregnant controls versus healthy, term‐pregnant obese women (Class II, BMI 35–40). Methods Systemic in vivo induction of eleven pro‐ and anti‐inflammatory biomarkers and acute phase proteins was assessed in plasma immediately prior to and again following Caesarian section surgery. Independently, innate immune capacity was examined by stimulating freshly isolated PBMC in vitro with a panel of defined PRR‐ligands for TLR4, TLR8, TLR3, and RLR 24 h post‐surgery. Results The kinetics and magnitude of the in vivo inflammatory responses examined were indistinguishable in the two populations across the broad range of biomarkers examined, despite the fact that obese women had higher baseline inflammatory status. Deliberate in vitro stimulation with a range of PRR ligands also elicited pro‐ and anti‐inflammatory cytokine responses that were indistinguishable between control and obese mothers. Conclusions Acute in vivo innate immune responses to C‐section, as well as subsequent in vitro stimulation with a panel of microbial mimics, are not detectably altered in Class II obese women. The data argue that while Class II obesity is undesirable, it has minimal impact on the in vivo inflammatory response, or innate immunomodulatory capacity, in women selecting C‐section. PMID:28544689

TEMPEST-2, Thermalization Program for Neutron Spectra and Multigroup Cross-Sections

International Nuclear Information System (INIS)

Gowins, G.

1984-01-01

Description of problem or function: TEMPEST2 is a neutron thermalization program based upon the Wigner-Wilkins approximation for light moderators and the Wilkins approximation for heavy moderators. A Maxwellian distribution may also be used. The model used may be selected as a function of energy. The second-order differential equations are integrated directly rather than transformed to the Riccati equation. The program provides microscopic and macroscopic cross-section averages over the thermal neutron spectrum

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

Energy Technology Data Exchange (ETDEWEB)

None

1978-08-01

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

ZZ SNLRML, Dosimetry Cross-Section Recommendations

International Nuclear Information System (INIS)

1996-01-01

Description of program or function: Format: SAND-II; Number of groups: 640 group SAND-II group structure. Nuclides: Cd, B, Au, S, Ni, Li, F, Na, Mg, Al, Si, P, Sc, Ti, Mn, Fe, Co, Cu, Zn, Zr, Nb, Mo, Rh, Ag, In, I, Th, U, Np, Pu, Am. Origin: ENDF/B-VI, ENDF/B-V, IRDF-90, JENDL-3, JEF 2.2 and GLUCS data with special modifications from private communications. Weighting spectrum: flat. SNLRML is a reactor dosimetry library that draws upon all available evaluated cross section libraries and selects the best evaluation for application to research reactor spectrum determinations. Many of the components of the SNLRML come from the ENDF/B-VI and IRDF-90 (DLC-0161) libraries. The library format was selected for easy interface with spectrum determination codes such as SAND-II (CCC-0112 and LSL-M2 (PSR-233) and the new PSR-0345/SNL/SAND-II has been enhanced to interface with SNLRML. The data is recommended for spectrum determination applications and for the prediction of neutron activation of typical radiation sensor materials. The library has been tested for consistency of the cross section in wide variety of neutron environments. The results and cautions from this testing have been documented. The data has been interfaced with radiation transport codes, such as TWODANT-SYS (CCC-0547) and MCNP (CCC-0200), in order to compare calculated and measured activities for benchmark reactor experiments

Effects of a Paternal Participation Program during Cesarean Section on Paternal Infant Attachment

Directory of Open Access Journals (Sweden)

Hyun Kyoung Kim

2013-06-01

Full Text Available PurposeIn this study effects of a paternal participation program during cesarean section on paternal infant attachment were investigate. The experimental treatment was an integrative nursing intervention to promote father to infant attachment.MethodsStudy design was a non-equivalent control group posttest design. The program consisted of emotional support to spouse and father towards infant attachment immediately following cesarean birth. Participants were 66 men, partners of women with normal full term pregnancy having a cesarean section with spinal or epidural anesthesia, (experimental group, 34; control group, 32. The experiment was carried out from August 1 to October 30, 2010. Control group data were obtained from May 1 to June 30, 2012. Posttest was performed 72 hours after cesarean birth. A self-report questionnaire including a paternal attachment instrument was used. Data were analyzed using t-test, propensity score matching, and analysis of covariance with the SPSS/WIN 18.0 program.ResultsTotal score for paternal infant attachment in the experimental group was significantly higher than the control group (p<.001. After matching, significant differences were found between the two groups through all subcategories. Adjusted mean score for paternal infant attachment verified experimental effects.ConclusionResults indicate that this paternal participation program during cesarean section is effective in improving paternal infant attachment.

78 FR 53423 - Section 538 Guaranteed Rural Rental Housing Program for Fiscal Year 2013

Science.gov (United States)

2013-08-29

... 3560.406) of existing direct Section 515 and Section 514/516 Farm Labor Housing (FLH) (transfer costs... is taken to extend the eligible properties to include Rural Development financed Farm Labor Housing...) program. Equity payment, as stipulated in 7 CFR 3560.406, in the transfer of existing direct Section 515...

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

Science.gov (United States)

Huber, C

1985-03-01

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

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

DEFF Research Database (Denmark)

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

2010-01-01

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

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

International Nuclear Information System (INIS)

Johnson, C.K.

1976-03-01

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

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

Energy Technology Data Exchange (ETDEWEB)

Johnson, C.K.

1976-03-01

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

Application Programming in AWIPS II

Science.gov (United States)

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

2012-01-01

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

Heavy-Section Steel Technology Program Semiannual progress report, April--September 1993. Volume 10, No. 2

Energy Technology Data Exchange (ETDEWEB)

Pennell, W.E. [Oak Ridge National Lab., TN (United States)

1995-05-01

The Heavy-Section Steel Technology (HSST) Program is conducted for the Nuclear Regulatory Commission by Oak Ridge National Laboratory (ORNL). The program focuses on the development and validation of technology for the assessment of fracture-prevention margins in commercial nuclear reactor pressure vessels. The HSST Program is organized in 12 tasks: Program management, fracture methodology and analysis, material characterizations and properties, special technical assistance, fracture analysis computer programs, cleavage-crack initiation, cladding evaluations, pressurized-thermal-shock technology, analysis methods validation, fracture evaluation tests, warm prestressing, and biaxial loading effects on fracture toughness. The program tasks have been structured to emphasize the resolution fracture issues with near-term licensing significance. Resources to execute the research tasks are drawn from ORNL with subcontract support from universities and other research laboratories. Close contact is maintained with the sister Heavy-Section Steel Irradiation Program at ORNL and with related research programs both in the United States and abroad. This report provide s an overview of principal developments in each of the 12 program tasks from April -- September 1993.

Heavy-Section Steel Technology Program Semiannual progress report, April--September 1993. Volume 10, No. 2

International Nuclear Information System (INIS)

Pennell, W.E.

1995-05-01

The Heavy-Section Steel Technology (HSST) Program is conducted for the Nuclear Regulatory Commission by Oak Ridge National Laboratory (ORNL). The program focuses on the development and validation of technology for the assessment of fracture-prevention margins in commercial nuclear reactor pressure vessels. The HSST Program is organized in 12 tasks: Program management, fracture methodology and analysis, material characterizations and properties, special technical assistance, fracture analysis computer programs, cleavage-crack initiation, cladding evaluations, pressurized-thermal-shock technology, analysis methods validation, fracture evaluation tests, warm prestressing, and biaxial loading effects on fracture toughness. The program tasks have been structured to emphasize the resolution fracture issues with near-term licensing significance. Resources to execute the research tasks are drawn from ORNL with subcontract support from universities and other research laboratories. Close contact is maintained with the sister Heavy-Section Steel Irradiation Program at ORNL and with related research programs both in the United States and abroad. This report provide s an overview of principal developments in each of the 12 program tasks from April -- September 1993

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

International Nuclear Information System (INIS)

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

1966-03-01

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

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

Energy Technology Data Exchange (ETDEWEB)

Grau Carles, A.; Grau Malonda, A.

1985-07-01

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

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

International Nuclear Information System (INIS)

Grau Carles, A.; Grau Malonda, A.

1985-01-01

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

75 FR 32182 - Medicaid Program: Proposed Implementation of Section 614 of the Children's Health Insurance...

Science.gov (United States)

2010-06-07

... of the Children's Health Insurance Program Reauthorization Act of 2009 for Adjustments to the Federal... subject to adjustment pursuant to section 614 of the Children's Health Insurance Program Reauthorization... assistance expenditures under the Children's Health Insurance Program under title XXI of the Social Security...

Heavy-section steel technology program. Semiannual progress report, April--September 1995 Vol. 12, No. 2

Energy Technology Data Exchange (ETDEWEB)

Pennell, W.E.

1997-01-01

The Heavy-Section Steel Technology (HSST) Program is conducted for the Nuclear Regulatory Commission by Oak Ridge National Laboratory (ORNL). The program focus is on the development and validation of technology for the assessment of fracture-prevention margins in commercial nuclear reactor pressure vessels. The HSST Program is organized in seven tasks: (1) program management, (2) constraint effects analytical development and validation, (3) evaluation of cladding effects, (4) ductile-to-cleavage fracture-mode conversion, (5) fracture analysis methods development and applications, (6) material property data and test methods, and (7) integration of results. The program tasks have been structured to place emphasis on the resolution of fracture issues with near-term licensing significance. Resources to execute the research tasks are drawn from ORNL with subcontract support from universities and other research laboratories. Close contact is maintained with the sister Heavy-Section Steel Irradiation Program at ORNL and with related research programs both in the United States and abroad. This report provides an overview of principal developments in each of the seven program tasks from April 1995 to September 1995.

Chemical speciation of Pb(II, Cd(II, Hg(II, Co(II, Ni(II, Cu(II and Zn(II binary complexes of l-methionine in 1,2-propanediol-water mixtures

Directory of Open Access Journals (Sweden)

M. Padma Latha

2007-04-01

Full Text Available Chemical speciation of Pb(II, Cd(II, Hg(II, Co(II, Ni(II, Cu(II and Zn(II complexes of L-methionine in 0.0-60 % v/v 1,2-propanediol-water mixtures maintaining an ionic strength of 0.16 M at 303 K has been studied pH metrically. The active forms of ligand are LH2+, LH and L-. The predominant species detected are ML, MLH, ML2, ML2H, ML2H2 and MLOH. Models containing different numbers of species were refined by using the computer program MINIQUAD 75. The best-fit chemical models were arrived at based on statistical parameters. The trend in variation of complex stability constants with change in the dielectric constant of the medium is explained on the basis of electrostatic and non-electrostatic forces.

Slender body theory programmed for bodies with arbitrary cross section. [including fuselages

Science.gov (United States)

Werner, J.; Krenkel, A. R.

1978-01-01

A computer program developed for determining the subsonic pressure, force, and moment coefficients for a fuselage-type body using slender body theory is described. The program is suitable for determining the angle of attack and sideslipping characteristics of such bodies in the linear range where viscous effects are not predominant. Procedures developed which are capable of treating cross sections with corners or regions of large curvature are outlined.

78 FR 79310 - Partial Section Eight Management Assessment Program (SEMAP) Indicator Waiver; Family Self...

Science.gov (United States)

2013-12-30

... Section Eight Management Assessment Program (SEMAP) Indicator Waiver; Family Self-Sufficiency (FSS... rating criteria at 24 CFR 985.3(o) (``Family self-sufficiency (FSS) enrollment and escrow accounts... Family Self-Sufficiency (FSS) Program Demonstration is a random assignment study conducted under contract...

Heavy-section steel irradiation program. Progress report, October 1992--March 1993

International Nuclear Information System (INIS)

Corwin, W.R.

1998-04-01

Maintaining the integrity of the reactor pressure vessel (RPV) in a light-water-cooled nuclear power plant is crucial in preventing and controlling severe accidents that have the potential for major contamination release. The RPV is one of only two more safety-related components of the plant for which a duplicate or redundant backup system does not exist. It is therefore imperative to understand and be able to predict the capabilities and limitations of the integrity inherent in the RPV. In particular, it is vital to fully understand the degree of irradiation-induced degradation of the RPV's fracture resistance that occurs during service. For this reason, the Heavy-Section Steel Irradiation (HSSI) Program has been established at Oak Ridge National Laboratory (ORNL) under sponsorship of the Nuclear Regulatory Commission (NRC). The primary goal of this major safety program is to provide a thorough, quantitative assessment of the effects of neutron irradiation on the material behavior (in particular, the fracture toughness properties) of typical pressure-vessel steels as they relate to light-water-reactor pressure-vessel integrity. The program centers on experimental assessments of irradiation-induced embrittlement (including the completion of certain irradiation studies previously conducted by the Heavy-Section Steel Technology Program) augmented by detailed examinations and modeling of the accompanying microstructural changes. Effects of specimen size; material chemistry; product form and microstructure; irradiation fluence, flux, temperature, and spectrum; and postirradiation annealing are being examined on a wide range of fracture properties

RTNS-II [Rotating Target Neutron Source II] operational summary

International Nuclear Information System (INIS)

Heikkinen, D.W.

1988-09-01

The Rotating Target Neutron Source II facility (RTNS-II) operated for over nine years. Its purpose was to provide high intensities of 14 MeV neutrons for materials studies in the fusion energy program. For the period from 1982-1987, the facility was supported by both the US (Department of Energy) and Japan (Ministry of Education, Culture, and Science). RTNS-II contains two accelerator-based neutron sources which use the T(d,n) 4 He reaction. In this paper, we will summarize the operational history of RTNS-II. Typical operating parameters are given. In addition, a brief description of the experimental program is presented. The current status and future options for the facility are discussed. 7 refs., 5 tabs

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

Science.gov (United States)

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

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

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

NARCIS (Netherlands)

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

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

Aerial radiometric and magnetic survey; Brushy Basin detail survey: Price/Salina national topographic map sheets, Utah. Volume III. Area II: graphic data, Section I-II. Final report

International Nuclear Information System (INIS)

1981-01-01

This volume contains all of the graphic data for Area II which consists of map lines 1660 to 3400 and 5360 to 5780, and tie lines 6100, 6120, and 6160. Due to the large map scale of the presented data (1:62,500), this sub-section was divided into eleven 7-1/2 min quadrant sheets

KINKFOLD—an AutoLISP program for construction of geological cross-sections using borehole image data

Science.gov (United States)

Özkaya, Sait Ismail

2002-04-01

KINKFOLD is an AutoLISP program designed to construct geological cross-sections from borehole image or dip meter logs. The program uses the kink-fold method for cross-section construction. Beds are folded around hinge lines as angle bisectors so that bedding thickness remains unchanged. KINKFOLD may be used to model a wide variety of parallel fold structures, including overturned and faulted folds, and folds truncated by unconformities. The program accepts data from vertical or inclined boreholes. The KINKFOLD program cannot be used to model fault drag, growth folds, inversion structures or disharmonic folds where the bed thickness changes either because of deformation or deposition. Faulted structures and similar folds can be modelled by KINKFOLD by omitting dip measurements within fault drag zones and near axial planes of similar folds.

RESEND, Infinitely Dilute Point Cross-Sections Calculation from ENDF/B Resonance Parameter. ADLER, ENDF/B Adler-Adler Resonance Parameter to Point Cross-Sections with Doppler Broadening

International Nuclear Information System (INIS)

Bhat, M.R.; Ozer, O.

1982-01-01

1 - Description of problem or function: RESEND generates infinitely- dilute, un-broadened, point cross sections in the ENDF format by combining ENDF File 3 background cross sections with points calculated from ENDF File 2 resonance parameter data. ADLER calculates total, capture, and fission cross sections from the corresponding Adler-Adler parameters in the ENDF/B File 2 Version II data and also Doppler-broadens cross sections. 2 - Method of solution: RESEND calculations are done in two steps by two separate sections of the program. The first section does the resonance calculation and stores the results on a scratch file. The second section combines the data from the scratch file with background cross sections and prints the results. ADLER uses the Adler-Adler formalism. 3 - Restrictions on the complexity of the problem: RESEND expects its input to be a standard mode BCD ENDF file (Version II/III). Since the output is also a standard mode BCD ENDF file, the program is limited by the six significant figure accuracy inherent in the ENDF formats. (If the cross section has been calculated at two points so close in energy that only their least significant figures differ, that interval is assumed to have converged, even if other convergence criteria may not be satisfied.) In the unresolved range the cross sections have been averaged over a Porter-Thomas distribution. In some regions the calculated resonance cross sections may be negative. In such cases the standard convergence criterion would cause an unnecessarily large number of points to be produced in the region where the cross section becomes zero. For this reason an additional input convergence criterion (AVERR) may be used. If the absolute value of the cross section at both ends of an interval is determined to be less than AVERR then the interval is assumed to have converged. There are no limitations on the total number of points generated. The present ENDF (Version II/III) formats restrict the total number of

OSMOSE: An experimental program for the qualification of integral cross sections of actinides

International Nuclear Information System (INIS)

Hudelot, J. P.; Klann, R.; Fougeras, P.; Jorion, F.; Drin, N.; Donnet, L.

2004-01-01

The accurate integral cross sectional reaction rates in representative spectra for the actinides are discussed at OSMOSE program. The first step in obtaining better nuclear data consists of measuring accurate integral data and comparing it to integrated energy dependent data: this comparison provides a direct assessment of the effect of deficiencies in the differential data. The OSMOSE program includes a complete analytical program associated with experimental measurement program and aims at understanding and resolving discrepancies between calculated and measured values. The measurement covers a wide range of neutron spectra, from over-moderate thermal spectra to fast spectra. (authors)

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

International Nuclear Information System (INIS)

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

1992-08-01

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

Development of ANJOYMC Program for Automatic Generation of Monte Carlo Cross Section Libraries

International Nuclear Information System (INIS)

Kim, Kang Seog; Lee, Chung Chan

2007-03-01

The NJOY code developed at Los Alamos National Laboratory is to generate the cross section libraries in ACE format for the Monte Carlo codes such as MCNP and McCARD by processing the evaluated nuclear data in ENDF/B format. It takes long time to prepare all the NJOY input files for hundreds of nuclides with various temperatures, and there can be some errors in the input files. In order to solve these problems, ANJOYMC program has been developed. By using a simple user input deck, this program is not only to generate all the NJOY input files automatically, but also to generate a batch file to perform all the NJOY calculations. The ANJOYMC program is written in Fortran90 and can be executed under the WINDOWS and LINUX operating systems in Personal Computer. Cross section libraries in ACE format can be generated in a short time and without an error by using a simple user input deck

76 FR 17180 - KLH Capital II, L.P.; Notice Seeking Exemption Under Section 312 of the Small Business Investment...

Science.gov (United States)

2011-03-28

... SMALL BUSINESS ADMINISTRATION [License No. 04/04-0296] KLH Capital II, L.P.; Notice Seeking Exemption Under Section 312 of the Small Business Investment Act, Conflicts of Interest Notice is hereby given that KLH Capital, L.P., 101 East Kennedy Boulevard, Suite 3925, Tampa, FL, 33602 a Federal...

Micellar effect on metal-ligand complexes of Co(II, Ni(II, Cu(II and Zn(II with citric acid

Directory of Open Access Journals (Sweden)

Nageswara Rao Gollapalli

2009-12-01

Full Text Available Chemical speciation of citric acid complexes of Co(II, Ni(II, Cu(II and Zn(II was investigated pH-metrically in 0.0-2.5% anionic, cationic and neutral micellar media. The primary alkalimetric data were pruned with SCPHD program. The existence of different binary species was established from modeling studies using the computer program MINIQUAD75. Alkalimetric titrations were carried out in different relative concentrations (M:L:X = 1:2:5, 1:3:5, 1:5:3 of metal (M to citric acid. The selection of best chemical models was based on statistical parameters and residual analysis. The species detected were MLH, ML2, ML2H and ML2H2. The trend in variation of stability constants with change in mole fraction of the medium is explained on the basis of electrostatic and non-electrostatic forces. Distributions of the species with pH at different compositions of micellar media are also presented.

KAPSIES: A program for the calculation of multi-step direct reaction cross sections

International Nuclear Information System (INIS)

Koning, A.J.; Akkermans, J.M.

1994-09-01

We present a program for the calculation of continuum cross sections, sepctra, angular distributions and analyzing powers according to various quantum-mechanical theories for statistical multi-step direct nuclear reactions. (orig.)

Heavy-Section Steel Irradiation Program

International Nuclear Information System (INIS)

Anon.

1991-01-01

In FY1990 the Heavy-Section Steel Irradiation (HSSI) Program was arranged into 8 tasks: (1) program management, (2) K Ic curve shift in high-copper welds, (3) K Ia curve shift in high-copper welds, (4) irradiation effects on cladding, (5) K Ic and K Ia curve shifts in low upper-shelf (LUS) welds, (6) irradiation effects in a commercial LUS weld, (7) microstructural analysis of irradiation effects, and (8) in-service aged material evaluations. Of particular interest are the efforts in FY1990 concerning the shifts in fracture toughness and crack arrest toughness in high-copper welds, the unirradiated examination of a LUS weld from the Midland reactor, and the continued investigation into the causes of accelerated low-temperature embrittlement recently observed in RPV support steels. In the Fifth and Sixth Irradiation Series, designed to examine the shifts and possible changes in shape in the ASME K Ic and K Ia curves for two irradiated high-copper welds, it was seen that both the lower bound and mean fracture toughness shifts were greater than those of the associated Charpy-impact energies, whereas the shifts in crack arrest toughness were comparable. The irradiation-shifted fracture toughness data fell slightly below the appropriately indexed ASME K Ic curve even when it was shifted according to Revision 2 of Regulatory Guide 1.99 including its margins. The beltline weld, which was removed from the Midland reactor, fabricated by Babcock and Wilcox, Co. using Linde 80 flux, is being examined in the Tenth Irradiation Series to establish the effects of irradiation on a commercial LUS weld. A wide variation in the unirradiated fracture properties of the Midland weld were measured with values of RT NDT ranging from -22 to 54F through its thickness. In addition, a wide range of copper content from 0.21 to 0.45 wt % was found, compared to the 0.42 wt % previously reported

Heavy-Section Steel Technology Program: Semiannual progress report for April--September 1994. Volume 11, Number 2

Energy Technology Data Exchange (ETDEWEB)

Pennell, W.E. [Oak Ridge National Lab., TN (United States)

1996-04-01

The Heavy-Section Steel Technology (HSST) Program is conducted for the Nuclear Regulatory Commission (NRC) by Oak Ridge National Laboratory (ORNL). The program focus is on the development and validation of technology for the assessment of fracture-prevention margins in commercial nuclear reactor pressure vessels. The HSST Program is organized in seven tasks: (1) program management, (2) constraint effects analytical development and validation, (3) evaluation of cladding effects, (4) ductile-to-cleavage fracture-mode conversion, (5) fracture analysis methods development and applications, (6) material property data and test methods, and (7) integration of results. The program tasks have been structured to place emphasis on the resolution fracture issues with near-term licensing significance. Resources to execute the research tasks are drawn from ORNL with subcontract support from universities and other research laboratories. Close contact is maintained with the sister Heavy-Section Steel Irradiation (HSSI) Program at ORNL and with related research programs both in the US and abroad. This report provides an overview of principal developments in each of the seven program tasks from April 1994 to September 1994.

Heavy-Section Steel Technology Program: Semiannual progress report for April--September 1994. Volume 11, Number 2

International Nuclear Information System (INIS)

Pennell, W.E.

1996-04-01

The Heavy-Section Steel Technology (HSST) Program is conducted for the Nuclear Regulatory Commission (NRC) by Oak Ridge National Laboratory (ORNL). The program focus is on the development and validation of technology for the assessment of fracture-prevention margins in commercial nuclear reactor pressure vessels. The HSST Program is organized in seven tasks: (1) program management, (2) constraint effects analytical development and validation, (3) evaluation of cladding effects, (4) ductile-to-cleavage fracture-mode conversion, (5) fracture analysis methods development and applications, (6) material property data and test methods, and (7) integration of results. The program tasks have been structured to place emphasis on the resolution fracture issues with near-term licensing significance. Resources to execute the research tasks are drawn from ORNL with subcontract support from universities and other research laboratories. Close contact is maintained with the sister Heavy-Section Steel Irradiation (HSSI) Program at ORNL and with related research programs both in the US and abroad. This report provides an overview of principal developments in each of the seven program tasks from April 1994 to September 1994

Measurement of DSM-5 section II personality disorder constructs using the MMPI-2-RF in clinical and forensic samples.

Science.gov (United States)

Anderson, Jaime L; Sellbom, Martin; Pymont, Carly; Smid, Wineke; De Saeger, Hilde; Kamphuis, Jan H

2015-09-01

In the current study, we evaluated the associations between the Minnesota Multiphasic Personality Inventory-2 Restructured Form (MMPI-2-RF; Ben-Porath & Tellegen, 2008) scale scores and the Diagnostic and Statistical Manual of Mental Disorders (5th ed.; DSM-5; American Psychiatric Association, 2013) Section II personality disorder (PD) criterion counts in inpatient and forensic psychiatric samples from The Netherlands using structured clinical interviews to operationalize PDs. The inpatient psychiatric sample included 190 male and female patients and the forensic sample included 162 male psychiatric patients. We conducted correlation and count regression analyses to evaluate the utility of relevant MMPI-2-RF scales in predicting PD criterion count scores. Generally, results from these analyses emerged as conceptually expected and provided evidence that MMPI-2-RF scales can be useful in assessing PDs. At the zero-order level, most hypothesized associations between Section II disorders and MMPI-2-RF scales were supported. Similarly, in the regression analyses, a unique set of predictors emerged for each PD that was generally in line with conceptual expectations. Additionally, the results provided general evidence that PDs can be captured by dimensional psychopathology constructs, which has implications for both DSM-5 Section III specifically and the personality psychopathology literature more broadly. (c) 2015 APA, all rights reserved.

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

International Nuclear Information System (INIS)

Talbert, D.M.

1981-04-01

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

40 CFR 147.2650 - State-administered program-Class I, II, III, IV, and V wells.

Science.gov (United States)

2010-07-01

... AGENCY (CONTINUED) WATER PROGRAMS (CONTINUED) STATE, TRIBAL, AND EPA-ADMINISTERED UNDERGROUND INJECTION... Underground Injection Control Program for all classes of wells in the Commonwealth of Puerto Rico, other than...), approved by the EPA pursuant to the Safe Drinking Water Act (SDWA) section 1422. This program consists of...

A user`s guide to LUGSAN II. A computer program to calculate and archive lug and sway brace loads for aircraft-carried stores

Energy Technology Data Exchange (ETDEWEB)

Dunn, W.N. [Sandia National Labs., Albuquerque, NM (United States). Mechanical and Thermal Environments Dept.

1998-03-01

LUG and Sway brace ANalysis (LUGSAN) II is an analysis and database computer program that is designed to calculate store lug and sway brace loads for aircraft captive carriage. LUGSAN II combines the rigid body dynamics code, SWAY85, with a Macintosh Hypercard database to function both as an analysis and archival system. This report describes the LUGSAN II application program, which operates on the Macintosh System (Hypercard 2.2 or later) and includes function descriptions, layout examples, and sample sessions. Although this report is primarily a user`s manual, a brief overview of the LUGSAN II computer code is included with suggested resources for programmers.

Program package for calculation of cross sections of neutron scattering on deformed nuclei by the coupled-channel method

International Nuclear Information System (INIS)

Kloss, Yu.Yu.

1985-01-01

Program package and numerical solution of the problem for a system of coupled equations used in optical model to solve a problem on low and mean energy neutron scattering on deformed nuclei, is considered. With these programs differnet scattering cross sections depending on the incident neutron energy on even-even and even-odd nuclei were obtained. The programm permits to obtain different scattering cross sections (elastic, inelastic), excitation cross sections of the first three energy levels of rotational band depending on the energy, angular distributions and neutron polarizations including excited channels. In the program there is possibility for accounting even-even nuclei octupole deformation

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

International Nuclear Information System (INIS)

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

2011-01-01

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

Penalty model for delay of bidding section construction period in South-to-North Water Diversion Eastern Route Project from perspective of programs

Directory of Open Access Journals (Sweden)

Jing-chun Feng

2012-09-01

Full Text Available According to the multi-project and program management theory, this paper analyzes the program generation principle and establishes a program based on progress goals. On the basis of the present situation of calculation of penalty for delay of the bidding section construction period with the critical path method, we studied the effects of contractor-induced delay of the bidding section construction period in detail, including the effects on the construction period of the bidding section itself, the earliest start times of the next bidding section and other subsequent bidding sections, and the construction period of the program, and then constructed a penalty model for delay of the bidding section construction period from the perspective of programs. Using the penalty model, we conducted a practical analysis of penalty for delay of the construction period of the Baoying station program in the South-to-North Water Diversion Project. The model can help determine the amount of penalty for delay of the construction period in bidding sections scientifically and reasonably.

Subseabed disposal program annual report, January-December 1980. Volume II. Appendices (principal investigator progress reports). Part 1

International Nuclear Information System (INIS)

Hinga, K.R.

1981-07-01

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

Subseabed disposal program annual report, January-December 1980. Volume II. Appendices (principal investigator progress reports). Part 1

Energy Technology Data Exchange (ETDEWEB)

Hinga, K.R. (ed.)

1981-07-01

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

Heavy-section steel technology program: Semiannual progress report, October 1993--March 1994. Volume 11, No. 1

Energy Technology Data Exchange (ETDEWEB)

Pennell, W.E. [Oak Ridge National Lab., TN (United States)

1995-11-01

The Heavy-Section Steel Technology (HSST) Program is conducted for the US Nuclear Regulatory Commission (NRC) by Oak Ridge National Laboratory (ORNL). The Program focus is on the development and validation of technology for the assessment Of fracture-prevention margins in commercial nuclear reactor pressure vessels. The HSST Program is organized in seven tasks: (1) program management (2) constraint effects analytical development and validation, (3) evaluation of cladding effects, (4) ductile to cleavage fracture mode conversion, (5) fracture analysis methods development and applications, (6) material Property data and test methods, and (7) integration of results into a state-of-the-art methodology. The program tasks have been structured to place emphasis on the resolution fracture issues with near-term licensing significance. Resources to execute the research tasks are drawn from ORNL with subcontract support from universities and other research laboratories. Close contact is maintained with the sister Heavy-Section Steel Irradiation Program at ORNL and with related research programs both in the United States and abroad. This report provides an overview of principal developments in each of the seven program tasks from October 1993--March 1994.

Heavy-section steel technology program: Semiannual progress report, October 1993--March 1994. Volume 11, No. 1

International Nuclear Information System (INIS)

Pennell, W.E.

1995-11-01

The Heavy-Section Steel Technology (HSST) Program is conducted for the US Nuclear Regulatory Commission (NRC) by Oak Ridge National Laboratory (ORNL). The Program focus is on the development and validation of technology for the assessment Of fracture-prevention margins in commercial nuclear reactor pressure vessels. The HSST Program is organized in seven tasks: (1) program management (2) constraint effects analytical development and validation, (3) evaluation of cladding effects, (4) ductile to cleavage fracture mode conversion, (5) fracture analysis methods development and applications, (6) material Property data and test methods, and (7) integration of results into a state-of-the-art methodology. The program tasks have been structured to place emphasis on the resolution fracture issues with near-term licensing significance. Resources to execute the research tasks are drawn from ORNL with subcontract support from universities and other research laboratories. Close contact is maintained with the sister Heavy-Section Steel Irradiation Program at ORNL and with related research programs both in the United States and abroad. This report provides an overview of principal developments in each of the seven program tasks from October 1993--March 1994

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

Energy Technology Data Exchange (ETDEWEB)

None

1980-04-01

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

Secondary Electron Yield Measurements and Groove Chambers Tests in the PEP-II Beam Line Straights Sections

International Nuclear Information System (INIS)

Pivi, M

2008-01-01

Beam instability caused by the electron cloud has been observed in positron and proton storage rings and it is expected to be a limiting factor in the performance of the positron Damping Ring (DR) of future Linear Colliders such as ILC and CLIC [1, 2]. In the Positron Low Energy Ring (LER) of the PEP-II accelerator, we have installed vacuum chambers with rectangular grooves in a straight magnetic-free section to test this promising possible electron cloud mitigation technique. We have also installed a special chamber to monitor the secondary electron yield of TiN and TiZrV (NEG) coating, Copper, Stainless Steel and Aluminum under the effect of electron and photon conditioning in situ in the beam line. In this paper, we describe the ongoing R and D effort to mitigate the electron cloud effect for the ILC damping ring, the latest results on in situ secondary electron yield conditioning and recent update on the groove tests in PEP-II

Heavy-section steel irradiation program. Progress report, October 1994--March 1995

International Nuclear Information System (INIS)

Corwin, W.R.

1995-10-01

This document is the October 1994-March 1995 Progress Report for the Heavy Section Steel Irradiation Program. The report contains a summary of activities in each of the 14 tasks of the HSSI Program, including: (1) Program management, (2) Fracture toughness shifts in high-copper weldments, (3) Fracture toughness shifts in low upper-shelf welds, (4) Irradiation effects in a commercial low upper-shelf weld, (5) Irradiation effects on weld heat-affected zone and plate materials, (6) Annealing effects in low upper-shelf welds, (7) Microstructural analysis of radiation effects, (8) In-service irradiated and aged material evaluations, (9) Japanese power development reactor vessel steel examination, (10) fracture toughness curve shift method, (11) Special technical assistance, (12) Technical assistance for JCCCNRS, (13) Correlation monitor materials, and (14) Test reactor irradiation coordination. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database

ZZ DOSCROS, Neutron Cross-Section Library for Spectra Unfolding and Integral Parameter Evaluation

International Nuclear Information System (INIS)

Zijp, Willem L.; Nolthenius, Henk J.; Rieffe, Henk Ch.

1987-01-01

1 - Description of problem or function: Format: SAND-II; Number of groups: 640 fine group cross section values; Nuclides: Li, B, F, Na, Mg, Al, S, Sc, Ti, Cr, Mn, Fe, Co, Ni, Cu, Zn, As, Br, Nb, Mo, Rh, Pd, Ag, In, Sb, I, Cs, La, Eu, Sm, Dy, Lu, Ta, W, Re, Au, Th, U, Np, Pu. Origin: ENDF/B-V mainly, ENDF/B-IV, INDL/V. This library forms in combination with the DAMSIG81 library a convenient source of evaluated energy dependent cross section sets which may be used in the determination of neutron spectra by means of adjustment (or unfolding) procedures or which can be used for the determination of integral parameters (such as damage-to-activation ratio) useful in characterising the neutron spectra. The energy dependent fine group cross section data are presented in a 640 group structure of the SAND-II type. This group structure has 45 energy groups per energy decade below 1 MeV and a group width of 100 KeV above 1 MeV. The total energy span of this group structure is from 10 -10 MeV to 20 MeV. The library has the SAND-II format, which implies that a special part of the library has to contain cover cross section data sets. These cross section data sets are required in the SAND-II program for taking into account the influence of special detector surroundings which may be used during an irradiation. 2 - Method of solution: The selection of the reactions from the evaluated nuclear data libraries was determined by various properties of the reactions for neutron metrology. For this reason all the well- known reactions of the ENDF/B-V dosimetry file are included but these data are supplemented with cross section sets for less well known metrology reactions which may become of interest

Heavy-Section Steel Technology program fracture issues

International Nuclear Information System (INIS)

Pennell, W.E.

1989-10-01

Large scale fracture mechanics tests have resulted in the identification of a number of fracture technology issues. Identification of additional issues has come from the reactor vessel materials irradiation test program and from reactor operating experience. This paper provides a review of fracture issues with an emphasis on their potential impact on a reactor vessel pressurized thermal shock (PTS) analysis. Mixed mode crack propagation emerges as a major issue, due in large measure to the poor performance of existing models for the prediction of ductile tearing. Rectification of ductile tearing technology deficiencies may require extending the technology to include a more complete treatment of stress state and loading history effects. The effect of cladding on vessel fracture remains uncertain to the point that it is not possible to determine at this time if the net effect will be positive or negative. Enhanced fracture toughness for shallow flaws has been demonstrated for low strength structural steels. Demonstration of a similar effect in reactor pressure vessel steels could have a significant beneficial effect on the probabilistic analysis of reactor vessel fracture. Further development of existing fracture mechanics models and concepts is required to meet the special requirements for fracture evaluation of circumferential flaws in the welds of ring forged vessels. Fracture technology advances required to address the issues discussed in this paper are the major objective for the ongoing Heavy Section Steel Technology (HSST) program at ORNL. 24 refs., 18 figs

Heavy-section steel technology program: Fracture issues

International Nuclear Information System (INIS)

Pennell, W.E.

1992-01-01

Large-scale fracture mechanics tests have resulted in the identification of a number of fracture technology issues. Identification of additional issues has come from the reactor vessel materials irradiation test program and from reactor operating experience. This paper provides a review of fracture issues with an emphasis on their potential impact on a reactor vessel pressurized thermal shock (PTS) analysis. Mixed mode crack propagation emerges as a major issue, due in large measure to the poor performance of existing models for the prediction of ductile tearing. Rectification of ductile tearing technology deficiencies may require extending the technology to include a more complete treatment of stress state and loading history effects. The effect of cladding on vessel fracture remains uncertain to the point that it is not possible to determine at this time if the net effect will be positive or negative. Enhanced fracture toughness for shallow flaws has been demonstrated for low-strength structural steels. Demonstration of a similar effect in reactor pressure vessel steels could have a significant beneficial effect on the probabilistic analysis of reactor vessel fracture. Further development of existing fracture mechanics models and concepts is required to meet the special requirements for fracture evaluation of circumferential flaws in the welds of ring-forged vessels. Fracture technology advances required to address the issues discussed in this paper are the major objective for the ongoing Heavy Section Steel Technology (HSST) program at ORNL

Recent developments in the Clean Water Act: Section 404 regulatory program

Energy Technology Data Exchange (ETDEWEB)

Kelsch, T. (EPA, Washington, DC (United States))

1992-12-01

Since the late 1970's and the 1980's, the Nation has become increasingly aware of the vital role wetlands play in providing habitat, protecting us from flooding and maintaining surface water quality. This public awakening came at the same time that the Fish and Wildlife Service's National Wetlands Inventory published reports indicating that less than one half of the wetlands that existed when the Europeans came to the US remain. The reports also indicated that the US was continuing to lose approximately 450,000 acres of our wetlands per year. Although recent data updating the status and trends of wetland losses for the 1980's indicate that the rate of loss has decreased, the Fish and Wildlife Service estimates indicate that approximately 290,000 acres of wetlands are still lost each year. Any loss in the natural functions provided by wetlands is not just felt in the environment; we simultaneously sustain, as a loss to our national economy, a decline in the income that could have been derived from the fisheries, recreation and other critical services performed by wetland systems. Clearly wetlands merit protection. However, in the US, where over 75 percent of our remaining wetlands are on private property, the protection of wetlands is often a difficult and sometimes contentious issue -- evoking debate about private property rights, economic development, the public interest in protecting wetland values, and the kind of world we wish to leave for future generations. Section 404 of the Clean Water Act establishes the primary Federal regulatory program providing protection for the Nation's remaining wetlands. The Section 404 permit program is recognized by both its supporters and critics as one of the strongest, yet often most contentious, Federal environmental protection programs. This presentation provides an overview of the Section 404 regulatory requirements and discusses some of the recent developments that have stirred considerable

20 CFR 408.1205 - How can a State have SSA administer its State recognition payment program?

Science.gov (United States)

2010-04-01

... recognition payment program? 408.1205 Section 408.1205 Employees' Benefits SOCIAL SECURITY ADMINISTRATION SPECIAL BENEFITS FOR CERTAIN WORLD WAR II VETERANS Federal Administration of State Recognition Payments § 408.1205 How can a State have SSA administer its State recognition payment program? A State (or...

78 FR 14909 - Pork Promotion, Research, and Consumer Information Program; Section 610 Review

Science.gov (United States)

2013-03-08

... of an Agricultural Marketing Service (AMS) review of the Pork Promotion, Research, and Consumer... DEPARTMENT OF AGRICULTURE Agricultural Marketing Service 7 CFR Part 1230 [Doc. No. AMS-LS-07-0143] Pork Promotion, Research, and Consumer Information Program; Section 610 Review AGENCY: Agricultural...

Effect of activation cross-section uncertainties in selecting steels for the HYLIFE-II chamber to successful waste management

International Nuclear Information System (INIS)

Sanz, J.; Cabellos, O.; Reyes, S.

2005-01-01

We perform the waste management assessment of the different types of steels proposed as structural material for the inertial fusion energy (IFE) HYLIFE-II concept. Both recycling options, hands-on (HoR) and remote (RR), are unacceptable. Regarding shallow land burial (SLB), 304SS has a very good performance, and both Cr-W ferritic steels (FS) and oxide-dispersion-strengthened (ODS) FS are very likely to be acceptable. The only two impurity elements that question the possibility of obtaining reduced activation (RA) steels for SLB are niobium and molybdenum. The effect of activation cross-section uncertainties on SLB assessments is proved to be important. The necessary improvement of some tungsten and niobium cross-sections is justified

Program RESENDD (version 84-07): a program for reconstruction of resonance cross sections from evaluated nuclear data in the ENDF/B format

International Nuclear Information System (INIS)

Nakagawa, Tsuneo

1984-10-01

RESENDD is a computer program to calculate resonance cross sections from evaluated resonance parameters in the ENDF/B format. This program was improved from RESEND by modifying the multi-level Breit-Wigner formula, adding a function of Doppler broadening, and so on. This report explains functions of RESENDD and describes input data. Some examples are also given. (author)

75 FR 52760 - Medicare Program; Listening Session Regarding the Implementation of Section 10332 of the Patient...

Science.gov (United States)

2010-08-27

...] Medicare Program; Listening Session Regarding the Implementation of Section 10332 of the Patient Protection... of the Patient Protection and Affordable Care Act (the Affordable Care Act), which amended section 1874 of the Social Security Act: Availability of Medicare Data for Performance Measurement. The purpose...

Measurement of the t (bar t) cross section at the Run II Tevatron using Support Vector Machines

International Nuclear Information System (INIS)

Whitehouse, Benjamin Eric

2010-01-01

This dissertation measures the t(bar t) production cross section at the Run II CDF detector using data from early 2001 through March 2007. The Tevatron at Fermilab is a p(bar p) collider with center of mass energy √s = 1.96 TeV. This data composes a sample with a time-integrated luminosity measured at 2.2 ± 0.1 fb -1 . A system of learning machines is developed to recognize t(bar t) events in the 'lepton plus jets' decay channel. Support Vector Machines are described, and their ability to cope with a multi-class discrimination problem is provided. The t(bar t) production cross section is then measured in this framework, and found to be σ t# bar t# = 7.14 ± 0.25 (stat) -0.86 +0.61 (sys) pb.

75 FR 56946 - Medicaid Program; Review and Approval Process for Section 1115 Demonstrations

Science.gov (United States)

2010-09-17

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Medicare & Medicaid Services 42 CFR Part 431 [CMS-2325-P] RIN 0938-AQ46 Medicaid Program; Review and Approval Process for Section 1115 Demonstrations AGENCY: Centers for Medicare & Medicaid Services (CMS), HHS. ACTION: Proposed rule. SUMMARY: This...

Status of the GPD program rate at COMPASS II

Energy Technology Data Exchange (ETDEWEB)

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

2015-07-01

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

The type II collagen fragments Helix-II and CTX-II reveal different enzymatic pathways of human cartilage collagen degradation

DEFF Research Database (Denmark)

Charni-Ben Tabassi, N; Desmarais, S; Jensen, Anne-Christine Bay

2008-01-01

human recombinant cathepsins (Cats) and matrix-metalloproteases (MMPs). Next, we analyzed the spontaneous release of Helix-II and CTX-II from cartilage sections of patients with knee OA who were immediately deep frozen after joint replacement to preserve endogenous enzyme activity until assay. Cartilage....... Cat D was unable to digest intact cartilage. MMPs-1, -3, -7, -9, and -13 efficiently released CTX-II, but only small amount of Helix-II. Neither CTX-II nor Helix-II alone was able to reflect accurately the collagenolytic activity of Cats and MMPs as reflected by the release of hydroxyproline. In OA...

RGENDF - An interface program between the NJOY code and codes using multigroup cross-sections

International Nuclear Information System (INIS)

Chalhoub, E.S.; Anaf, J.

1988-02-01

An interface program for reformatting multigroup cross-section libraries generated by NJOY into ENDF/B-V format and the EXPANDA, PFCOND and COMPAR input formats is presented. (author). 7 refs, 1 fig., 1 tab

The OSMOSE Experimental Program for the qualification of integral cross sections of actinides

Energy Technology Data Exchange (ETDEWEB)

Antony, Muriel; Hudelot, Jean-Pascal [CEA, Centre de Cadarache, F-13108 Saint Paul lez Durance (France); Klann, Raymond [Nuclear Engineering Division, Argonne. National Laboratory, 9700 South Cass Ave., Argonne, IL 60439-4814 (United States)

2006-07-01

at understanding and resolving potential discrepancies between calculated and measured values. The OSMOSE program began in 2005 and will continue until 2010. The reactivity worth of samples having been fabricated in CEA Marcoule from 2001 to 2005, and containing separated actinides ({sup 232}Th, {sup 233}U, {sup 234}U, {sup 235}U, {sup 236}U, {sup 238}U, {sup 237}Np, {sup 238}Pu, {sup 239}Pu, {sup 240}Pu, {sup 241}Pu, {sup 242}Pu, {sup 241}Am, {sup 243}Am, {sup 244}Cm and {sup 245}Cm), will be measured by an oscillation technique with an overall expected accuracy better than 3%. The measurements will cover a wide range of neutron spectra: over-moderated thermal spectrum, PWR UOx standard spectrum, PWR 100% MOX spectrum and epithermal HCLWR type spectrum. The paper has the following structure: I. Introduction; II. Main goals and major stakes; III. Experimental conditions; 1. The MINERVE facility; 2. The experimental lattices; 3. The oscillation technique of measurement; 4. Calibration curves for samples measurement; 5. OSMOSE samples; IV. Conclusion. To summarize, this paper has described the OSMOSE experimental program that will be performed between 2005 and 2010 in the MINERVE facility of CEA Cadarache. It covers the majority of the actinides that concern in the reactor physics and the fuel cycle, from {sup 232}Th up to {sup 245}Cm and is therefore highly valuable for every domain of neutron study. Indeed it will allow to determine by an oscillation technique the reactivity of samples containing the separated studied actinides with an accuracy that takes into account the uncertainties on the experiments, on the calculations and on the material balance of the samples. As a consequence, the OSMOSE program will involve an improvement - at least by a factor 2 - on the main nuclear data (integral resonance, capture cross section, reproduction factor) of the studied actinides, and on a large range of neutron spectra (thermal and epithermal). A single and accurate

77 FR 16203 - Section 538 Guaranteed Rural Rental Housing Program 2012 Industry Forums-Open Teleconference and...

Science.gov (United States)

2012-03-20

.... However, if it appears that existing capabilities may prevent the Agency from accommodating all requests... Section 515 developments. The impact of Low Income Housing Tax Credits program changes on Section 538..., genetic information, political beliefs, reprisal, or because all or part of an individual's income is...

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

Energy Technology Data Exchange (ETDEWEB)

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

1999-10-01

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

Model calculations as one means of satisfying the neutron cross-section requirements of the CTR program

International Nuclear Information System (INIS)

Gardner, D.G.

1975-01-01

A large amount of cross section and spectral information for neutron-induced reactions will be required for the CTR design program. To undertake to provide the required data through a purely experimental measurement program alone may not be the most efficient way of attacking the problem. It is suggested that a preliminary theoretical calculation be made of all relevant reactions on the dozen or so elements that now seem to comprise the inventory of possible construction materials to find out which are actually important, and over what energy ranges they are important. A number of computer codes for calculating cross sections for neutron induced reactions have been evaluated and extended. These will be described and examples will be given of various types of calculations of interest to the CTR program. (U.S.)

Ageing management program of wires for Atucha II Nuclear Power Plant

International Nuclear Information System (INIS)

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

2012-01-01

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

13 CFR 121.301 - What size standards are applicable to financial assistance programs?

Science.gov (United States)

2010-01-01

...) and (b)(2)(ii) of this section. (c) For the Small Business Investment Company (SBIC) program, an... Trends in Employment and Unemployment.” [61 FR 3286, Jan. 31, 1996, as amended at 66 FR 30648, June 7...

ANADP II Program Committee Closing Remarks 2013

OpenAIRE

Program Committee

2014-01-01

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

Evaluation of ETOG-3Q/ETOG-3, FLANGE-II, XLACS, NJOY and linear/recent/groupie codes for calculations of resonance and reference cross sections

International Nuclear Information System (INIS)

Anaf, J.; Chalhoub, E.S.

1991-01-01

The NJOY and LINEAR/RECENT/GROUPIE calculational procedures for the resolved and unresolved resonance contributions and background cross sections are evaluated. Elastic scattering, fission and capture multigroup cross sections generated by these codes and the previously validated ETOG-3Q, ETOG-3, FLANGE-II and XLACS are compared. Constant weighting function and zero Kelvin temperature are considered. Discrepancies are presented and analyzed. (author)

Integrated Sensing and Processing (ISP) Phase II: Demonstration and Evaluation for Distributed Sensor Netowrks and Missile Seeker Systems

Science.gov (United States)

2007-02-28

National Industrial Security Program Operating Manual (NISPOM), Chapter 5, Section 7, or DOD 5200.1-R, Information Security Program Regulation...Sensing and Processing (ISP) Phase II: Demonstration and Evaluation for Distributed Sensor Netowrks and Missile Seeker Systems 5a. CONTRACT NUMBER 5b... SECURITY CLASSIFICATION OF: 17. LIMITATION OF ABSTRACT 18. NUMBER OF PAGES 41 19a. NAME OF RESPONSIBLE PERSON a. REPORT unclassified b. ABSTRACT

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

Energy Technology Data Exchange (ETDEWEB)

1978-07-27

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

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

International Nuclear Information System (INIS)

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

1982-12-01

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

ENDFIC - A program for indexing and intercomparison of ENDFs

International Nuclear Information System (INIS)

Gopalakrishnan, V.; Devan, K.

1995-01-01

The program ENDFIC, a nuclear data utility program in FORTRAN, was written under contract on 'Indexing and Intercomparison Programme of Evaluated Nuclear Data Files' (No. 7866/RB/TC), between Indira Gandhi Centre for Atomic Research, Kalpakkam, and the International Atomic Energy Agency, Vienna. The program can be used for the following two activities: i. INFO activity: to find from a given ENDF/B formatted evaluated nuclear data library, information regarding the contents of the library; ii. COMP activity: to do comparison of cross sections from several given ENDF libraries. 1 ref

Overviews of EMRAS I and II

International Nuclear Information System (INIS)

Kawaguchi, Isao

2011-01-01

Recently there has been attracting growing interest in impacts of irradiation to wildlife organisms. In IAEA, biota dosimetry working group (BWG) was established in Environmental Modeling for Radiation Safety (EMRAS) program, which aimed to intercompare biota dose assessment models to validate their assumptions and estimations. After EMRAS program finished, new program which is referred as EMRAS II was set on January 2009. In EMRAS II, there are three themes, and 9 working groups were established. One of three themes is related to environmental protection, and three working groups (Biota modeling, wildlife transfer coefficient handbook, biota dose effects modeling) were constituted in it. In this report, activities of EMRAS I BWG and EMRAS II theme II are summarized. (author)

Risk Management Programs under Clean Air Act Section 112(r): Guidance for Implementing Agencies

Science.gov (United States)

Accidental release prevention programs under section 112(r) of the Clean Air Act (CAA) are related to and build on activities under the Emergency Planning and Community Right-to-Know Act, and Occupational Safety and Health Administration standards.

PIP-II Injector Test: Challenges and Status

Energy Technology Data Exchange (ETDEWEB)

Derwent, P. F. [Fermilab; Carneiro, J. P. [Fermilab; Edelen, J. [Fermilab; Lebedev, V. [Fermilab; Prost, L. [Fermilab; Saini, A. [Fermilab; Shemyakin, A. [Fermilab; Steimel, J. [Fermilab

2016-10-04

The Proton Improvement Plan II (PIP-II) at Fermilab is a program of upgrades to the injection complex. At its core is the design and construction of a CW-compatible, pulsed H- superconducting RF linac. To validate the concept of the front-end of such machine, a test accelerator known as PIP-II Injector Test is under construction. It includes a 10mA DC, 30 keV H- ion source, a 2 m-long Low Energy Beam Transport (LEBT), a 2.1 MeV CW RFQ, followed by a Medium Energy Beam Transport (MEBT) that feeds the first of 2 cryomodules increasing the beam energy to about 25 MeV, and a High Energy Beam Transport section (HEBT) that takes the beam to a dump. The ion source, LEBT, RFQ, and initial version of the MEBT have been built, installed, and commissioned. This report presents the overall status of the Injector Test warm front end, including results of the beam commissioning through the installed components, and progress with SRF cryomodules and other systems.

Applied structural and solid mechanics section: 1983 review and 1984 programs

International Nuclear Information System (INIS)

Chadha, J.A.

1984-01-01

This report reviews briefly the applied research and problem solving work carried out by the Applied Structural and Solid Mechanics Section during 1983. In 1983 there was a strong demand for services in the areas of theroretical and experimental stress analysis, heat transfer analysis, nonlinear analysis, and general structural analyses related to nuclear and thermal power plant, and transmission line components. Development of capabilities in these areas progressed well. Proposed work programs for 1984 are outlined in this report

Report on the Concept Review Committee recommendations for proof-of-principle alternate concept programs

International Nuclear Information System (INIS)

1979-03-01

The report is organized as follows: Section II contains a discussion of the meeting procedures used on October 16--18, 1978, and the rules employed for technical consultants and advisors to the CRC. Section III contains a discussion of the CRC recommendations and some of the factors taken into consideration by the Committee. Section IV briefly discusses where do we go from here in DOE's alternate concepts program

The EBR-II materials-surveillance program. 5: Results of SURV-5

International Nuclear Information System (INIS)

Ruther, W.E.; Staffon, J.D.; Carlson, B.G.; Allen, T.R.

1998-01-01

In March of 1965, a set of surveillance (SURV) samples was placed in the EBR-II reactor to determine the effect of irradiation, thermal aging, and sodium corrosion on reactor materials. Eight subassemblies were placed into row 12 positions of EBR-II to determine the effect of irradiation at 370 C. Two subassemblies were placed into the primary sodium basket to determine the effect of thermal aging at 370 C. One half of all samples were exposed to primary system sodium while one half were sealed in capsules with a helium atmosphere. Fifteen different structural materials were tested in the SURV program. In this work, the properties of these materials irradiated at 370 C to a total fluence of 3.2 x 10 22 n/cm 2 were determined. These materials are the fifth set of irradiated subassemblies to be examined as part of the SURV program (SURV-5). The properties analyzed were weight, density, microstructure, hardness, tensile and yield strength, and fracture resistance. Of all the alloys examined in SURV-5, only Berylco-25 showed any significant weight loss. Stainless steel (both 304 and 347) had the largest density decrease, although the density decrease from irradiation for all alloys was less than 0.4 percent. The microstructure of both Berylco-25 and the aluminum-bronze alloy was altered significantly. Iron- and nickel-base alloys showed little change in microstructure. Austenitic steels (304 and 347) harden with irradiation. The hardness of Inconel X750 did not change significantly with irradiation. The ultimate tensile strength of Inconel X750, 304 stainless steel, 420 stainless steel and welded 304 changed little due to a fluence increase from 2.2 x 10 22 n/cm 2 (the maximum fluence of the SURV-4 samples) to 3.2 x 10 22 n/cm 2

Heavy-section steel irradiation program: Embrittlement issues

International Nuclear Information System (INIS)

Corwin, W.R.

1991-01-01

Maintaining the integrity of the reactor pressure vessel (RPV) in a light-water-cooled nuclear power plant is crucial in preventing and controlling severe accidents and the potential for major contamination releases. The RPV is one of only two major safety- related components of the plant for which a duplicate or redundant backup system does not exist. In particular, it is vital to fully understand the degree of irradiation-induced degradation of the RPV's fracture resistance which occurs during service, since without that radiation damage it is virtually impossible to postulate a realistic scenario which would result in RPV failure. For this reason, the Heavy-Section Steel Irradiation (HSSI) Program has been established by the US Nuclear Regulatory Commission (USNRC) to provide a thorough, quantitative assessment of the effects of neutron irradiation on the material behavior, and in particular the fracture toughness properties, of typical pressure vessel steels as they relate to light-water reactor pressure-vessel integrity. Effects of specimen size, material chemistry, product form and microstructure, irradiation fluence, flux, temperature and spectrum, and postirradiation annealing are being examined on a wide range of fracture properties including fracture toughness crack arrest toughness ductile tearing resistance Charpy V-notch impact energy, dropweight nil-ductility temperature and tensile properties. Models based on observations of radiation-induced microstructural changes using the field on microprobe and the high resolution transmission electron microscopy provide improved bases for extrapolating the measured changes in fracture properties to wider ranges of irradiation conditions. The principal materials examined within the HSSI program are high-copper welds since their postirradiation properties are most frequently limiting in the continued safe operation of commercial RPVs

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

International Nuclear Information System (INIS)

Meneghetti, D.; Kucera, D.A.

1981-01-01

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

Cutting work in thick section cryomicrotomy.

Science.gov (United States)

Saubermann, A J; Riley, W D; Beeuwkes, R

1977-09-01

The forces during cryosectioning were measured using miniature strain gauges attached to a load cell fitted to the drive arm of the Porter-Blum MT-2 cryomicrotome. Work was calculated and the data normalized to a standard (1 mm X 1 mm X 0.5 micrometer) section. Thermal energy generated was also calculated. Five parameters were studied: cutting angle, thickness, temperature, hardness, and block shape. Force patterns could be divided into three major groups thought to represent cutting (Type I), large fracture planes greater than 10 micrometer in length (Type II), and small fracture planes less than 10 micrometer in length (Type III). Type I and Type II produced satisfactory sections. Work in cutting ranged from an average of 78.4 muJ to 568.8 muJ. Cutting angle and temperature had the greatest effect on sectioning. Heat generated would be sufficient to cause through-section melting for 0.5 micrometer thick sections assuming the worst possible case, namely that all heat went into the section without loss. Presence of a Type II pattern (large fracture pattern) is thought to be presumptive evidence against thawing.

DOE program guide for universities and other research groups. Part I. DOE Research and Development Programs; Part II. DOE Procurement and Assistance Policies/Procedures

Energy Technology Data Exchange (ETDEWEB)

1980-03-01

This guide addresses the DOE responsibility for fostering advanced research and development of all energy resources, both current and potential. It is intended to provide, in a single publication, all the fundamental information needed by an institution to develop a potential working relationship with DOE. Part I describes DOE research and development programs and facilities, and identifies areas of additional research needs and potential areas for new research opportunities. It also summarizes budget data and identifies the DOE program information contacts for each program. Part II provides researchers and research administrators with an introduction to the DOE administrative policies and procedures for submission and evaluation of proposals and the administration of resulting grants, cooperative agreements, and research contracts. (RWR)

Metal components analysis of metallothionein-III in the brain sections of metallothionein-I and metallothionein-II null mice exposed to mercury vapor with HPLC/ICP-MS

Energy Technology Data Exchange (ETDEWEB)

Kameo, Satomi; Nakai, Kunihiko; Kurokawa, Naoyuki; Satoh, Hiroshi [Tohoku University, Graduate School of Medicine, Aoba-ku, Sendai (Japan); Kanehisa, Tomokazu; Naganuma, Akira [Tohoku University, Graduate School of Pharmaceutical Sciences, Sendai (Japan)

2005-04-01

Mercury vapor is effectively absorbed via inhalation and easily passes through the blood-brain barrier; therefore, mercury poisoning with primarily central nervous system symptoms occurs. Metallothionein (MT) is a cysteine-rich metal-binding protein and plays a protective role in heavy-metal poisoning and it is associated with the metabolism of trace elements. Two MT isoforms, MT-I and MT-II, are expressed coordinately in all mammalian tissues, whereas MT-III is a brain-specific member of the MT family. MT-III binds zinc and copper physiologically and is seemed to have important neurophysiological and neuromodulatory functions. The MT functions and metal components of MTs in the brain after mercury vapor exposure are of much interest; however, until now they have not been fully examined. In this study, the influences of the lack of MT-I and MT-II on mercury accumulation in the brain and the changes of zinc and copper concentrations and metal components of MTs were examined after mercury vapor exposure by using MT-I, II null mice and 129/Sv (wild-type) mice as experimental animals. MT-I, II null mice and wild-type mice were exposed to mercury vapor or an air stream for 2 h and were killed 24 h later. The brain was dissected into the cerebral cortex, the cerebellum, and the hippocampus. The concentrations of mercury in each brain section were determined by cold vapor atomic absorption spectrometry. The concentrations of mercury, copper, and zinc in each brain section were determined by inductively coupled plasma mass spectrometry (ICP-MS). The mercury accumulated in brains after mercury vapor exposure for MT-I, II null mice and wild-type mice. The mercury levels of MT-I, II null mice in each brain section were significantly higher than those of wild-type mice after mercury vapor exposure. A significant change of zinc concentrations with the following mercury vapor exposure for MT-I, II null mice was observed only in the cerebellum analyzed by two-way analysis of

Subseabed disposal program annual report, January-December 1979. Volume II. Appendices (principal investigator progress reports). Part 1 of 2

International Nuclear Information System (INIS)

Talbert, D.M.

1981-04-01

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

USDA Section 9006 Program: Status and Energy Benefits of Grant Awards in FY 2003-2005

Energy Technology Data Exchange (ETDEWEB)

Walters, T.; Savage, S.; Brown, J.

2006-08-01

At the request of the U. S. Department of Agriculture (USDA) Rural Development, the National Renewable Energy Laboratory reviewed projects awarded in the Section 9006 Program: Renewable Energy Systems and Energy Efficiency Improvements Program. This report quantifies federal and private investment, outlines project status based on recent field updates, and calculates the effects on energy and emissions of energy efficiency and renewable energy projects awarded grants in FY 2003, FY 2004, and FY 2005. An overview of the program challenges and modifications in the first three years of operation is also included.

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

Science.gov (United States)

Gudehus, D. H.

2001-05-01

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

Research on radionuclide migration under subsurface geochemical conditions. JAERI/AECL Phase II Collaborative Program Year 1 (joint research)

International Nuclear Information System (INIS)

1998-11-01

A radionuclide migration experiment program for fractured rocks was performed under the JAERI/AECL Phase-II Collaborative Program on research and development in radioactive waste management. The program started in the fiscal year 1993, as a five-year program consists of Quarried block radionuclide migration program, Speciation of long-lived radionuclides in groundwater, Isotopic hydrogeology and Groundwater flow model development. During the first year of the program (Program Year 1: March 18, 1994 - September 30, 1994), a plan was developed to take out granite blocks containing part of natural water-bearing fracture from the wall of the experimental gallery at the depth of 240 m, and literature reviews were done in the area of the speciation of long-lived radionuclides in groundwater, isotopic hydrogeology and the groundwater flow model development to proceed further work for the Program Year 2. (author)

CD4(+) type II NKT cells mediate ICOS and programmed death-1-dependent regulation of type 1 diabetes.

Science.gov (United States)

Kadri, Nadir; Korpos, Eva; Gupta, Shashank; Briet, Claire; Löfbom, Linda; Yagita, Hideo; Lehuen, Agnes; Boitard, Christian; Holmberg, Dan; Sorokin, Lydia; Cardell, Susanna L

2012-04-01

Type 1 diabetes (T1D) is a chronic autoimmune disease that results from T cell-mediated destruction of pancreatic β cells. CD1d-restricted NKT lymphocytes have the ability to regulate immunity, including autoimmunity. We previously demonstrated that CD1d-restricted type II NKT cells, which carry diverse TCRs, prevented T1D in the NOD mouse model for the human disease. In this study, we show that CD4(+) 24αβ type II NKT cells, but not CD4/CD8 double-negative NKT cells, were sufficient to downregulate diabetogenic CD4(+) BDC2.5 NOD T cells in adoptive transfer experiments. CD4(+) 24αβ NKT cells exhibited a memory phenotype including high ICOS expression, increased cytokine production, and limited display of NK cell markers, compared with double-negative 24αβ NKT cells. Blocking of ICOS or the programmed death-1/programmed death ligand 1 pathway was shown to abolish the regulation that occurred in the pancreas draining lymph nodes. To our knowledge, these results provide for the first time cellular and molecular information on how type II CD1d-restricted NKT cells regulate T1D.

20 CFR 408.1235 - How does the State transfer funds to SSA to administer its recognition payment program?

Science.gov (United States)

2010-04-01

... administer its recognition payment program? 408.1235 Section 408.1235 Employees' Benefits SOCIAL SECURITY ADMINISTRATION SPECIAL BENEFITS FOR CERTAIN WORLD WAR II VETERANS Federal Administration of State Recognition Payments § 408.1235 How does the State transfer funds to SSA to administer its recognition payment program...

77 FR 23228 - Notice of Submission for OMB Review; Small Business Innovation Research (SBIR) Program-Phase II...

Science.gov (United States)

2012-04-18

... business concerns to submit a Phase II application for the Small Business Innovation Research (SBIR) Program (CFDA 84.133). This is in response to Public Law 106-554, the ``Small Business Reauthorization Act... DEPARTMENT OF EDUCATION Notice of Submission for OMB Review; Small Business Innovation Research...

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

International Nuclear Information System (INIS)

2003-03-01

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

Measurement of the t$\\bar{t}$ cross section at the Run II Tevatron using Support Vector Machines

Energy Technology Data Exchange (ETDEWEB)

Whitehouse, Benjamin Eric [Tufts Univ., Medford, MA (United States)

2010-08-01

This dissertation measures the t$\\bar{t}$ production cross section at the Run II CDF detector using data from early 2001 through March 2007. The Tevatron at Fermilab is a p$\\bar{p}$ collider with center of mass energy √s = 1.96 TeV. This data composes a sample with a time-integrated luminosity measured at 2.2 ± 0.1 fb^-1. A system of learning machines is developed to recognize t$\\bar{t}$ events in the 'lepton plus jets' decay channel. Support Vector Machines are described, and their ability to cope with a multi-class discrimination problem is provided. The t$\\bar{t}$ production cross section is then measured in this framework, and found to be σ_t$\\bar{t}$ = 7.14 ± 0.25 (stat)_-0.86^+0.61(sys) pb.

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

International Nuclear Information System (INIS)

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

2015-01-01

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

TRUPACT-II container maintenance program plan

International Nuclear Information System (INIS)

1990-01-01

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

Manufacturing Math Classes: An Instructional Program Guide for Manufacturing Workers.

Science.gov (United States)

McBride, Pamela G.; And Others

This program guide documents a manufacturing job family curriculum that develops competence in generic work force education skills through three courses: Reading Rulers, Charts, and Gauges and Math for Manufacturing Workers I and II. An annotated table of contents lists a brief description of the questions answered in each section. An introduction…

Measurements of the neutral current e{sup {+-}}p cross sections using longitudinally polarised lepton beams at HERA II

Energy Technology Data Exchange (ETDEWEB)

Nikiforov, A.

2007-01-18

This thesis presents inclusive e{sup {+-}}p single and double differential cross sections for neutral current deep inelastic scattering measured as functions of the four-momentum transfer squared Q{sup 2} and the Bjorken variable x in interactions of longitudinally polarised leptons with unpolarised protons using the H1 detector at HERA II. An overview of the phenomenology of deep inelastic scattering is given and the experimental apparatus as well as the measurement and analysis procedures are described. The analysis is based on e{sup +}p data taken in 2003-04 and e{sup -}p data taken in 2005 at a centre-of-mass energy of {radical}(s)=318 GeV, with integrated luminosities of 47.6 pb{sup -1} and 98.4 pb{sup -1} for the e{sup +}p and e{sup -}p samples, respectively. The cross sections are measured in the range of 200II data are combined together with previously published data from HERA I to determine the structure function xF{sub 3} with improved precision. Furthermore, this measurement is combined with the corresponding ZEUS measurement to provide the most accurate measurement of the interference structure function xF{sup {gamma}}{sup Z}{sub 3}, which is sensitive to the valence quark distributions down to low values of x. The data on polarised cross section asymmetries A{sup {+-}} are also combined with the ZEUS data. This leads to the first observation of parity violation in neutral current e{sup {+-}}p scattering at distances down to 10{sup -18} m. The data are well described by the Standard Model predictions. (orig.)

Sample Exchange Evaluation (SEE) Report - Phase II

Energy Technology Data Exchange (ETDEWEB)

Winters, W.I.

1994-09-28

This report describes the results from Phase II of the Sample Exchange Evaluation (SEE) Program, a joint effort to compare analytical laboratory performance on samples from the Hanford Site`s high-level waste tanks. In Phase II, the program has been expanded to include inorganic constituents in addition to radionuclides. Results from Phase II that exceeded 20% relative percent difference criteria are identified.

Sample Exchange Evaluation (SEE) Report - Phase II

International Nuclear Information System (INIS)

Winters, W.I.

1994-01-01

This report describes the results from Phase II of the Sample Exchange Evaluation (SEE) Program, a joint effort to compare analytical laboratory performance on samples from the Hanford Site's high-level waste tanks. In Phase II, the program has been expanded to include inorganic constituents in addition to radionuclides. Results from Phase II that exceeded 20% relative percent difference criteria are identified

Heavy-Section Steel Irradiation Program: Embrittlement issues

International Nuclear Information System (INIS)

Corwin, W.R.

1991-01-01

Maintaining the integrity of the reactor pressure vessel (RPV) in a light-water-cooled nuclear power plant is crucial in preventing and controlling severe accidents and the potential for major contamination releases. It is imperative to understand and predict the capabilities and limitations of its integrity. It is particularly vital to fully understand the degree of irradiation-induced degradation of the RPV's fracture resistance which occurs during service, since without that radiation damage it is virtually impossible to postulate a realistic scenario which would result in RPV failure. The Heavy-Section Steel Irradiation (HSSI) Program has been established by the US Nuclear Regulatory Commission (USNRC) to provide a thorough, quantitative assessment of the effects of neutron irradiation on the material behavior, and in particular the fracture toughness properties, of typical pressure vessel steels as they relate to light-water reactor pressure-vessel integrity. Results from HSSI studies provide information needed to aid in resolving major regulatory issues facing the USNRC which involve RPV irradiation embrittlement such as pressurized-thermal shock, operating pressure-temperature limits, low-temperature overpressurization, and the specialized problems associated with low upper-shelf (LUS) welds. Taken together the results of these studies also provide guidance and bases for evaluating both the aging behavior and the potential for plant life extension of light-water RPVs. The principal materials examined within the HSSI program are high-copper welds since their postirradiation properties are most frequently limiting in the continued safe operation of commercial RPVs. Embrittlement modeling studies have shown that the time or dose required for the point defect concentrations, which ultimately contribute to irradiation embrittlement, to reach their steady state values can be comparable to the component lifetime or to the duration of an irradiation experiment

Measurement of the cross section for prompt isolated diphoton production using the full CDF run II data sample.

Science.gov (United States)

Aaltonen, T; Amerio, S; Amidei, D; Anastassov, A; Annovi, A; Antos, J; Apollinari, G; Appel, J A; Arisawa, T; Artikov, A; Asaadi, J; Ashmanskas, W; Auerbach, B; Aurisano, A; Azfar, F; Badgett, W; Bae, T; Barbaro-Galtieri, A; Barnes, V E; Barnett, B A; Barria, P; Bartos, P; Bauce, M; Bedeschi, F; Behari, S; Bellettini, G; Bellinger, J; Benjamin, D; Beretvas, A; Bhatti, A; Bland, K R; Blumenfeld, B; Bocci, A; Bodek, A; Bortoletto, D; Boudreau, J; Boveia, A; Brigliadori, L; Bromberg, C; Brucken, E; Budagov, J; Budd, H S; Burkett, K; Busetto, G; Bussey, P; Butti, P; Buzatu, A; Calamba, A; Camarda, S; Campanelli, M; Canelli, F; Carls, B; Carlsmith, D; Carosi, R; Carrillo, S; Casal, B; Casarsa, M; Castro, A; Catastini, P; Cauz, D; Cavaliere, V; Cavalli-Sforza, M; Cerri, A; Cerrito, L; Chen, Y C; Chertok, M; Chiarelli, G; Chlachidze, G; Cho, K; Chokheli, D; Ciocci, M A; Clark, A; Clarke, C; Convery, M E; Conway, J; Corbo, M; Cordelli, M; Cox, C A; Cox, D J; Cremonesi, M; Cruz, D; Cuevas, J; Culbertson, R; d'Ascenzo, N; Datta, M; De Barbaro, P; Demortier, L; Deninno, M; Devoto, F; d'Errico, M; Di Canto, A; Di Ruzza, B; Dittmann, J R; D'Onofrio, M; Donati, S; Dorigo, M; Driutti, A; Ebina, K; Edgar, R; Elagin, A; Erbacher, R; Errede, S; Esham, B; Eusebi, R; Farrington, S; Fernández Ramos, J P; Field, R; Flanagan, G; Forrest, R; Franklin, M; Freeman, J C; Frisch, H; Funakoshi, Y; Garfinkel, A F; Garosi, P; Gerberich, H; Gerchtein, E; Giagu, S; Giakoumopoulou, V; Gibson, K; Ginsburg, C M; Giokaris, N; Giromini, P; Giurgiu, G; Glagolev, V; Glenzinski, D; Gold, M; Goldin, D; Golossanov, A; Gomez, G; Gomez-Ceballos, G; Goncharov, M; González López, O; Gorelov, I; Goshaw, A T; Goulianos, K; Gramellini, E; Grinstein, S; Grosso-Pilcher, C; Group, R C; Guimaraes da Costa, J; Hahn, S R; Han, J Y; Happacher, F; Hara, K; Hare, M; Harr, R F; Harrington-Taber, T; Hatakeyama, K; Hays, C; Heinrich, J; Herndon, M; Hocker, A; Hong, Z; Hopkins, W; Hou, S; Hughes, R E; Husemann, U; Huston, J; Introzzi, G; Iori, M; Ivanov, A; James, E; Jang, D; Jayatilaka, B; Jeon, E J; Jindariani, S; Jones, M; Joo, K K; Jun, S Y; Junk, T R; Kambeitz, M; Kamon, T; Karchin, P E; Kasmi, A; Kato, Y; Ketchum, W; Keung, J; Kilminster, B; Kim, D H; Kim, H S; Kim, J E; Kim, M J; Kim, S B; Kim, S H; Kim, Y K; Kim, Y J; Kimura, N; Kirby, M; Knoepfel, K; Kondo, K; Kong, D J; Konigsberg, J; Kotwal, A V; Kreps, M; Kroll, J; Kruse, M; Kuhr, T; Kurata, M; Laasanen, A T; Lammel, S; Lancaster, M; Lannon, K; Latino, G; Lee, H S; Lee, J S; Leo, S; Leone, S; Lewis, J D; Limosani, A; Lipeles, E; Liu, H; Liu, Q; Liu, T; Lockwitz, S; Loginov, A; Lucchesi, D; Lueck, J; Lujan, P; Lukens, P; Lungu, G; Lys, J; Lysak, R; Madrak, R; Maestro, P; Malik, S; Manca, G; Manousakis-Katsikakis, A; Margaroli, F; Marino, P; Martínez, M; Matera, K; Mattson, M E; Mazzacane, A; Mazzanti, P; McNulty, R; Mehta, A; Mehtala, P; Mesropian, C; Miao, T; Mietlicki, D; Mitra, A; Miyake, H; Moed, S; Moggi, N; Moon, C S; Moore, R; Morello, M J; Mukherjee, A; Muller, Th; Murat, P; Mussini, M; Nachtman, J; Nagai, Y; Naganoma, J; Nakano, I; Napier, A; Nett, J; Neu, C; Nigmanov, T; Nodulman, L; Noh, S Y; Norniella, O; Oakes, L; Oh, S H; Oh, Y D; Oksuzian, I; Okusawa, T; Orava, R; Ortolan, L; Pagliarone, C; Palencia, E; Palni, P; Papadimitriou, V; Parker, W; Pauletta, G; Paulini, M; Paus, C; Phillips, T J; Piacentino, G; Pianori, E; Pilot, J; Pitts, K; Plager, C; Pondrom, L; Poprocki, S; Potamianos, K; Prokoshin, F; Pranko, A; Ptohos, F; Punzi, G; Ranjan, N; Redondo Fernández, I; Renton, P; Rescigno, M; Riddick, T; Rimondi, F; Ristori, L; Robson, A; Rodriguez, T; Rolli, S; Ronzani, M; Roser, R; Rosner, J L; Ruffini, F; Ruiz, A; Russ, J; Rusu, V; Safonov, A; Sakumoto, W K; Sakurai, Y; Santi, L; Sato, K; Saveliev, V; Savoy-Navarro, A; Schlabach, P; Schmidt, E E; Schwarz, T; Scodellaro, L; Scuri, F; Seidel, S; Seiya, Y; Semenov, A; Sforza, F; Shalhout, S Z; Shears, T; Shepard, P F; Shimojima, M; Shochet, M; Shreyber-Tecker, I; Simonenko, A; Sinervo, P; Sliwa, K; Smith, J R; Snider, F D; Sorin, V; Song, H; Stancari, M; St Denis, R; Stelzer, B; Stelzer-Chilton, O; Stentz, D; Strologas, J; Sudo, Y; Sukhanov, A; Suslov, I; Takemasa, K; Takeuchi, Y; Tang, J; Tecchio, M; Teng, P K; Thom, J; Thomson, E; Thukral, V; Toback, D; Tokar, S; Tollefson, K; Tomura, T; Tonelli, D; Torre, S; Torretta, D; Totaro, P; Trovato, M; Ukegawa, F; Uozumi, S; Vázquez, F; Velev, G; Vellidis, C; Vernieri, C; Vidal, M; Vilar, R; Vizán, J; Vogel, M; Volpi, G; Wagner, P; Wallny, R; Wang, S M; Warburton, A; Waters, D; Wester, W C; Whiteson, D; Wicklund, A B; Wilbur, S; Williams, H H; Wilson, J S; Wilson, P; Winer, B L; Wittich, P; Wolbers, S; Wolfe, H; Wright, T; Wu, X; Wu, Z; Yamamoto, K; Yamato, D; Yang, T; Yang, U K; Yang, Y C; Yao, W-M; Yeh, G P; Yi, K; Yoh, J; Yorita, K; Yoshida, T; Yu, G B; Yu, I; Zanetti, A M; Zeng, Y; Zhou, C; Zucchelli, S

2013-03-08

This Letter reports a measurement of the cross section for producing pairs of central prompt isolated photons in proton-antiproton collisions at a total energy sqrt[s] = 1.96 TeV using data corresponding to 9.5 fb(-1) integrated luminosity collected with the CDF II detector at the Fermilab Tevatron. The measured differential cross section is compared to three calculations derived from the theory of strong interactions. These include a prediction based on a leading order matrix element calculation merged with a parton shower model, a next-to-leading order calculation, and a next-to-next-to-leading order calculation. The first and last calculations reproduce most aspects of the data, thus showing the importance of higher-order contributions for understanding the theory of strong interaction and improving measurements of the Higgs boson and searches for new phenomena in diphoton final states.

Cross section measurement and integral test for several activation reactions using T + d and thick-Li + d sources

International Nuclear Information System (INIS)

Dumais, J.R.; Tanaka, S.; Odano, N.; Iwasaki, S.; Sugiyama, K.

1988-01-01

Recent activities on the area of the cross section measurement for several activation reactions at Department of Nucl. Eng., Tohoku Univ. are described. The first subject is the cross section measurement for (n,2n) reaction on aluminum using the RTNS-II neutron source. Cross sections with rather small error band were obtained for the incident neutron energies from 14 to 14.7 MeV. The second one is the status of the program for the integral experiments on several reactions using the thick Li + d source at Tohoku Fast Neutron Lab. The experimental results showed the usefullness of the source as a tool for the cross section assessment. (author)

The TRUPACT-II Matrix Depleton Program

International Nuclear Information System (INIS)

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

1995-01-01

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

Elliptical cross section fuel rod study II

International Nuclear Information System (INIS)

Taboada, H.; Marajofsky, A.

1996-01-01

In this paper it is continued the behavior analysis and comparison between cylindrical fuel rods of circular and elliptical cross sections. Taking into account the accepted models in the literature, the fission gas swelling and release were studied. An analytical comparison between both kinds of rod reveals a sensible gas release reduction in the elliptical case, a 50% swelling reduction due to intragranular bubble coalescence mechanism and an important swelling increase due to migration bubble mechanism. From the safety operation point of view, for the same linear power, an elliptical cross section rod is favored by lower central temperatures, lower gas release rates, greater gas store in ceramic matrix and lower stored energy rates. (author). 6 refs., 8 figs., 1 tab

Training experience at Experimental Breeder Reactor II

International Nuclear Information System (INIS)

Driscoll, J.W.; McCormick, R.P.; McCreery, H.I.

1978-01-01

The EBR-II Training Group develops, maintains,and oversees training programs and activities associated with the EBR-II Project. The group originally spent all its time on EBR-II plant-operations training, but has gradually spread its work into other areas. These other areas of training now include mechanical maintenance, fuel manufacturing facility, instrumentation and control, fissile fuel handling, and emergency activities. This report describes each of the programs and gives a statistical breakdown of the time spent by the Training Group for each program. The major training programs for the EBR-II Project are presented by multimedia methods at a pace controlled by the student. The Training Group has much experience in the use of audio-visual techniques and equipment, including video-tapes, 35 mm slides, Super 8 and 16 mm film, models, and filmstrips. The effectiveness of these techniques is evaluated in this report

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

International Nuclear Information System (INIS)

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

2001-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

None

1977-01-17

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

Confined states of individual type-II GaSb/GaAs quantum rings studied by cross-sectional scanning tunneling spectroscopy.

Science.gov (United States)

Timm, Rainer; Eisele, Holger; Lenz, Andrea; Ivanova, Lena; Vossebürger, Vivien; Warming, Till; Bimberg, Dieter; Farrer, Ian; Ritchie, David A; Dähne, Mario

2010-10-13

Combined cross-sectional scanning tunneling microscopy and spectroscopy results reveal the interplay between the atomic structure of ring-shaped GaSb quantum dots in GaAs and the corresponding electronic properties. Hole confinement energies between 0.2 and 0.3 eV and a type-II conduction band offset of 0.1 eV are directly obtained from the data. Additionally, the hole occupancy of quantum dot states and spatially separated Coulomb-bound electron states are observed in the tunneling spectra.

PEP-II Large Power Supplies Rebuild Program at SLAC

CERN Document Server

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

2005-01-01

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

Constellation Program: Lessons Learned. Volume 1; Executive Summary

Science.gov (United States)

Rhatigan, Jennifer L. (Editor)

2011-01-01

This document (Volume I) provides an executive summary of the lessons learned from the Constellation Program. A companion Volume II provides more detailed analyses for those seeking further insight and information. In this volume, Section 1.0 introduces the approach in preparing and organizing the content to enable rapid assimilation of the lessons. Section 2.0 describes the contextual framework in which the Constellation Program was formulated and functioned that is necessary to understand most of the lessons. Context of a former program may seem irrelevant in the heady days of new program formulation. However, readers should take some time to understand the context. Many of the lessons would be different in a different context, so the reader should reflect on the similarities and differences in his or her current circumstances. Section 3.0 summarizes key findings developed from the significant lessons learned at the program level that appear in Section 4.0. Readers can use the key findings in Section 3.0 to peruse for particular topics, and will find more supporting detail and analyses in Section 4.0 in a topical format. Appendix A contains a white paper describing the Constellation Program formulation that may be of use to readers wanting more context or background information. The reader will no doubt recognize some very similar themes from previous lessons learned, blue-ribbon committee reviews, National Academy reviews, and advisory panel reviews for this and other large-scale human spaceflight programs; including Apollo, Space Shuttle, Shuttle/Mir, and the ISS. This could represent an inability to learn lessons from previous generations; however, it is more likely that similar challenges persist in the Agency structure and approach to program formulation, budget advocacy, and management. Perhaps the greatest value of these Constellation lessons learned can be found in viewing them in context with these previous efforts to guide and advise the Agency and its

RTNS-II: present status

International Nuclear Information System (INIS)

Heikkinen, D.W.; Logan, C.M.

1980-10-01

The present status of the RTNS-II facility is described and typical operating parameters are given. A brief discussion is given of the methods used in production of the TiT 2 targets as well as their performance and tritium handling at RTNS-II. The various types of non-interactive beam diagnostics presently in use at the neutron sources are outlined. The on-line computer system which provides a time history of an irradiation and records target performance is described. Examples are listed of several representative experimental programs which have been carried out thus far at RTNS-II. These include both active and passive experiments. Finally, several of the major improvements to the facility made since the beginning of the experimental program are given

Measurement of the WW + WZ production cross section using the lepton + jets final state at CDF II.

Science.gov (United States)

Aaltonen, T; Adelman, J; Alvarez González, B; Amerio, S; Amidei, D; Anastassov, A; Annovi, A; Antos, J; Apollinari, G; Apresyan, A; Arisawa, T; Artikov, A; Asaadi, J; Ashmanskas, W; Attal, A; Aurisano, A; Azfar, F; Badgett, W; Barbaro-Galtieri, A; Barnes, V E; Barnett, B A; Barria, P; Bartos, P; Bauer, G; Beauchemin, P-H; Bedeschi, F; Beecher, D; Behari, S; Bellettini, G; Bellinger, J; Benjamin, D; Beretvas, A; Bhatti, A; Binkley, M; Bisello, D; Bizjak, I; Blair, R E; Blocker, C; Blumenfeld, B; Bocci, A; Bodek, A; Boisvert, V; Bortoletto, D; Boudreau, J; Boveia, A; Brau, B; Bridgeman, A; Brigliadori, L; Bromberg, C; Brubaker, E; Budagov, J; Budd, H S; Budd, S; Burkett, K; Busetto, G; Bussey, P; Buzatu, A; Byrum, K L; Cabrera, S; Calancha, C; Camarda, S; Campanelli, M; Campbell, M; Canelli, F; Canepa, A; Carls, B; Carlsmith, D; Carosi, R; Carrillo, S; Carron, S; Casal, B; Casarsa, M; Castro, A; Catastini, P; Cauz, D; Cavaliere, V; Cavalli-Sforza, M; Cerri, A; Cerrito, L; Chang, S H; Chen, Y C; Chertok, M; Chiarelli, G; Chlachidze, G; Chlebana, F; Cho, K; Chokheli, D; Chou, J P; Chung, K; Chung, W H; Chung, Y S; Chwalek, T; Ciobanu, C I; Ciocci, M A; Clark, A; Clark, D; Compostella, G; Convery, M E; Conway, J; Corbo, M; Cordelli, M; Cox, C A; Cox, D J; Crescioli, F; Cuenca Almenar, C; Cuevas, J; Culbertson, R; Cully, J C; Dagenhart, D; Datta, M; Davies, T; de Barbaro, P; De Cecco, S; Deisher, A; De Lorenzo, G; Dell'Orso, M; Deluca, C; Demortier, L; Deng, J; Deninno, M; d'Errico, M; Di Canto, A; di Giovanni, G P; Di Ruzza, B; Dittmann, J R; D'Onofrio, M; Donati, S; Dong, P; Dorigo, T; Dube, S; Ebina, K; Elagin, A; Erbacher, R; Errede, D; Errede, S; Ershaidat, N; Eusebi, R; Fang, H C; Farrington, S; Fedorko, W T; Feild, R G; Feindt, M; Fernandez, J P; Ferrazza, C; Field, R; Flanagan, G; Forrest, R; Frank, M J; Franklin, M; Freeman, J C; Furic, I; Gallinaro, M; Galyardt, J; Garberson, F; Garcia, J E; Garfinkel, A F; Garosi, P; Gerberich, H; Gerdes, D; Gessler, A; Giagu, S; Giakoumopoulou, V; Giannetti, P; Gibson, K; Gimmell, J L; Ginsburg, C M; Giokaris, N; Giordani, M; Giromini, P; Giunta, M; Giurgiu, G; Glagolev, V; Glenzinski, D; Gold, M; Goldschmidt, N; Golossanov, A; Gomez, G; Gomez-Ceballos, G; Goncharov, M; González, O; Gorelov, I; Goshaw, A T; Goulianos, K; Gresele, A; Grinstein, S; Grosso-Pilcher, C; Group, R C; Grundler, U; Guimaraes da Costa, J; Gunay-Unalan, Z; Haber, C; Hahn, S R; Halkiadakis, E; Han, B-Y; Han, J Y; Happacher, F; Hara, K; Hare, D; Hare, M; Harr, R F; Hartz, M; Hatakeyama, K; Hays, C; Heck, M; Heinrich, J; Herndon, M; Heuser, J; Hewamanage, S; Hidas, D; Hill, C S; Hirschbuehl, D; Hocker, A; Hou, S; Houlden, M; Hsu, S-C; Hughes, R E; Hurwitz, M; Husemann, U; Hussein, M; Huston, J; Incandela, J; Introzzi, G; Iori, M; Ivanov, A; James, E; Jang, D; Jayatilaka, B; Jeon, E J; Jha, M K; Jindariani, S; Johnson, W; Jones, M; Joo, K K; Jun, S Y; Jung, J E; Junk, T R; Kamon, T; Kar, D; Karchin, P E; Kato, Y; Kephart, R; Ketchum, W; Keung, J; Khotilovich, V; Kilminster, B; Kim, D H; Kim, H S; Kim, H W; Kim, J E; Kim, M J; Kim, S B; Kim, S H; Kim, Y K; Kimura, N; Kirsch, L; Klimenko, S; Kondo, K; Kong, D J; Konigsberg, J; Korytov, A; Kotwal, A V; Kreps, M; Kroll, J; Krop, D; Krumnack, N; Kruse, M; Krutelyov, V; Kuhr, T; Kulkarni, N P; Kurata, M; Kwang, S; Laasanen, A T; Lami, S; Lammel, S; Lancaster, M; Lander, R L; Lannon, K; Lath, A; Latino, G; Lazzizzera, I; LeCompte, T; Lee, E; Lee, H S; Lee, J S; Lee, S W; Leone, S; Lewis, J D; Lin, C-J; Linacre, J; Lindgren, M; Lipeles, E; Lister, A; Litvintsev, D O; Liu, C; Liu, T; Lockyer, N S; Loginov, A; Lovas, L; Lucchesi, D; Lueck, J; Lujan, P; Lukens, P; Lungu, G; Lys, J; Lysak, R; MacQueen, D; Madrak, R; Maeshima, K; Makhoul, K; Maksimovic, P; Malde, S; Malik, S; Manca, G; Manousakis-Katsikakis, A; Margaroli, F; Marino, C; Marino, C P; Martin, A; Martin, V; Martínez, M; Martínez-Ballarín, R; Mastrandrea, P; Mathis, M; Mattson, M E; Mazzanti, P; McFarland, K S; McIntyre, P; McNulty, R; Mehta, A; Mehtala, P; Menzione, A; Mesropian, C; Miao, T; Mietlicki, D; Miladinovic, N; Miller, R; Mills, C; Milnik, M; Mitra, A; Mitselmakher, G; Miyake, H; Moed, S; Moggi, N; Mondragon, M N; Moon, C S; Moore, R; Morello, M J; Morlock, J; Movilla Fernandez, P; Mülmenstädt, J; Mukherjee, A; Muller, Th; Murat, P; Mussini, M; Nachtman, J; Nagai, Y; Naganoma, J; Nakamura, K; Nakano, I; Napier, A; Nett, J; Neu, C; Neubauer, M S; Neubauer, S; Nielsen, J; Nodulman, L; Norman, M; Norniella, O; Nurse, E; Oakes, L; Oh, S H; Oh, Y D; Oksuzian, I; Okusawa, T; Orava, R; Osterberg, K; Pagan Griso, S; Pagliarone, C; Palencia, E; Papadimitriou, V; Papaikonomou, A; Paramanov, A A; Parks, B; Pashapour, S; Patrick, J; Pauletta, G; Paulini, M; Paus, C; Peiffer, T; Pellett, D E; Penzo, A; Phillips, T J; Piacentino, G; Pianori, E; Pinera, L; Pitts, K; Plager, C; Pondrom, L; Potamianos, K; Poukhov, O; Prokoshin, F; Pronko, A; Ptohos, F; Pueschel, E; Punzi, G; Pursley, J; Rademacker, J; Rahaman, A; Ramakrishnan, V; Ranjan, N; Redondo, I; Renton, P; Renz, M; Rescigno, M; Richter, S; Rimondi, F; Ristori, L; Robson, A; Rodrigo, T; Rodriguez, T; Rogers, E; Rolli, S; Roser, R; Rossi, M; Rossin, R; Roy, P; Ruiz, A; Russ, J; Rusu, V; Rutherford, B; Saarikko, H; Safonov, A; Sakumoto, W K; Santi, L; Sartori, L; Sato, K; Savoy-Navarro, A; Schlabach, P; Schmidt, A; Schmidt, E E; Schmidt, M A; Schmidt, M P; Schmitt, M; Schwarz, T; Scodellaro, L; Scribano, A; Scuri, F; Sedov, A; Seidel, S; Seiya, Y; Semenov, A; Sexton-Kennedy, L; Sforza, F; Sfyrla, A; Shalhout, S Z; Shears, T; Shepard, P F; Shimojima, M; Shiraishi, S; Shochet, M; Shon, Y; Shreyber, I; Simonenko, A; Sinervo, P; Sisakyan, A; Slaughter, A J; Slaunwhite, J; Sliwa, K; Smith, J R; Snider, F D; Snihur, R; Soha, A; Somalwar, S; Sorin, V; Squillacioti, P; Stanitzki, M; St Denis, R; Stelzer, B; Stelzer-Chilton, O; Stentz, D; Strologas, J; Strycker, G L; Suh, J S; Sukhanov, A; Suslov, I; Taffard, A; Takashima, R; Takeuchi, Y; Tanaka, R; Tang, J; Tecchio, M; Teng, P K; Thom, J; Thome, J; Thompson, G A; Thomson, E; Tipton, P; Ttito-Guzmán, P; Tkaczyk, S; Toback, D; Tokar, S; Tollefson, K; Tomura, T; Tonelli, D; Torre, S; Torretta, D; Totaro, P; Tourneur, S; Trovato, M; Tsai, S-Y; Tu, Y; Turini, N; Ukegawa, F; Uozumi, S; van Remortel, N; Varganov, A; Vataga, E; Vázquez, F; Velev, G; Vellidis, C; Vidal, M; Vila, I; Vilar, R; Vogel, M; Volobouev, I; Volpi, G; Wagner, P; Wagner, R G; Wagner, R L; Wagner, W; Wagner-Kuhr, J; Wakisaka, T; Wallny, R; Wang, S M; Warburton, A; Waters, D; Weinberger, M; Weinelt, J; Wester, W C; Whitehouse, B; Whiteson, D; Wicklund, A B; Wicklund, E; Wilbur, S; Williams, G; Williams, H H; Wilson, P; Winer, B L; Wittich, P; Wolbers, S; Wolfe, C; Wolfe, H; Wright, T; Wu, X; Würthwein, F; Yagil, A; Yamamoto, K; Yamaoka, J; Yang, U K; Yang, Y C; Yao, W M; Yeh, G P; Yi, K; Yoh, J; Yorita, K; Yoshida, T; Yu, G B; Yu, I; Yu, S S; Yun, J C; Zanetti, A; Zeng, Y; Zhang, X; Zheng, Y; Zucchelli, S

2010-03-12

We report two complementary measurements of the WW + WZ cross section in the final state consisting of an electron or muon, missing transverse energy, and jets, performed using pp collision data at square root of s = 1.96 TeV collected by the CDF II detector. The first method uses the dijet invariant mass distribution while the second more sensitive method uses matrix-element calculations. The result from the second method has a signal significance of 5.4sigma and is the first observation of WW + WZ production using this signature. Combining the results gives sigma(WW + WZ) = 16.0 +/- 3.3 pb, in agreement with the standard model prediction.

Program SIGMA1 (version 79-1): Doppler broaden evaluated cross sections in the evaluated nuclear data file/version B (ENDF/B) format

International Nuclear Information System (INIS)

Cullen, D.E.

1979-01-01

Program SIGMA1 Doppler-broadens evaluated cross sections in the ENDF/B format. The program requires that input cross sections be tabulated as linearly interpolable functions of energy in ENDF/B File 3; broadened cross sections, in this same form, replace the original values in the output tape. This report describes the methods used in the code and serves as a user's guide. A listing of the source deck is available on request

Evaluation of ETOG-3Q, ETOG-3, FLANGE-II, XLACS, NJOY and LINEAR/RECENT/GROUPIE computer codes concerning to the resonance contribution and background cross sections

International Nuclear Information System (INIS)

Anaf, J.; Chalhoub, E.S.

1988-12-01

The NJOY and LINEAR/RECENT/GROUPIE calculational procedures for the resolved and unresolved resonance contributions and background cross sections are evaluated. Elastic scattering, fission and capture multigroup cross sections generated by these codes and the previously validated ETOG-3Q, ETOG-3, FLANGE-II and XLACS are compared. Constant weighting function and zero Kelvin temperature are considered. Discrepancies are presented and analysed. (author) [pt

Quality assurance guidance for TRUPACT-II [Transuranic Package Transporter-II] payload control

International Nuclear Information System (INIS)

1989-10-01

The Transuranic Package Transporter-II (TRUPACT-II) Safety Analysis Report for Packaging (SARP) approved by the Nuclear Regulatory Commission (NRC), discusses authorized methods for payload control in Appendix 1.3.7 and the Quality Assurance (QA) requirements in Section 9.3. Subsection 9.3.2.1 covers maintenance and use of the TRUPACT-II and the specific QA requirements are given in DOE/WIPP 89-012. Subsection 9.3.2.2 covers payload compliance, for which this document was written. 6 refs

FDA (Food and Drug Administration) Compliance Program Guidance Manual (FY 88). Section 4. Medical and radiological devices

International Nuclear Information System (INIS)

1988-01-01

The FDA Compliance Program Guidance Manual provides a system for issuing and filing program plans and instructions directed to Food and Drug Administration Field operations for project implementation. Section IV provides those chapters of the Compliance Program Guidance Manual which pertain to the areas of medical and radiological devices. Some of the areas of coverage include laser and sunlamp standards inspections, compliance testing of various radiation-emitting products such as television receivers and microwave ovens, emergency response planning and policy, premarket approval and device manufacturers inspections, device problem reporting, sterilization of devices, and consumer education programs on medical and radiological devices

20 CFR 404.1340 - Wage credits for World War II and post-World War II veterans.

Science.gov (United States)

2010-04-01

... 20 Employees' Benefits 2 2010-04-01 2010-04-01 false Wage credits for World War II and post-World War II veterans. 404.1340 Section 404.1340 Employees' Benefits SOCIAL SECURITY ADMINISTRATION FEDERAL... Uniformed Services Amounts of Wage Credits and Limits on Their Use § 404.1340 Wage credits for World War II...

40 CFR 147.3400 - Navajo Indian lands-Class II wells.

Science.gov (United States)

2010-07-01

... to Operate an Underground Injection Control Program under the Safe Drinking Water Act”, October 11... PROGRAMS (CONTINUED) STATE, TRIBAL, AND EPA-ADMINISTERED UNDERGROUND INJECTION CONTROL PROGRAMS Navajo Indian Lands § 147.3400 Navajo Indian lands—Class II wells. The UIC program for Class II injection wells...

Status of the Warm Front End of PIP-II Injector Test

Energy Technology Data Exchange (ETDEWEB)

Shemyakin, Alexander [Fermilab; Alvarez, Matthew [Fermilab; Andrews, Richard [Fermilab; Baffes, Curtis [Fermilab; Carneiro, Jean-Paul [Fermilab; Chen, Alex [Fermilab; Derwent, Paul [Fermilab; Edelen, Jonathan [Fermilab; Frolov, Daniil [Fermilab; Hanna, Bruce [Fermilab; Prost, Lionel [Fermilab; Saewert, Gregory [Fermilab; Saini, Arun [Fermilab; Scarpine, Victor [Fermilab; Sista, V. Lalitha [Fermilab; Steimel, Jim [Fermilab; Sun, Ding [Fermilab; Warner, Arden [Fermilab

2017-05-01

The Proton Improvement Plan II (PIP-II) at Fermilab is a program of upgrades to the injection complex. At its core is the design and construction of a CW-compatible, pulsed H⁻ SRF linac. To validate the concept of the front-end of such machine, a test accelerator known as PIP-II Injector Test is under construction. It includes a 10 mA DC, 30 keV H⁻ ion source, a 2 m-long Low Energy Beam Transport (LEBT), a 2.1 MeV CW RFQ, followed by a Medium Energy Beam Transport (MEBT) that feeds the first of 2 cryomodules increasing the beam energy to about 25 MeV, and a High Energy Beam Transport section (HEBT) that takes the beam to a dump. The ion source, LEBT, RFQ, and initial version of the MEBT have been built, installed, and commissioned. This report presents the overall status of the warm front end.

PACER: a Monte Carlo time-dependent spectrum program for generating few-group diffusion-theory cross sections

International Nuclear Information System (INIS)

Candelore, N.R.; Kerrick, W.E.; Johnson, E.G.; Gast, R.C.; Dei, D.E.; Fields, D.L.

1982-09-01

The PACER Monte Carlo program for the CDC-7600 performs fixed source or eigenvalue calculations of spatially dependent neutron spectra in rod-lattice geometries. The neutron flux solution is used to produce few group, flux-weighted cross sections spatially averaged over edit regions. In general, PACER provides environmentally dependent flux-weighted few group microscopic cross sections which can be made time (depletion) dependent. These cross sections can be written in a standard POX output file format. To minimize computer storage requirements, PACER allows separate spectrum and edit options. PACER also calculates an explicit (n, 2n) cross section. The PACER geometry allows multiple rod arrays with axial detail. This report provides details of the neutron kinematics and the input required

TRUPACT-II Operating and Maintenance Instructions

Energy Technology Data Exchange (ETDEWEB)

Westinghouse Electric Corporation, Waste Isolation Division

1999-12-31

The purpose of this document is to provide the technical requirements for preparation for use, operation, inspection, and maintenance of a Transuranic Package Transporter Model II (TRUPACT-II) Shipping Package and directly related components. This document complies with the minimum requirements as specified in the TRUPACT-II Safety Analysis Report for Packaging (SARP) and Nuclear Regulatory Commission (NRC) Certificate of Compliance (C of C) 9218. In the event there is a conflict between this document and the TRUPACT-II SARP, the TRUPACT-II SARP shall govern. TRUPACT-II C of C number 9218 states, ''... each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application.'' It further states, ''... each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the application.'' Chapter 9 of the TRUPACT-II SARP charges the Westinghouse Electric Corporation Waste Isolation Division (WID) with assuring that the TRUPACT-II is used in accordance with the requirements of the C of C. To meet this requirement and verify consistency of operations when loading and unloading the TRUPACT-II on the trailer, placing a payload in the packaging, unloading the payload from the packaging, or performing maintenance, the U.S. Department of Energy Carlsbad Area Office (U.S. DOE/CAO) finds it necessary to implement the changes that follow. This TRUPACT-II maintenance document represents a change to previous philosophy regarding site specific procedures for the use of the TRUPACT-II. This document details the instructions to be followed to consistently operate and maintain the TRUPACT-II. The intent of these instructions is to ensure that all users of the TRUPACT-II follow the same or equivalent instructions. Users may achieve this intent by any of the following methods: (1

Experimental Engineering Section semiannual progress report, March 1-August 31, 1976. Volume 2. Biotechnology and environmental programs

Energy Technology Data Exchange (ETDEWEB)

Pitt, Jr., W. W.; Mrochek, J. E. [comps.

1978-03-01

This volume contains the progress report of the biotechnology and environmental programs in the Experimental Engineering Section of the Chemical Technology Division. Research efforts in these programs during this report period have been in five areas: (1) environmental research; (2) centrifugal analyzer development; (3) advanced analytical systems development; (4) bioengineering research; and (5) bioengineering development. Summaries of these programmatic areas are contained in Volume I.

75 FR 31738 - Nondiscrimination on the Basis of Age in Programs or Activities Receiving Federal Assistance From...

Science.gov (United States)

2010-06-04

... and Advancement Act Section 12(d) of the National Technology Transfer and Advancement Act of 1995... federally funded program. II. Rulemaking History EPA first proposed regulations implementing the Age... small entities. Small entities include small businesses, small organizations, and small governmental...

User's manual for the NEFTRAN II computer code

International Nuclear Information System (INIS)

Olague, N.E.; Campbell, J.E.; Leigh, C.D.; Longsine, D.E.

1991-02-01

This document describes the NEFTRAN II (NEtwork Flow and TRANsport in Time-Dependent Velocity Fields) computer code and is intended to provide the reader with sufficient information to use the code. NEFTRAN II was developed as part of a performance assessment methodology for storage of high-level nuclear waste in unsaturated, welded tuff. NEFTRAN II is a successor to the NEFTRAN and NWFT/DVM computer codes and contains several new capabilities. These capabilities include: (1) the ability to input pore velocities directly to the transport model and bypass the network fluid flow model, (2) the ability to transport radionuclides in time-dependent velocity fields, (3) the ability to account for the effect of time-dependent saturation changes on the retardation factor, and (4) the ability to account for time-dependent flow rates through the source regime. In addition to these changes, the input to NEFTRAN II has been modified to be more convenient for the user. This document is divided into four main sections consisting of (1) a description of all the models contained in the code, (2) a description of the program and subprograms in the code, (3) a data input guide and (4) verification and sample problems. Although NEFTRAN II is the fourth generation code, this document is a complete description of the code and reference to past user's manuals should not be necessary. 19 refs., 33 figs., 25 tabs

Phase II investigation of the response of columns to short duration loadings: scaling report. Mark I Program, Task 3.2.1. Teledyne report TR-2488(e)

International Nuclear Information System (INIS)

1978-03-01

Phase II of a two-phase column testing program which will determine short-term load capacities for the Mark I containment columns is now under way. The scaling report is submitted to outline the scaling procedures and also to present the scaled quantities such as geometry, load eccentricity, and load time duration. Dimensional analysis and similarity techniques were applied to the experimental models to obtain a set of twelve scaling laws. These scaling laws provide a rational basis for modeling the columns. The scaling laws give nondimensional relationships which are common to both the model and prototype. Parameters which are known to be important in column buckling and which were found to be important during Phase I testing were used as the independent variables in the scaling laws. Column specimens for Phase II testing have been designed to be representative of the prototype columns. Combined bending and compression are characteristic of the Mark I columns with the maximum moment applied at the column-ring girder junction. The experimental columns reflect these characteristics, even though special fixtures and equipment will be required to perform the tests. The column specimens include the scaled rotational stiffness of the ring girder as well as the boundary condition of the pinned or sliding end. To properly incorporate the effects of residual stress, the models will be constructed from ''off-the-shelf', carbon steel pipe and rolled sections, and built-up sections will be fabricated from standard plate. The column geometries scale almost exactly, even though ''replica'' modeling was not used

Syllabus in Trade Electricity-Electronics. Section II. Trade Electricity.

Science.gov (United States)

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

This second section of a three-part syllabus for a flexible curriculum in trade electricity-electronics contains four semi-independent units: (1) Advanced Electricity, (2) Residential and Commercial Wiring, (3) Industrial Electricity, and (4) Motor Controls. Introductory sections describe development of the curriculum, outline the total trade…

KOP program for calculating cross sections of neutron and charged particle interactions with atomic nuclei using the optical model

International Nuclear Information System (INIS)

Grudzevich, O.D.; Zelenetskij, A.V.; Pashchenko, A.B.

1986-01-01

The last version of the KOP program for calculating cross sections of neutron and charged particle interaction with atomic nuclei within the scope of the optical model is described. The structure and program organization, library of total parameters of the optical potential, program identificators and peculiarities of its operation, input of source data and output of calculational results for printing are described in detail. The KOP program is described in Fortran- and adapted for EC-1033 computer

National Waste Terminal Storage Program. Progress report, April 1, 1975--September 30, 1976

International Nuclear Information System (INIS)

1976-01-01

This report is divided into two parts: the Management Report and the Technical Report. Section 1 of the Management Report provides a general National Waste Terminal Storage program overview, which includes a summary of the long-range plan. Part II contains the status reports of the technical projects, facility projects, and systems projects

Cross sections for atmospheric corrections

International Nuclear Information System (INIS)

Meyer, J.P.; Casse, M.; Westergaard, N.

1975-01-01

A set of cross sections for spallation of relativistic nuclei is proposed based on (i) the best available proton cross sections, (ii) an extrapolation to heavier nuclei of the dependence on the number of nucleons lost of the 'target factor' observed for C 12 and O 16 by Lindstrom et al. (1975), in analogy with Rudstam's formalism, and (iii) on a normalization of all cross sections to the total cross sections for production of fragments with Asub(f) >= 6. The obtained cross sections for peripheral interactions are not inconsistent with simple geometrical considerations. (orig.) [de

High temperature turbine technology program. Phase II. Technology test and support studies. Annual technical progress report, January 1, 1979-December 31, 1979

Energy Technology Data Exchange (ETDEWEB)

1980-01-01

Work performed on the High Temperature Turbine Technology Program, Phase II - Technology Test and Support Studies during the period from January 1, 1979 through December 31, 1979 is summarized. Objectives of the program elements as well as technical progress and problems encountered during this Phase II annual reporting period are presented. Progress on design, fabrication and checkout of test facilities and test rigs is described. LP turbine cascade tests were concluded. 350 hours of testing were conducted on the LP rig engine first with clean distillate fuel and then with fly ash particulates injected into the hot gas stream. Design and fabrication of the turbine spool technology rig components are described. TSTR 60/sup 0/ sector combustor rig fabrication and testing are reviewed. Progress in the design and fabrication of TSTR cascade rig components for operation on both distillate fuel and low Btu gas is described. The new coal-derived gaseous fuel synthesizing facility is reviewed. Results and future plans for the supporting metallurgical programs are discussed.

78 FR 17349 - Section 538 Guaranteed Rural Rental Housing Program 2013 Industry Forums-Open Teleconference and...

Science.gov (United States)

2013-03-21

... or via web link. However, if it appears that existing capabilities may prevent the Agency from... program changes on Section 538 financing. USDA prohibits discrimination against its customers, employees..., gender identity, religion, reprisal and where applicable, political beliefs, marital status, familial or...

Heavy-Section Steel Irradiation Program: Volume 3, Progress report, October 1991--September 1992

International Nuclear Information System (INIS)

Corwin, W.R.

1995-02-01

The primary goal of the Heavy-Section Steel Irradiation Program is to provide a thorough, quantitative assessment of the effects of neutron irradiation on the material behavior, and in particular the fracture toughness properties, of typical pressure vessel steels as they relate to light-water reactor pressure-vessel integrity. Effects of specimen size, material chemistry, product form and microstructure, irradiation fluence, flux, temperature and spectrum, and postirradiation annealing are being examined on a wide range of fracture properties. The HSSI Program is arranged into 10 tasks: (1) program management, (2) K Ic curve shift in high-copper welds, (3) K Ia curve shift in high-copper welds, (4) irradiation effects on cladding, (5) K Ic and K Ia curve shifts in low upper-shelf welds, (6) irradiation effects in a commercial low upper-shelf weld, (7) microstructural analysis of irradiation effects, (8) in-service aged material evaluations, (9) correlation monitor materials, and (10) special technical assistance. This report provides an overview of the activities within each of these tasks from October 1991 to September 1992

Dairy Herd Mastitis Program in Argentina: Farm Clusters and Effects on Bulk Milk Somatic Cell Counts

Directory of Open Access Journals (Sweden)

C Vissio1*, SA Dieser2, CG Raspanti2, JA Giraudo1, CI Bogni2, LM Odierno2 and AJ Larriestra1

2013-01-01

Full Text Available This research has been conducted to characterize dairy farm clusters according to mastitis control program practiced among small and medium dairy producer from Argentina, and also to evaluate the effect of such farm cluster patterns on bulk milk somatic cell count (BMSCC. Two samples of 51 (cross-sectional and 38 (longitudinal herds were selected to identify farm clusters and study the influence of management on monthly BMSCC, respectively. The cross-sectional sample involved the milking routine and facilities assessment of each herd visited. Hierarchical cluster analysis was used to find the most discriminating farm attributes in the cross sectional sample. Afterward, the herd cluster typologies were identified in the longitudinal sample. Herd monthly BMSCC average was evaluated during 12 months fitting a linear mixed model. Two clusters were identified, the farms in the Cluster I applied a comprehensive mastitis program in opposite to Cluster II. Post-dipping, dry cow therapy and milking machine test were routinely applied in Cluster I. In the longitudinal study, 14 out of 38 dairy herds were labeled as Cluster I and the rest were assigned to Cluster II. Significant difference in BMSCC was found between cluster I and II (60,000 cells/mL. The present study showed the relevance and potential impact of promoting mastitis control practices among small and medium sized dairy producers in Argentina.

Java-based Graphical User Interface for MAVERIC-II

Science.gov (United States)

Seo, Suk Jai

2005-01-01

A computer program entitled "Marshall Aerospace Vehicle Representation in C II, (MAVERIC-II)" is a vehicle flight simulation program written primarily in the C programming language. It is written by James W. McCarter at NASA/Marshall Space Flight Center. The goal of the MAVERIC-II development effort is to provide a simulation tool that facilitates the rapid development of high-fidelity flight simulations for launch, orbital, and reentry vehicles of any user-defined configuration for all phases of flight. MAVERIC-II has been found invaluable in performing flight simulations for various Space Transportation Systems. The flexibility provided by MAVERIC-II has allowed several different launch vehicles, including the Saturn V, a Space Launch Initiative Two-Stage-to-Orbit concept and a Shuttle-derived launch vehicle, to be simulated during ascent and portions of on-orbit flight in an extremely efficient manner. It was found that MAVERIC-II provided the high fidelity vehicle and flight environment models as well as the program modularity to allow efficient integration, modification and testing of advanced guidance and control algorithms. In addition to serving as an analysis tool for techno logy development, many researchers have found MAVERIC-II to be an efficient, powerful analysis tool that evaluates guidance, navigation, and control designs, vehicle robustness, and requirements. MAVERIC-II is currently designed to execute in a UNIX environment. The input to the program is composed of three segments: 1) the vehicle models such as propulsion, aerodynamics, and guidance, navigation, and control 2) the environment models such as atmosphere and gravity, and 3) a simulation framework which is responsible for executing the vehicle and environment models and propagating the vehicle s states forward in time and handling user input/output. MAVERIC users prepare data files for the above models and run the simulation program. They can see the output on screen and/or store in

Testing the Gossamer Albatross II

Science.gov (United States)

1980-01-01

The Gossamer Albatross II is seen here during a test flight at NASA's Dryden Flight Research Center, Edwards, California. The original Gossamer Albatross is best known for completing the first completely human powered flight across the English Channel on June 12, 1979. The Albatross II was the backup craft for the Channel flight. It was fitted with a small battery-powered electric motor and flight instruments for the NASA research program in low-speed flight. NASA completed its flight testing of the Gossamer Albatross II and began analysis of the results in April, 1980. During the six week program, 17 actual data gathering flights and 10 other flights were flown here as part of the joint NASA Langley/Dryden flight research program. The lightweight craft, carrying a miniaturized instrumentation system, was flown in three configurations; using human power, with a small electric motor, and towed with the propeller removed. Results from the program contributed to data on the unusual aerodynamic, performance, stability, and control characteristics of large, lightweight aircraft that fly at slow speeds for application to future high altitude aircraft. The Albatross' design and research data contributed to numerous later high altitude projects, including the Pathfinder.

Whole-core damage analysis of EBR-II driver fuel elements following SHRT program

International Nuclear Information System (INIS)

Chang, L.K.; Koenig, J.F.; Porter, D.L.

1987-01-01

In the Shutdown Heat Removal Testing (SHRT) program in EBR-II, fuel element cladding temperatures of some driver subassemblies were predicted to exceed temperatures at which cladding breach may occur. A whole-core thermal analysis of driver subassemblies was performed to determine the cladding temperatures of fuel elemnts, and these temperatures were used for fuel element damage calculation. The accumulated cladding damage of fuel element was found to be very small and fuel element failure resulting from SHRT transients is unlikely. No element breach was noted during the SHRT transients. The reactor was immediately restarted after the most severe SHRT transient had been completed and no driver fuel breach has been noted to date. (orig.)

Ultrasonic inspection of heavy section steel components: the PISC II final report

International Nuclear Information System (INIS)

Nichols, R.W.; Crutzen, S.

1988-01-01

This Symposium represented the end of the PISC (Programme for Inspection of Steel Components), II Round Robin Test Project, and the book is the final report. The contents are divided into three parts: part 1 contains contributions from the PISC Management Group, part II contains individual contributions, part III contains views of Licensing Authorities. All the twenty three papers presented in the three parts are selected for INIS and indexed separately. (author)

The PIP-II Conceptual Design Report

Energy Technology Data Exchange (ETDEWEB)

Ball, M. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Burov, A. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Chase, B. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Chakravarty, A. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Chen, A. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Dixon, S. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Edelen, J. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Grassellino, A. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Johnson, D. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Holmes, S. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Kazakov, S. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Klebaner, A. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Kourbanis, I. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Leveling, A. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Melnychuk, O. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Neuffer, D. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Nicol, T. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Ostiguy, J. -F. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Pasquinelli, R. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Passarelli, D. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Ristori, L. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Pellico, W. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Patrick, J. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Prost, L. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Rakhno, I. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Saini, A. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Schappert, W. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Shemyakin, A. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Steimel, J. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Scarpine, V. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Vivoli, A. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Warner, A. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Yakovlev, V. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Ostroumov, P. [Argonne National Lab. (ANL), Argonne, IL (United States); Conway, Z. [Argonne National Lab. (ANL), Argonne, IL (United States)

2017-03-01

The Proton Improvement Plan-II (PIP-II) encompasses a set of upgrades and improvements to the Fermilab accelerator complex aimed at supporting a world-leading neutrino program over the next several decades. PIP-II is an integral part of the strategic plan for U.S. High Energy Physics as described in the Particle Physics Project Prioritization Panel (P5) report of May 2014 and formalized through the Mission Need Statement approved in November 2015. As an immediate goal, PIP-II is focused on upgrades to the Fermilab accelerator complex capable of providing proton beam power in excess of 1 MW on target at the initiation of the Long Baseline Neutrino Facility/Deep Underground Neutrino Experiment (LBNF/DUNE) program, currently anticipated for the mid- 2020s. PIP-II is a part of a longer-term goal of establishing a high-intensity proton facility that is unique within the world, ultimately leading to multi-MW capabilities at Fermilab....

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

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

International Nuclear Information System (INIS)

1993-09-01

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

Hauser-Feshbach cross-section calculations for elastic and inelastic scattering of alpha particles-program CORA

International Nuclear Information System (INIS)

Hartman, A.; Siemaszko, M.; Zipper, W.

1975-01-01

The program CORA was prepared on the basis of Hauser and Feshbach compound reaction formalism. It allows the differential cross-section distributions for the elastic and inelastic scattering of alpha particles (via compound nucleus state) to be calculated. The transmission coefficients are calculated on the basis of a four parameter optical model. The search procedure is also included. (author)

Urban energy management: a course on the administration of public energy programs. An instructor's guide

Energy Technology Data Exchange (ETDEWEB)

Mandelbaum, Dr., Len; Olsen, Dr., Marvin; Hyman, Dr., Barry; Sheridan, Mimi; Dahlberg, Judy; O' Brien, Jeremy

1980-12-01

The course provides local government administrators, staff, and students with the background knowledge to deal with a broad range of energy management concerns and is not to train technical energy conservation specialists. Section II contains the Instructor's Guide and Section III provides the Student Outlines and Handouts on the following subjects: The Energy Problem; National Energy Politics and Programs; State and Local Energy Programs; Techniques of Energy Planning; Techniques of Energy Conservation; Techniques of Renewable Energy Production; Strategies for Voluntary Energy Management; Strategies for Finan. Energy Management; and Strategies for Mandatory Energy Management. (MCW)

Perinatal Na+ Overload Programs Raised Renal Proximal Na+ Transport and Enalapril-Sensitive Alterations of Ang II Signaling Pathways during Adulthood

Science.gov (United States)

Cabral, Edjair V.; Vieira-Filho, Leucio D.; Silva, Paulo A.; Nascimento, Williams S.; Aires, Regina S.; Oliveira, Fabiana S. T.; Luzardo, Ricardo; Vieyra, Adalberto; Paixão, Ana D. O.

2012-01-01

Background High Na+ intake is a reality in nowadays and is frequently accompanied by renal and cardiovascular alterations. In this study, renal mechanisms underlying perinatal Na+ overload-programmed alterations in Na+ transporters and the renin/angiotensin system (RAS) were investigated, together with effects of short-term treatment with enalapril in terms of reprogramming molecular alterations in kidney. Methodology/Principal Findings Male adult Wistar rats were obtained from dams maintained throughout pregnancy and lactation on a standard diet and drinking water (control) or 0.17 M NaCl (saline group). Enalapril (100 mg/l), an angiotensin converting enzyme inhibitor, was administered for three weeks after weaning. Ninety day old offspring from dams that drank saline presented with proximal tubules exhibiting increased (Na++K+)ATPase expression and activity. Ouabain-insensitive Na+-ATPase activity remained unchanged but its response to angiotensin II (Ang II) was lost. PKC, PKA, renal thiobarbituric acid reactive substances (TBARS), macrophage infiltration and collagen deposition markedly increased, and AT2 receptor expression decreased while AT1 expression was unaltered. Early treatment with enalapril reduced expression and activity of (Na++K+)ATPase, partially recovered the response of Na+-ATPase to Ang II, and reduced PKC and PKA activities independently of whether offspring were exposed to high perinatal Na+ or not. In addition, treatment with enalapril per se reduced AT2 receptor expression, and increased TBARS, macrophage infiltration and collagen deposition. The perinatally Na+-overloaded offspring presented high numbers of Ang II-positive cortical cells, and significantly lower circulating Ang I, indicating that programming/reprogramming impacted systemic and local RAS. Conclusions/Significance Maternal Na+ overload programmed alterations in renal Na+ transporters and in its regulation, as well as severe structural lesions in adult offspring. Enalapril

25 CFR 502.3 - Class II gaming.

Science.gov (United States)

2010-04-01

... 25 Indians 2 2010-04-01 2010-04-01 false Class II gaming. 502.3 Section 502.3 Indians NATIONAL INDIAN GAMING COMMISSION, DEPARTMENT OF THE INTERIOR GENERAL PROVISIONS DEFINITIONS OF THIS CHAPTER § 502.3 Class II gaming. Class II gaming means: (a) Bingo or lotto (whether or not electronic, computer...

THE FEASIBILITY OF VILLAGE FOREST PROGRAM IN TANJUNG AUR II VILLAGE, PINO RAYA SUBDISTRICT, SOUTH BENGKULU REGENCY

Directory of Open Access Journals (Sweden)

Desmantoro

2016-08-01

Full Text Available A feasibility study toward the prerequisite conditions is required for the successful implementation of the Village Forest program in Tanjung Aur II Village. This study aims to: 1 identify bio-geophysical conditions of the work area; 2 analyze the conditions of sosioeconomic-cultural society/institutional; 3 analyze the support of stakeholders; and 4 formulate appropriate implementation strategies. The study was using survey method and qualitative studies with multiple analysis techniques. The results showed that: 1 the biogeophysical conditions was eligible and suitable to be proposed as village forest working area; 2 conditions of socio-economic-cultural communities enable to form village forest management institution, through collaboration between state forest encroachers and the villager representatives; 3 stakeholders were ready to provide support facilitation and assistance according to their capacity and capabilities. Key stakeholder were among others BPDAS Ketahun, Dishut Provinsi Bengkulu, Dishut ESDM Bengkulu Selatan, NGOs Ulayat, and officials of the Village; 4 the implementation strategy of village forest program that suitable for Tanjung Aur II was a competitive strategy or diversification (S-T strategy, with the main priority of the strategy, among others by seeking and asking for support from relevant stakeholders or other parties who had capacity and capability to undertake facilitation and assistance.

Electrodril system field test program. Phase II: Task C-1-deep drilling system demonstration. Final report for Phase II: Task C-1

Energy Technology Data Exchange (ETDEWEB)

Taylor, P D

1981-04-01

The Electrodril Deep Drilling System field test demonstrations were aborted in July 1979, due to connector problems. Subsequent post test analyses concluded that the field replacable connectors were the probable cause of the problems encountered. The designs for both the male and female connectors, together with their manufacturing processes, were subsequently modified, as was the acceptance test procedures. A total of nine male and nine female connectors were manufactured and delivered during the 2nd Quarter 1980. Exhaustive testing was then conducted on each connector as a precursor to formal qualification testing conducted during the month of October 1980, at the Brown Oil Tool test facility located in Houston, Texas. With this report, requirements under Phase II, Task C-1 are satisfied. The report documents the results of the connector qualification test program which was successfully completed October 28, 1980. In general, it was concluded that connector qualification had been achieved and plans are now in progress to resume the field test demonstration program so that Electrodril System performance predictions and economic viability can be evaluated.

76 FR 8712 - Section 538 Guaranteed Rural Rental Housing Program 2011 Industry Forums-Open Teleconference and...

Science.gov (United States)

2011-02-15

... existing capabilities may prevent the Agency from accommodating all requests for one form of participation... developments. The impact of Low Income Housing Tax Credits program changes on Section 538 financings. USDA... information, political beliefs, reprisal, or because all or part of an individual's income is derived from any...

Combination of the LEP II ffbar Results

CERN Document Server

Geweniger, C; Elsing, M; Goy, C; Holt, J; Liebig, W; Minard, M N; Renton, P B; Riemann, S; Sachs, K; Ward, P; Wynhoff, S

2002-01-01

Preliminary combinations of measurements of the 4 LEP collaborations of the process e+e-->ffbar at LEP-II are presented, using data from the full LEP-II data set where available. Cross-sections and forward-backward asymmetry measurements are combined for the full LEP-II data set. Combined differential cross-sections $\\frac{{\\rm d}\\sigma}{{\\rm d}\\cos\\theta}$ for electron-pairs, muon pair and tau-pair final states are presented. Measurements of the production of heavy flavours are combined. The combined results are interpreted in terms of contact interactions and the exchange Z' bosons and leptoquarks, and within models of low scale gravity in large extra dimensions.

TJ-II project

International Nuclear Information System (INIS)

Alejaldre, C.; Gozalo, J.J.A.; Perez, J.B.; Magaria, F.C.; Diaz, J.R.C.; Perez, J.G.; Lopez-Fraguas, A.; Garcia, L.; Krivenski, V.I.; Martin, R.; Navarro, A.P.; Perea, A.; Rodriguez-Yunta, A.; Ayza, M.S.; Varias, A.

1990-01-01

The TJ-II device is a medium-size helical-axis stellarator to be built in Madrid. Its main characteristics are potential for high-beta operation; flexibility, i.e., its rotational transform can be varied over a wide range and its shear to some extent; and bean-shaped plasma cross section. The latest understanding of TJ-II physics in the fields of electron cyclotron resonance heating, transport, and magneto-hydrodynamics, and the engineering solutions introduced in its final design are discussed

Program POD; A computer code to calculate nuclear elastic scattering cross sections with the optical model and neutron inelastic scattering cross sections by the distorted-wave born approximation

International Nuclear Information System (INIS)

Ichihara, Akira; Kunieda, Satoshi; Chiba, Satoshi; Iwamoto, Osamu; Shibata, Keiichi; Nakagawa, Tsuneo; Fukahori, Tokio; Katakura, Jun-ichi

2005-07-01

The computer code, POD, was developed to calculate angle-differential cross sections and analyzing powers for shape-elastic scattering for collisions of neutron or light ions with target nucleus. The cross sections are computed with the optical model. Angle-differential cross sections for neutron inelastic scattering can also be calculated with the distorted-wave Born approximation. The optical model potential parameters are the most essential inputs for those model computations. In this program, the cross sections and analyzing powers are obtained by using the existing local or global parameters. The parameters can also be inputted by users. In this report, the theoretical formulas, the computational methods, and the input parameters are explained. The sample inputs and outputs are also presented. (author)

The safe motherhood referral system to reduce cesarean sections and perinatal mortality - a cross-sectional study [1995-2006

Directory of Open Access Journals (Sweden)

Rudge Marilza VC

2011-11-01

Full Text Available Abstract Background In 2000, the eight Millennium Development Goals (MDGs set targets for reducing child mortality and improving maternal health by 2015. Objective To evaluate the results of a new education and referral system for antenatal/intrapartum care as a strategy to reduce the rates of Cesarean sections (C-sections and maternal/perinatal mortality. Methods Design: Cross-sectional study. Setting: Department of Gynecology and Obstetrics, Botucatu Medical School, Sao Paulo State University/UNESP, Brazil. Population: 27,387 delivering women and 27,827 offspring. Data collection: maternal and perinatal data between 1995 and 2006 at the major level III and level II hospitals in Botucatu, Brazil following initiation of a safe motherhood education and referral system. Main outcome measures: Yearly rates of C-sections, maternal (/100,000 LB and perinatal (/1000 births mortality rates at both hospitals. Data analysis: Simple linear regression models were adjusted to estimate the referral system's annual effects on the total number of deliveries, C-section and perinatal mortality ratios in the two hospitals. The linear regression were assessed by residual analysis (Shapiro-Wilk test and the influence of possible conflicting observations was evaluated by a diagnostic test (Leverage, with p Results Over the time period evaluated, the overall C-section rate was 37.3%, there were 30 maternal deaths (maternal mortality ratio = 109.5/100,000 LB and 660 perinatal deaths (perinatal mortality rate = 23.7/1000 births. The C-section rate decreased from 46.5% to 23.4% at the level II hospital while remaining unchanged at the level III hospital. The perinatal mortality rate decreased from 9.71 to 1.66/1000 births and from 60.8 to 39.6/1000 births at the level II and level III hospital, respectively. Maternal mortality ratios were 16.3/100,000 LB and 185.1/100,000 LB at the level II and level III hospitals. There was a shift from direct to indirect causes of

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

Science.gov (United States)

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

2009-01-01

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

ZZ TEMPEST/MUFT, Thermal Neutron and Fast Neutron Multigroup Cross-Section Library for Program LEOPARD

International Nuclear Information System (INIS)

Kim, Jung-Do; Lee, Jong Tai

1986-01-01

Description of problem or function: Format: TEMPEST and MUFT; Number of groups: 246 thermal groups in TEMPEST Format and 54 fast groups in MUFT Format. From this library, the program SPOTS4 generates a 172-54 group library as input to the code LEOPARD. Nuclides: H, O, Zr, C, Fe, Ni, Al, Cr, Mn, U, Pu, Th, Pa, Xe, Sm, B and D. Origin: ENDF/B-4; Weighting spectrum: 1/E + U 235 fission spectrum. Data library of thermal and fast neutron group Cross sections to generate input to the program LEOPARD. The data is based on ENDF/B-4 and consists of two parts: (1) 246 thermal groups in TEMPEST Format. (2) 54 fast groups in MUFT Format. From this library, the program SPOTS4 generates a 172-54 group library as input to the code LEOPARD (NESC0279)

34 CFR 461.46 - What requirements for program reviews and evaluations must be met by a State?

Science.gov (United States)

2010-07-01

... consider the following factors: (i) Projected goals of the recipient as described in its application... section in the year preceding the year for which the data are submitted. (ii) The information required...-administered Workplace Literacy Program (See 34 CFR part 462) and the State-administered English Literacy...

[Atomic Vapor Laser Isotope Separation (AVLIS) program

International Nuclear Information System (INIS)

1992-01-01

This report summarizes work performed for the Atomic Vapor Laser Isotope Separation (AVLIS) program from January through July, 1992. Each of the tasks assigned during this period is described, and results are presented. Section I details work on sensitivity matrices for the UDS relay telescope. These matrices show which combination of mirror motions may be performed in order to effect certain changes in beam parameters. In Section II, an analysis is given of transmission through a clipping aperture on the launch telescope deformable mirror. Observed large transmission losses could not be simulated in the analysis. An EXCEL spreadsheet program designed for in situ analysis of UDS optical systems is described in Section III. This spreadsheet permits analysis of changes in beam first-order characteristics due to changes in any optical system parameter, simple optimization to predict mirror motions needed to effect a combination of changes in beam parameters, and plotting of a variety of first-order data. Optical systems may be assembled directly from OSSD data. A CODE V nonsequential model of the UDS optical system is described in Section IV. This uses OSSD data to build the UDS model; mirror coordinates may thus be verified. Section V summarizes observations of relay telescope performance. Possible procedures which allow more accurate assessment of relay telescope performance are given

MHC class II+ (HLA-DP-like) cells in the cow reproductive tract: II. Immunolocalization of MHC class II+ cells in oviduct and vagina.

Science.gov (United States)

Eren, U; Kum, S; Sandikçi, M; Eren, V; Ilhan, F

2009-08-01

The aim of this study was to determine and examine the distribution of major frequency MHC II+ cells in the oviduct and vagina of cows during the oestrous and dioestrus phases. Right oviduct (ampulla, isthmus) and vaginal samples taken from a total of twenty seven multiparous cows were used. Tissue samples were processed to obtain both cryostat and paraffin sections. Sections were stained immunocytochemically using StreptABC method using a specific monoclonal antibody to MHC II+ cell population. Intra-epithelial and subepithelial areas along with lamina propria, muscularis mucosae and serosa of both ampulla and isthmus and intra-epithelial/subepithelial areas and mucosae of vagina were examined for the presence of MHC II+ cells. The density of immune positive cells was determined using a subjective scoring system. MHC II+ cells were demonstrated in all areas examined in both oestrus and dioestrus. In oestrus, the density of MHC II+ cells decreased in subepithelial areas (in between the epithelial cells and the basal membrane) of isthmus, whereas the density of immune positive cells was increased in muscularis mucosae of isthmus (P < 0.05), lamina propria and muscularis mucosae of ampulla (P < 0.05) as well as in the mucosae of vagina (P II+ cells observed in the oviduct and vagina increases in the majority of areas examined due to the effect of oestrogen.

MINX, Multigroup Cross-Sections and Self-Shielding Factors from ENDF/B for Program SPHINX

International Nuclear Information System (INIS)

Soran, P.D.; MacFarlane, R.E.; Harris, D.R.; LaBauve, R.J.; Hendricks, J.S.; Kidman, R.B.; Weisbin, C.R.; White, J.E.

1977-01-01

1 - Description of problem or function: MINX calculates fine-group averaged infinitely diluted cross sections and self-shielding factors from ENDF/B-IV data. Its primary purpose is to generate a pseudo-composition-independent multigroup library which is input to the SPHINX space-energy collapse program (2) (PSR-0129) through standard CCCC-III (8) interfaces. MINX incorporates and improves upon the resonance capabilities of existing codes such as ETOX (5) (NESC0388) and ENDRUN (9) and the high-order group-to-group transfer matrices of SUPERTOG (10) (PSR-0013) and ETOG (11). Fine group energy boundaries, Legendre expansion order, gross spectral shape component (in the Bondarenko flux model), temperatures and dilutions can all be used specifically. 2 - Method of solution: Infinitely dilute, un-broadened point cross sections are obtained from resolved resonance parameters using a modified version of the RESEND program (3) (NESC0465). The SIGMA1 (4) (IAEA0854) kernel-broadening method is used to Doppler broaden and thin the tabulated linearized pointwise cross sections at 0 K (outside of the unresolved energy region). Effective temperature- dependent self-shielded pointwise cross sections are derived from the formulation in the ETOX code. The primary modification to the ETOX algorithm is associated with the numerical quadrature scheme used to establish the mean values of the fluctuation intervals. The selection of energy mesh points, at which the effective cross sections are calculated, has been modified to include the energy points given in the ENDF/B file or, if the energy-independent formalism was employed, points at half-lethargy intervals. Infinitely dilute group cross sections and self-shielding factors are generated using the Bondarenko flux weighting model with the gross spectral shape under user control. The integral over energy for each group is divided into a set of panels defined by the union of the grid points describing the total cross section, the

Irradiation, annealing, and reirradiation research in the ORNL heavy-section steel irradiation program

International Nuclear Information System (INIS)

Nanstad, R.K.; Iskander, S.K.; McCabe, D.E.; Sokolov, M.A.

1997-01-01

One of the options to mitigate the effects of irradiation on reactor pressure vessels (RPV) is to thermally anneal them to restore the toughness properties that have been degraded by neutron irradiation. This paper summarizes experimental results from work performed as part of the Heavy-Section Steel Irradiation (HSSI) Program managed by Oak Ridge National Laboratory (ORNL) for the U.S. Nuclear Regulatory Commission. The HSSI Program focuses on annealing and re-embrittlement response of materials which are representative of those in commercial RPVs and which are considered to be radiation-sensitive. Experimental studies include (1) the annealing of materials in the existing inventory of previously irradiated materials, (2) reirradiation of previously irradiated/annealed materials in a collaborative program with the University of California, Santa Barbara (UCSB), (3) irradiation/annealing/reirradiation of U.S. and Russian materials in a cooperative program with the Russian Research Center-Kurchatov Institute (RRC-KI), (4) the design and fabrication of an irradiation/anneal/reirradiation capsule and facility for operation at the University of Michigan Ford Reactor, (5) the investigation of potential for irradiation-and/or thermal-induced temper embrittlement in heat-affected zones (HAZs) of RPV steels due to phosphorous segregation at grain boundaries, and (6) investigation of the relationship between Charpy impact toughness and fracture toughness under all conditions of irradiation, annealing, and reirradiation

Historical summary of the heavy-section steel technology program and some related activities in light-water reactor pressure vessel safety research

International Nuclear Information System (INIS)

Whitman, G.D.

1986-03-01

The accomplishments of the Heavy-Section Steel Technology Program and other programs having a close relationship to the development of information used in the assessment of light-water reactor pressure vessel integrity are reviewed. The early Pressure Vessel Research Committee planning, the principals contributing to program formulation, the role of the US Atomic Energy Commission, and the developments under the US Nuclear Regulatory Commission sponsorship are identified. The need for major research and development accomplishments in fracture mechanics, heavy-section steel procurement, materials properties, irradiation effects, fatigue crack growth, and structural testing are summarized. The impact of program results on regulatory issues and the development of data used in the preparation of codes, standards, and guides are discussed. Continuing activities and recommendations for future research and development in support of pressure vessel integrity assessments are presented

Receptor Autoradiography Protocol for the Localized Visualization of Angiotensin II Receptors.

Science.gov (United States)

Linares, Andrea; Couling, Leena E; Carrera, Eduardo J; Speth, Robert C

2016-06-07

This protocol describes receptor binding patterns for Angiotensin II (Ang II) in the rat brain using a radioligand specific for Ang II receptors to perform receptor autoradiographic mapping. Tissue specimens are harvested and stored at -80 °C. A cryostat is used to coronally section the tissue (brain) and thaw-mount the sections onto charged slides. The slide-mounted tissue sections are incubated in (125)I-SI-Ang II to radiolabel Ang II receptors. Adjacent slides are separated into two sets: 'non-specific binding' (NSP) in the presence of a receptor saturating concentration of non-radiolabeled Ang II, or an AT1 Ang II receptor subtype (AT1R) selective Ang II receptor antagonist, and 'total binding' with no AT1R antagonist. A saturating concentration of AT2 Ang II receptor subtype (AT2R) antagonist (PD123319, 10 µM) is also present in the incubation buffer to limit (125)I-SI-Ang II binding to the AT1R subtype. During a 30 min pre-incubation at ~22 °C, NSP slides are exposed to 10 µM PD123319 and losartan, while 'total binding' slides are exposed to 10 µM PD123319. Slides are then incubated with (125)I-SI-Ang II in the presence of PD123319 for 'total binding', and PD123319 and losartan for NSP in assay buffer, followed by several 'washes' in buffer, and water to remove salt and non-specifically bound radioligand. The slides are dried using blow-dryers, then exposed to autoradiography film using a specialized film and cassette. The film is developed and the images are scanned into a computer for visual and quantitative densitometry using a proprietary imaging system and a spreadsheet. An additional set of slides are thionin-stained for histological comparisons. The advantage of using receptor autoradiography is the ability to visualize Ang II receptors in situ, within a section of a tissue specimen, and anatomically identify the region of the tissue by comparing it to an adjacent histological reference section.

Burkina Faso - BRIGHT II

Data.gov (United States)

Millennium Challenge Corporation — Millennium Challenge Corporation hired Mathematica Policy Research to conduct an independent evaluation of the BRIGHT II program. The three main research questions...

Heavy-Section Steel Technology program overview

International Nuclear Information System (INIS)

Pennell, W.E.

1990-01-01

This paper presents a status review of ongoing HSST program tasks aimed at refining the technology used in analysis of reactor pressure vessel fracture margins under pressurized thermal-shock (PTS) loading. Specific fracture-technology issues addressed include vessel flaw density and distribution, shallow flaws, fracture-toughness data transfer, circumferential cracks, ductile tearing and the influence of low-tearing toughness in stainless steel cladding. Preliminary results from the analysis and test programs are presented, together with interim assessments of their potential impact on a reactor vessel PTS analysis. 31 refs., 23 figs., 1 tab

A report on intercomparison studies of computer programs which respectively model: i) radionuclide migration ii) equilibrium chemistry of groundwater

International Nuclear Information System (INIS)

Broyd, T.W.; McD Grant, M.; Cross, J.E.

1985-01-01

This report describes two intercomparison studies of computer programs which respectively model: i) radionuclide migration ii) equilibrium chemistry of groundwaters. These studies have been performed by running a series of test cases with each program and comparing the various results obtained. The work forms a part of the CEC MIRAGE project (MIgration of RAdionuclides in the GEosphere) and has been jointly funded by the CEC and the United Kingdom Department of the Environment. Presentations of the material contained herein were given at plenary meetings of the MIRAGE project in Brussels in March, 1984 (migration) and March, 1985 (equilibrium chemistry) respectively

Simulation of the behaviour of a set of Cu/sub 2/S-CdS unit photocells. [Spice II program

Energy Technology Data Exchange (ETDEWEB)

Jacquemin, J L; Bordure, G

1982-03-01

With the help of a general simulation program (the Spice II program from the University of California, Berkeley), adapted to photocell modeling, authors studied the behavior of a large solar photocell consisting of smaller Cu/sub 2/S-CdS unit solar cells in parallel, in particular, a theoretical set of photocells identical with the best cell made in the laboratory, a set of 30 real photocells characterized individually and the effect of introducing low efficiency cells. The role of each parameter characterizing the photocells is indicated, in order to improve the behavior of photovoltaic panels of larger dimensions. 2 refs.

Heavy-section steel irradiation program. Semiannual progress report, October 1996--March 1997

International Nuclear Information System (INIS)

Rosseel, T.M.

1998-02-01

Maintaining the integrity of the reactor pressure vessel (RPV) in a light-water-cooled nuclear power plant is crucial in preventing and controlling severe accidents that have the potential for major contamination release. Because the RPV is the only key safety-related component of the plant for which a redundant backup system does not exist, it is imperative to fully understand the degree of irradiation-induced degradation of the RPV's fracture resistance that occurs during service. For this reason, the Heavy-Section Steel Irradiation (HSSI) Program has been established. Its primary goal is to provide a thorough, quantitative assessment of the effects of neutron irradiation on the material behavior and, in particular, the fracture toughness properties of typical pressure-vessel steels as they relate to light-water RPV integrity. Effects of specimen size; material chemistry; product form and microstructure; irradiation fluence, flux, temperature, and spectrum; and postirradiation annealing are being examined on a wide range of fracture properties. The HSSI Program is arranged into eight tasks: (1) program management, (2) irradiation effects in engineering materials, (3) annealing, (4) microstructural analysis of radiation effects, (5) in-service irradiated and aged material evaluations, (6) fracture toughness curve shift method, (7) special technical assistance, and (8) foreign research interactions. The work is performed by the Oak Ridge National Laboratory

COXPRO-II: a computer program for calculating radiation and conduction heat transfer in irradiated fuel assemblies

International Nuclear Information System (INIS)

Rhodes, C.A.

1984-12-01

This report describes the computer program COXPRO-II, which was written for performing thermal analyses of irradiated fuel assemblies in a gaseous environment with no forced cooling. The heat transfer modes within the fuel pin bundle are radiation exchange among fuel pin surfaces and conduction by the stagnant gas. The array of parallel cylindrical fuel pins may be enclosed by a metal wrapper or shroud. Heat is dissipated from the outer surface of the fuel pin assembly by radiation and convection. Both equilateral triangle and square fuel pin arrays can be analyzed. Steady-state and unsteady-state conditions are included. Temperatures predicted by the COXPRO-II code have been validated by comparing them with experimental measurements. Temperature predictions compare favorably to temperature measurements in pressurized water reactor (PWR) and liquid-metal fast breeder reactor (LMFBR) simulated, electrically heated fuel assemblies. Also, temperature comparisons are made on an actual irradiated Fast-Flux Test Facility (FFTF) LMFBR fuel assembly

Transport with Astra in TJ-II; Transporte con Astra en TJ-II

Energy Technology Data Exchange (ETDEWEB)

Lopez-Bruna, D; Castejon, F; Fontdecaba, J M

2004-07-01

This report describes the adaptation of the numerical transport shell ASTRA for performing plasma calculations in the TJ-II stellarator device. Firstly, an approximation to the TJ-II geometry is made and a simple transport model is shared with two other codes in order to compare these codes (PROCTR, PRETOR-Stellarator) with ASTRA as calculation tool for TJ-II plasmas are provided: interpretative and predictive transport. The first consists in estimating the transport coefficients from real experimental data, thes being taken from three TJ-II discharges. The predictive facet is illustrated using a model that is able to includes self-consistently thedynamics of transport barriers. The report includes this model, written in the ASTRA programming language, to illustrate the use of ASTRA. (Author) 26 refs.

Factors associated with work ability in patients with chronic whiplash-associated disorder grade II-III: A cross-sectional analysis.

Science.gov (United States)

Agnew, Louise; Johnston, Venerina; Landén Ludvigsson, Maria; Peterson, Gunnel; Overmeer, Thomas; Johansson, Gun; Peolsson, Anneli

2015-06-01

To investigate the factors related to self-perceived work ability in patients with chronic whiplash-associated disorder grades II-III. Cross-sectional analysis. A total of 166 working age patients with chronic whiplash-associated disorder. A comprehensive survey collected data on work ability (using the Work Ability Index); demographic, psychosocial, personal, work- and condition-related factors. Forward, stepwise regression modelling was used to assess the factors related to work ability. The proportion of patients in each work ability category were as follows: poor (12.7%); moderate (39.8%); good (38.5%); excellent (9%). Seven factors explained 65% (adjusted R2 = 0.65, p whiplash-associated disorder.

The Literacy Requirements of an Account Clerk on the Job and in a Vocational Training Program.

Science.gov (United States)

Moe, Alden J.; And Others

As part of a project that identified the specific literacy skills required in ten occupations, this report provides two levels of instructional information about account clerks. Factual data are presented in Parts I and II for use in decision making by program developers, administrators, teachers, and counselors. These sections note the specific…

Heavy-Section Steel Technology Program: Recent developments in crack initiation and arrest research

International Nuclear Information System (INIS)

Pennell, W.E.

1991-01-01

Technology for the analysis of crack initiation and arrest is central to the reactor pressure vessel fracture-margin-assessment process. Regulatory procedures for nuclear plants utilize this technology to assure the retention of adequate fracture-prevention margins throughout the plant operating license period. As nuclear plants age and regulatory procedures dictate that fracture-margin assessments be performed, interest in the fracture-mechanics technology incorporated into those procedures has heightened. This has led to proposals from a number of sources for development and refinement of the underlying crack-initiation and arrest-analysis technology. An important element of the Heavy-Section Steel Technology (HSST) Program is devoted to the investigation and evaluation of these proposals. This paper presents the technological bases and fracture-margin assessment objectives for some of the recently proposed crack-initiation and arrest-technology developments. The HSST Program approach to the evaluation of the proposals is described and the results and conclusions obtained to date are presented

Preliminary Evaluation of the Impact of the Section 1603 Treasury Grant Program on Renewable Energy Deployment in 2009

Energy Technology Data Exchange (ETDEWEB)

Bolinger, Mark; Wiser, Ryan; Darghouth, Naim

2010-03-31

achieve 'the near term goal of creating and retaining jobs - as well as the long-term benefit of expanding the use of clean and renewable energy and decreasing our dependency on non-renewable energy sources' (U.S. Department of the Treasury 2009). More than a year has now passed since the Recovery Act became law. Although the Section 1603 program has been operational for only part of that time - roughly eight months - the program faces a looming milestone in just another nine months. Specifically, in order to qualify for the Section 1603 grant, eligible projects must have commenced construction by the end of 2010. With this deadline approaching, the Committee on Ways and Means of the U.S. House of Representatives requested that Lawrence Berkeley National Laboratory evaluate the effectiveness of the Section 1603 grant program to date (see Attachment 1), focusing on specific elements of the program that were subsequently agreed upon by Committee staff, the U.S. Department of Energy, and Berkeley Lab. This report responds to the Committee's request. The evaluation focuses primarily on the commercial wind power sector, for two reasons: (1) commercial wind power projects had received nearly 86% of all grant money awarded as of March 1, 2010; and (2) there is substantially more market-related information available for the commercial wind power sector than there is for other renewable power sectors, thereby facilitating analysis. Despite the focus on wind power, this initial analysis does endeavor to provide relevant information on other technologies, and in particular geothermal (the second-largest recipient of grant money), where possible.

Computer Program NIKE

DEFF Research Database (Denmark)

Spanget-Larsen, Jens

2014-01-01

FORTRAN source code for program NIKE (PC version of QCPE 343). Sample input and output for two model chemical reactions are appended: I. Three consecutive monomolecular reactions, II. A simple chain mechanism......FORTRAN source code for program NIKE (PC version of QCPE 343). Sample input and output for two model chemical reactions are appended: I. Three consecutive monomolecular reactions, II. A simple chain mechanism...

The Argonne Radiological Impact Program (ARIP). Part II. MONITOR: A Program and Data Base for Retrieval and Utilization of Pollutant Monitoring Data

Energy Technology Data Exchange (ETDEWEB)

Eckerman, Keith F.; Stowe, Ralph F.; Frigerio, Norman A.

1977-02-01

The Argonne Radiological Impact Program (ARIP) is an ongoing project of the Laboratory's Division of Environmental Impact Studies that aims at developing methodologies for assessing the carcinogenic hazards associated with nuclear power development. The project's first report (ANL/ES-26, Part I), published in September.l973, discussed models of radiation carcinogenesis and the contribution of U .. S. background radiation levels to hazardous dose rates. The current report (Part II) treats the storage and access of available data on radiation and radioactivity levels in the u. S. A compute-r code. (the MONITOR program) is prf!sented, which can serve as a ready-access data. bank for all monitoring data acquired over the past two decades. The MONITOR program currently stores data on monitoring locations, types of monitoring efforts, and types of monitoring data. reported in Radiation Data and Reports by the various state and federal ne-tworks; expansion of this data base to include nuclear power facilities in operation or on order is ongoing ·. The MONITOR code retrieves information within a search radius, or rectangl.e ,. circumscribed by parameters of latitude and longitude, and l:.ists or maps the data_as: requested. The code, with examples, is given in full in the report ..

Sample problems for the novice user of the AMPX-II system

International Nuclear Information System (INIS)

Ford, W.E. III; Roussin, R.W.; Petrie, L.M.; Diggs, B.R.; Comolander, H.E.

1979-01-01

Contents of the IBM version of the APMX system distributed by the Radiation Shielding Information Center (APMX-II) are described. Sample problems which demonstrate the procedure for implementing AMPX-II modules to generate point cross sections; generate multigroup neutron, photon production, and photon interaction cross sections for various transport codes; collapse multigroup cross sections; check, edit, and punch multigroup cross sections; and execute a one-dimensional discrete ordinates transport calculation are detailed. 25 figures, 9 tables

Final Report for the MANNRRSS II Program Management of Nevada's Natural Resources with Remote Sensing Systems, Beatty, NV

Energy Technology Data Exchange (ETDEWEB)

Lester Miller; Brian Horowitz; Chris Kratt; Tim Minor; Stephen F. Zitzer; James. V. Taranik; Zan L. Aslett; Todd O. Morken

2009-06-04

This document provides the Final Report on the Management of Nevada’s Natural Resources with Remote Sensing Systems (MANNRRSS) II program. This is a U.S. Department of Energy (DOE)-funded project tasked with utilizing hyperspectral and ancillary electro-optical instrumentation data to create an environmental characterization of an area directly adjacent to the Nevada Test Site (NTS).

20 CFR 404.1342 - Limits on granting World War II and post-World War II wage credits.

Science.gov (United States)

2010-04-01

... 20 Employees' Benefits 2 2010-04-01 2010-04-01 false Limits on granting World War II and post-World War II wage credits. 404.1342 Section 404.1342 Employees' Benefits SOCIAL SECURITY ADMINISTRATION... Uniformed Services Amounts of Wage Credits and Limits on Their Use § 404.1342 Limits on granting World War...

The MMPI-2 Restructured Form Personality Psychopathology Five Scales: bridging DSM-5 Section 2 personality disorders and DSM-5 Section 3 personality trait dimensions.

Science.gov (United States)

Finn, Jacob A; Arbisi, Paul A; Erbes, Christopher R; Polusny, Melissa A; Thuras, Paul

2014-01-01

This study examined in a college sample and a sample of non-treatment-seeking, trauma-exposed veterans the association between the MMPI-2 Restructured Form (MMPI-2-RF) Personality Psychopathology Five (PSY-5) Scales and DSM-5 Section 2 personality disorder (PD) criteria, the same system used in DSM-IV-TR, and the proposed broad personality trait dimensions contained in Section 3 of DSM-5. DSM-5 Section 2 PD symptoms were assessed using the SCID-II-PQ, and applying a replicated rational selection procedure to the SCID-II-PQ item pool, proxies for the DSM-5 Section 3 dimensions and select facets were constructed. The MMPI-2-RF PSY-5 scales demonstrated appropriate convergent and discriminant associations with both Section 2 PDs and Section 3 dimensions in both samples. These findings suggest the MMPI-2-RF PSY-5 scales can serve both conceptually and practically as a bridge between the DSM-5 Section 2 PD criteria and the DSM-5 Section 3 personality features.

The EBR-II materials-surveillance program. 4: Results of SURV-4 and SURV-6

International Nuclear Information System (INIS)

Ruther, W.E.; Hayner, G.O.; Carlson, B.G.; Ebersole, E.R.; Allen, T.R.

1998-01-01

In March of 1965, a set of surveillance (SURV) samples was placed in the EBR-II reactor to determine the effect of irradiation, thermal aging, and sodium corrosion on reactor materials. Eight subassemblies were placed into row 12 positions of EBR-II to determine the effect of irradiation at 370 C. Two subassemblies were placed into the primary sodium basket to determine the effect of thermal aging at 370 C. For both the irradiated and thermally aged samples, one half of all samples were exposed to primary system sodium while one half were sealed in capsules with a helium atmosphere. Fifteen different structural materials were tested in the SURV program. In addition to the fifteen types of metal samples, graphite blocks were irradiated in the SURV subassemblies to determine the effect of irradiation on the graphite neutron shield. In this report, the properties of these materials irradiated at 370 C to a total fluence of 2.2 x 10 22 n/cm 2 (over 2,994 days) are compared with those of similar specimens thermally aged at 370 C for 2,994 days in the storage basket of the reactor. The properties analyzed were weight, density, microstructure, hardness, tensile and yield strength, impact strength, and creep

Program RECENT (version 79-1): reconstruction of energy-dependent neutron cross sections from resonance parameters in the ENDF/B format

International Nuclear Information System (INIS)

Cullen, D.E.

1979-01-01

Program RECENT reconstructs energy-dependent neutron total, elastic, capture, and fission cross sections from a combination of resonance parameters and tabulated background cross sections in the ENDF/B format. Entire evaluations, not just cross sections, are written to the result file, which is in ENDF/B format. The output includes the original resonance parameters in a form that can be used in Doppler broadening and self-shielding calculations. A listing of the source deck is available on request. 5 figures, 5 tables

Wetlands Research Program. Corps of Engineers Wetlands Delineation Manual. Appendix C. Sections 1 and 2. Region 2 - Southeast.

Science.gov (United States)

1987-01-01

22 7.V.: 14 -1b Jil -7 1 N.- .- WETLANDS RESEARCH PROGRAM TECHNICAL REPORT Y-87-1 CORPS OF ENGINEERS WETLANDS DELINEATION MANUAL APPENDIX C SECTIONS ...ARMYLA- US Army Corps of Engineers Washington, DC 20314-1000 B , , , -I *. 4 -w *" APPENDIX C SECTION 1 NATIONAL LIST OF PLANT SPECIES THAT OCCUR IN...Redtop FACW A. hiernalia (Walter) B.S.P. Winter bent FAC A. scabra Wilid. Rough bentgrass FAC A. st~nfyaL. Carpet bentgrass FACW Aletris aurea

The effect of serum angiotensin II and angiotensin II type 1 receptor ...

African Journals Online (AJOL)

Ehab

2012-06-18

Jun 18, 2012 ... case-control cross sectional study which included 24 patients with pLN ..... significantly high levels (1000-fold) of Ang II .... initial validation of the Systemic Lupus International ... Fyhrquist F, Metsärinne K, Tikkanen I. Role of.

Implementing real-time robotic systems using CHIMERA II

Science.gov (United States)

Stewart, David B.; Schmitz, Donald E.; Khosla, Pradeep K.

1990-01-01

A description is given of the CHIMERA II programming environment and operating system, which was developed for implementing real-time robotic systems. Sensor-based robotic systems contain both general- and special-purpose hardware, and thus the development of applications tends to be a time-consuming task. The CHIMERA II environment is designed to reduce the development time by providing a convenient software interface between the hardware and the user. CHIMERA II supports flexible hardware configurations which are based on one or more VME-backplanes. All communication across multiple processors is transparent to the user through an extensive set of interprocessor communication primitives. CHIMERA II also provides a high-performance real-time kernel which supports both deadline and highest-priority-first scheduling. The flexibility of CHIMERA II allows hierarchical models for robot control, such as NASREM, to be implemented with minimal programming time and effort.

Heavy-section steel irradiation program. Semiannual progress report, September 1993--March 1994

International Nuclear Information System (INIS)

Corwin, W.R.

1995-04-01

Maintaining the integrity of the reactor pressure vessel (RPV) in a light-water-cooled nuclear power plant is crucial in preventing and controlling severe accidents that have the potential for major contamination release. The RPV is the only component in the primary pressure boundary for which, if it should rupture, the engineering safety systems cannot assure protection from core damage. It is therefore imperative to understand and be able to predict the capabilities and limitations of the integrity inherent in the RPV. In particular, ft is vital to fully understand the degree of irradiation-induced degradation of the RPV's fracture resistance that occurs during service. The Heavy-Section Steel (HSS) Irradiation Program has been established; its primary goal is to provide a thorough, quantitative assessment of the effects of neutron irradiation on the material behavior, and in particular the fracture toughness properties of typical pressure-vessel steels, as they relate to light-water RPV integrity. The program includes the direct continuation of irradiation studies previously conducted within the HSS Technology Program augmented by enhanced examinations of the accompanying microstructural changes. During this period, the report on the duplex-type crack-arrest specimen tests from Phase 11 of the K la program was issued, and final preparations for testing the large, irradiated crack-arrest specimens from the Italian Committee for Research and Development of Nuclear Energy and Alternative Energies were completed. Tests on undersize Charpy V-notch (CVN) energy specimens in the irradiated and annealed weld 73W were completed. The results are described in detail in a draft NUREG report. In addition, the ORNL investigation of the embrittlement of the High Flux Isotope RPV indicated that an unusually large ratio of the high-energy gamma-ray flux to fast-neutron flux is most likely responsible for the apparently accelerated embrittlement

Summary report of Japan-US joint project. JUPITER-II. FuY 2001 - 2006

International Nuclear Information System (INIS)

Abe, K.; Kohyama, A.; Tanaka, S.; Muroga, T.; Namba, C.; Sze, D.K.

2008-03-01

This report summarizes the scientific accomplishments achieved through the JUPITER-II Japan-US Collaboration Program. The JUPITER-II collaboration (Japan-USA Program of Irradiation/Integration Test for Fusion Research -II) has been carried out through six years (2001-2006) under Phase 4 of the collaboration implemented by Amendment 4 of Annex I to the MEXT (Ministry of Education, Culture, Sports, Science and Technology)-DOE (United States Department of Energy) Cooperation. This program followed the RTNS-II Program (Phase 1: 1982-1986), the FFTF/MOTA Program (Phase 2: 1987-1994) and the JUPITER Program (Phase 3: 1995-2000). The JUPITER-II collaboration was established to provide the scientific foundations for understanding the integrated behavior of blanket materials combinations operating under conditions characteristic of fusion reactors, including interactive neutron irradiation effects, high temperature coolant flow phenomena, heat and mass transport in blanket materials, and coolant chemistry and its interactions with surrounding materials. The scientific concept of this program is to study the key technology in macroscopic system integration for advanced blanket based on an understanding of the relevant mechanics at the microscopic level. The 44 of the presented papers are indexed individually. (J.P.N.)

Comparing Mixed & Integer Programming vs. Constraint Programming by solving Job-Shop Scheduling Problems

Directory of Open Access Journals (Sweden)

Renata Melo e Silva de Oliveira

2015-03-01

Full Text Available Scheduling is a key factor for operations management as well as for business success. From industrial Job-shop Scheduling problems (JSSP, many optimization challenges have emerged since de 1960s when improvements have been continuously required such as bottlenecks allocation, lead-time reductions and reducing response time to requests.  With this in perspective, this work aims to discuss 3 different optimization models for minimizing Makespan. Those 3 models were applied on 17 classical problems of examples JSSP and produced different outputs.  The first model resorts on Mixed and Integer Programming (MIP and it resulted on optimizing 60% of the studied problems. The other models were based on Constraint Programming (CP and approached the problem in two different ways: a model CP1 is a standard IBM algorithm whereof restrictions have an interval structure that fail to solve 53% of the proposed instances, b Model CP-2 approaches the problem with disjunctive constraints and optimized 88% of the instances. In this work, each model is individually analyzed and then compared considering: i Optimization success performance, ii Computational processing time, iii Greatest Resource Utilization and, iv Minimum Work-in-process Inventory. Results demonstrated that CP-2 presented best results on criteria i and ii, but MIP was superior on criteria iii and iv and those findings are discussed at the final section of this work.

Design concepts for PBFA-II's applied-B ion diode

International Nuclear Information System (INIS)

Rovang, D.C.

1985-01-01

The lithium ion diode to be used at the center of Particle Beam Fusion Accelerator-II (PBFA-II) at Sandia National Laboratories is an applied-B ion diode. The center section of the PBFA-II accelerator is where the electrical requirements of the accelerator, the design requirements of the diode, and the operational requirements must all be satisfied simultaneously for a successful experiment. From an operational standpoint, the ion diode is the experimental hub of the accelerator and needs to be easily and quickly installed and removed. Because of the physical size and geometry of the PBFA-II center section, achieving the operational requirements has presented an interesting design challenge. A discussion of the various design requirements and the proposed concepts for satisfying them is presented

Integrated data base program

International Nuclear Information System (INIS)

Notz, K.J.

1981-01-01

The IDB Program provides direct support to the DOE Nuclear Waste Management and Fuel Cycle Programs and their lead sites and support contractors by providing and maintaining a current, integrated data base of spent fuel and radioactive waste inventories and projections. All major waste types (HLW, TRU, and LLW) and sources (government, commerical fuel cycle, and I/I) are included. A major data compilation was issued in September, 1981: Spent Fuel and Radioactive Waste Inventories and Projections as of December 31, 1980, DOE/NE-0017. This report includes chapters on Spent Fuel, HLW, TRU Waste, LLW, Remedial Action Waste, Active Uranium Mill Tailings, and Airborne Waste, plus Appendices with more detailed data in selected areas such as isotopics, radioactivity, thermal power, projections, and land usage. The LLW sections include volumes, radioactivity, thermal power, current inventories, projected inventories and characteristics, source terms, land requirements, and a breakdown in terms of government/commercial and defense/fuel cycle/I and I

Development of advanced blanket performance under irradiation and system integration through JUPITER-II project

Energy Technology Data Exchange (ETDEWEB)

Abe, Katsunori; Kohyama, Akira; Tanaka, Satoru; Namba, C.; Terai, T.; Kunugi, T.; Muroga, Takeo; Hasegawa, Akira; Sagara, A.; Berk, S.; Zinkle, Steven J.; Sze, Dai Kai; Petti, D. A.; Abdou, Mohamed A.; Morley, Neil B.; Kurtz, Richard J.; Snead, Lance L.; Ghoniem, Nasr M.

2008-12-01

This report describes an outline of the activities of the JUPITER-II collaboration (japan-USA program of Irradiation/Integration test for Fusion Research-II), Which has bee carried out through six years (2001-2006) under Phase 4 of the collabroation implemented by Amendment 4 of Annex 1 to the DOE (United States Department of Energy)-MEXT (Ministry of Education ,Culture,Sports,Science and Technology) Cooperation. This program followed the RTNS-II Program (Phase1:1982-4986), the FFTF/MOTA Program (Phase2:1987-1994) and the JUPITER Program (Phase 3: 1995-2000) [1].

The effect on cross sections for Quad Cities by introducing control rod history in the assembly program LEWARD

International Nuclear Information System (INIS)

Nonboel, E.

1989-08-01

This paper shows the effect on the 2-group neutron cross sections for the BWR reactor Quad Cities by introducing control rod ''history'' in the assembly program LEWARD. Control rod ''history'' is a concept which accounts for the movement of control rods during operation. (author)

78 FR 40084 - Proposed Requirement-Migrant Education Program Consortium Incentive Grant Program

Science.gov (United States)

2013-07-03

... DEPARTMENT OF EDUCATION 34 CFR Chapter II Proposed Requirement--Migrant Education Program... educational agencies (SEAs) under the Migrant Education Program (MEP) Consortium Incentive Grant (CIG) Program... the interstate or intrastate coordination of migrant education programs by addressing key needs of...

RTNS-II irradiations and operations

International Nuclear Information System (INIS)

Logan, C.M.; Heikkinen, D.W.

1982-01-01

The objectives of this work are operation of RTNS-II (a 14-MeV neutron source facility), machine development, and support of the experimental program that utilizes this facility. Experimenter services include dosimetry handling, scheduling, coordination, and reporting. RTNS-II is dedicated to materials research for the fusion power program. Its primary use is to aid in the development of models of high-energy neutron effects. Such models are needed in interpreting and projecting to the fusion environment engineering data obtained in other neutron spectra. Irradiations were performed for a total of twenty-nine different experimenters during this quarter. A JOEL 200 CX TEM and other post-irradiation test equipment have been installed

DART II documentation. Volume III. Appendices

Energy Technology Data Exchange (ETDEWEB)

1979-10-01

The DART II is a remote, interactive, microprocessor-based data acquistion system suitable for use with air monitors. This volume of DART II documentation contains the following appendixes: adjustment and calibration procedures; mother board signature list; schematic diagrams; device specification sheets; ROM program listing; 6800 microprocessor instruction list, octal listing; and cable lists. (RWR)

Section 1. Confinement systems

International Nuclear Information System (INIS)

Anon.

1975-01-01

Major experimental and theoretical results achieved by the Controlled Thermonuclear Research (CTR) program at Lawrence Livermore Laboratory during FY 1975 gave the greatest encouragement to date that the ultimate goal of a deuterium-tritium-fueled mirror reactor can be reached. In the experimental program, the year was characterized by unusually important physics results from the 2XIIB experiment and by significant steps in the plan to change the Baseball II mode of operation. The stabilization of ion-cyclotron instabilities in the 2XIIB experiment by the introduction of an auxiliary warm plasma permitted the buildup of a high-temperature, high-density plasma with an n tau parameter an order of magnitude larger than the 2XII experiment.I In the Baseball II experiment, preliminary tests and computer predictions indicated that a dense, transient, target plasma can be created by laser irradiation of a pellet in midflight through the center of the Baseball confinement zone

Displacement cross sections and PKA spectra: tables and applications

International Nuclear Information System (INIS)

Doran, D.G.; Graves, N.J.

1976-12-01

Damage energy cross sections to 20 MeV are given for aluminum, vanadium, chromium, iron, nickel, copper, zirconium, niobium, molybdenum, tantalum, tungsten, lead, and 18Cr10Ni stainless steel. They are based on ENDF/B-IV nuclear data and the Lindhard energy partition model. Primary knockon atom (PKA) spectra are given for aluminum, iron, niobium, tantalum, and lead for neutron energies up to 15 MeV at approximately one-quarter lethargy intervals. The contributions of various reactions to both the displacement cross sections (taken to be proportional to the damage energy cross sections) and the PKA spectra are presented graphically. Spectral-averaged values of the displacement cross sections are given for several spectra, including approximate maps for the Experimental Breeder Reactor-II (EBR-II) and several positions in the Fast Test Reactor (FTR). Flux values are included to permit estimation of displacement rates. Graphs show integral PKA spectra for the five metals listed above for neutron spectra corresponding to locations in the EBR-II, the High Flux Isotope Reactor (HFIR), and a conceptual fusion reactor (UWMAK-I). Detailed calculations are given only for cases not previously documented. Uncertainty estimates are included

Assembling the Gossamer Albatross II in hangar

Science.gov (United States)

1980-01-01

The Gossamer Albatross II is seen here being assembled in a hangar at the Dryden Flight Research Center, Edwards, California. The original Gossamer Albatross is best known for completing the first completely human powered flight across the English Channel on June 12, 1979. The Albatross II was the backup craft for the Channel flight. The aircraft was fitted with a small battery-powered electric motor and flight instruments for the NASA research program in low-speed flight. NASA completed its flight testing of the Gossamer Albatross II and began analysis of the results in April, 1980. During the six week program, 17 actual data gathering flights and 10 other flights were flown here as part of the joint NASA Langley/Dryden flight research program. The lightweight craft, carrying a miniaturized instrumentation system, was flown in three configurations; using human power, with a small electric motor, and towed with the propeller removed. Results from the program contributed to data on the unusual aerodynamic, performance, stability, and control characteristics of large, lightweight aircraft that fly at slow speeds for application to future high altitude aircraft. The Albatross' design and research data contributed to numerous later high altitude projects, including the Pathfinder.

Comparing the dependability and associations with functioning of the DSM-5 Section III trait model of personality pathology and the DSM-5 Section II personality disorder model.

Science.gov (United States)

Chmielewski, Michael; Ruggero, Camilo J; Kotov, Roman; Liu, Keke; Krueger, Robert F

2017-07-01

Two competing models of personality psychopathology are included in the fifth edition of the Diagnostic Statistical Manual of Mental Disorders ( DSM-5 ; American Psychiatric Association, 2013); the traditional personality disorder (PD) model included in Section II and an alternative trait-based model included in Section III. Numerous studies have examined the validity of the alternative trait model and its official assessment instrument, the Personality Inventory for DSM-5 (PID-5; Krueger, Derringer, Markon, Watson, & Skodol, 2012). However, few studies have directly compared the trait-based model to the traditional PD model empirically in the same dataset. Moreover, to our knowledge, only a single study (Suzuki, Griffin, & Samuel, 2015) has examined the dependability of the PID-5, which is an essential component of construct validity for traits (Chmielewski & Watson, 2009; McCrae, Kurtz, Yamagata, & Terracciano, 2011). The current study directly compared the dependability of the DSM-5 traits, as assessed by the PID-5, and the traditional PD model, as assessed by the Personality Diagnostic Questionnaire-4 (PDQ-4+), in a large undergraduate sample. In addition, it evaluated and compared their associations with functioning, another essential component of personality pathology. In general, our findings indicate that most DSM-5 traits demonstrate high levels of dependability that are superior to the traditional PD model; however, some of the constructs assessed by the PID-5 may be more state like. The models were roughly equivalent in terms of their associations with functioning. The current results provide additional support for the validity of PID-5 and the DSM-5 Section III personality pathology model. (PsycINFO Database Record (c) 2017 APA, all rights reserved).

Three-section expiratory CT

DEFF Research Database (Denmark)

Loeve, Martine; de Bruijne, Marleen; Hartmann, Ieneke C. J.

2012-01-01

. Longitudinal follow-up was performed with three sections. All images were deidentified and randomized, and TA was scored with the Brody II system and a new quantitative system. Statistical analysis included the Wilcoxon signed rank test, calculation of Spearman and intraclass correlation coefficients, and use......Purpose: To estimate the effect of the number of computed tomography (CT) sections on trapped air (TA) assessment in patients with cystic fibrosis (CF) by using an established scoring system and a new quantitative scoring system and to compare CT and pulmonary function test (PFT) estimates of TA...

Examining the DSM-5 Section III Criteria for Obsessive-Compulsive Personality Disorder in a Community Sample.

Science.gov (United States)

Liggett, Jacqueline; Sellbom, Martin; Carmichael, Kieran L C

2017-12-01

The current study examined the extent to which the trait-based operationalization of obsessive-compulsive personality disorder (OCPD) in Section III of the DSM-5 describes the same construct as the one described in Section II. A community sample of 313 adults completed a series of personality inventories indexing the DSM-5 Sections II and III diagnostic criteria for OCPD, in addition to a measure of functional impairment modelled after the criteria in Section III. Results indicated that latent constructs representing Section II and Section III OCPD overlapped substantially (r = .75, p OCPD variable. Further, Anxiousness and (low) Impulsivity, as well as self and interpersonal impairment, augmented the prediction of latent OCPD scores.

PODESY program for flux mapping of CNA II reactor:

International Nuclear Information System (INIS)

Ribeiro Guevara, Sergio

1988-01-01

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

Integrated Data Collection Analysis (IDCA) Program - RDX Type II Class 5 Standard, Data Set 1

Energy Technology Data Exchange (ETDEWEB)

Sandstrom, Mary M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Brown, Geoffrey W. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Preston, Daniel N. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Pollard, Colin J. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Warner, Kirstin F. [Naval Surface Warfare Center (NSWC), Indian Head, MD (United States). Indian Head Division; Sorenson, Daniel N. [Naval Surface Warfare Center (NSWC), Indian Head, MD (United States). Indian Head Division; Remmers, Daniel L. [Naval Surface Warfare Center (NSWC), Indian Head, MD (United States). Indian Head Division; Moran, Jesse S. [Naval Surface Warfare Center (NSWC), Indian Head, MD (United States). Indian Head Division; Shelley, Timothy J. [Air Force Research Lab. (AFRL), Tyndall AFB, FL (United States); Reyes, Jose A. [Applied Research Associates, Inc., Tyndall AFB, FL (United States); Hsu, Peter C. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Whipple, Richard E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Reynolds, John G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2011-04-11

This document describes the results of the first reference sample material—RDX Type II Class 5—examined in the proficiency study for small-scale safety and thermal (SSST) testing of explosive materials for the Integrated Data Collection Analysis (IDCA) Program. The IDCA program is conducting proficiency testing on homemade explosives (HMEs). The reference sample materials are being studied to establish the accuracy of traditional explosives safety testing for each performing laboratory. These results will be used for comparison to results from testing HMEs. This effort, funded by the Department of Homeland Security (DHS), ultimately will put the issues of safe handling of these materials in perspective with standard military explosives. The results of the study will add SSST testing results for a broad suite of different HMEs to the literature, potentially suggest new guidelines and methods for HME testing, and possibly establish what are the needed accuracies in SSST testing to develop safe handling practices. Described here are the results for impact, friction, electrostatic discharge, and scanning calorimetry analysis of a reference sample of RDX Type II Class 5. The results from each participating testing laboratory are compared using identical test material and preparation methods wherever possible. Note, however, the test procedures differ among the laboratories. These results are then compared to historical data from various sources. The performers involved are Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Air Force Research Laboratory/ RXQL (AFRL), Indian Head Division, Naval Surface Warfare Center, (IHD-NSWC), and Sandia National Laboratories (SNL). These tests are conducted as a proficiency study in order to establish some consistency in test protocols, procedures, and experiments and to understand how to compare results when test protocols are not identical.

Community energy auditing: experience with the comprehensive community energy management program

Energy Technology Data Exchange (ETDEWEB)

Moore, J.L.; Berger, D.A.; Rubin, C.B.; Hutchinson, P.A. Sr.; Griggs, H.M.

1980-09-01

The report provides local officials and staff with information on lessons from the audit, projection, and general planning experiences of the Comprehensive Community Energy Management Program (CCEMP) communities and provides ANL and US DOE with information useful to the further development of local energy management planning methods. In keeping with the objectives, the report is organized into the following sections: Section II presents the evaluation issues and key findings based on the communities' experiences from Spring of 1979 to approximately March of 1980; Section III gives an organized review of experience of communities in applying the detailed audit methodology for estimating current community energy consumption and projecting future consumption and supply; Section IV provides a preliminary assessment of how audit information is being used in other CCEMP tasks; Section V presents an organized review of preliminary lessons from development of the community planning processes; and Section VI provides preliminary conclusions on the audit and planning methodology. (MCW)

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

Clean Water Act Section 319 Nonpoint Source Pollution Control Projects Grants, US EPA Region 9, 2008, California Nonpoint Source Program

Data.gov (United States)

U.S. Environmental Protection Agency — The California Nonpoint Source (NPS) Program allocates about $4.5 million of CWA Section 319 funding from the U.S. Environmental Protection Agency annually to...

Digital optical computer II

Science.gov (United States)

Guilfoyle, Peter S.; Stone, Richard V.

1991-12-01

OptiComp is currently completing a 32-bit, fully programmable digital optical computer (DOC II) that is designed to operate in a UNIX environment running RISC microcode. OptiComp's DOC II architecture is focused toward parallel microcode implementation where data is input in a dual rail format. By exploiting the physical principals inherent to optics (speed and low power consumption), an architectural balance of optical interconnects and software code efficiency can be achieved including high fan-in and fan-out. OptiComp's DOC II program is jointly sponsored by the Office of Naval Research (ONR), the Strategic Defense Initiative Office (SDIO), NASA space station group and Rome Laboratory (USAF). This paper not only describes the motivational basis behind DOC II but also provides an optical overview and architectural summary of the device that allows the emulation of any digital instruction set.

Cervical Muscle Dysfunction in the Chronic Whiplash Associated Disorder Grade II (WAD-II)

NARCIS (Netherlands)

Nederhand, Marcus Johannes; IJzerman, Maarten Joost; Hermens, Hermanus J.; Baten, Christian T.M.; Zilvold, Gerrit

2000-01-01

Study Design: In a cross-sectional study, surface electromyography measurements of the upper trapezius muscles were obtained during different functional tasks in patients with a chronic whiplash associated disorder Grade II and healthy control subjects. - Objectives: To investigate whether muscle

Lunar Health Monitor, Phase II

Data.gov (United States)

National Aeronautics and Space Administration — During the Phase II Lunar Health Monitor program, Orbital Research will develop a second generation wearable sensor suite for astronaut physiologic monitoring. The...

The PIP-II Reference Design Report

Energy Technology Data Exchange (ETDEWEB)

Lebedev, Valeri, [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); et al.

2015-06-01

The Proton Improvement Plan-II (PIP-II) is a high-intensity proton facility being developed to support a world-leading neutrino program over the next two decades at Fermilab. PIP-II is an integral part of the U.S. Intensity Frontier Roadmap as described in the Particle Physics Project Prioritization Panel (P5) report of May 2014 [1]. As an immediate goal PIP-II is focused on upgrades to the Fermilab accelerator complex capable of providing a beam power in excess of 1 MW on target at the initiation of LBNF [1,2] operations. PIP-II is a part of a longer-term concept for a sustained campaign of upgrades and improvements to achieve multi-MW capabilities at Fermilab. PIP-II is based on three major thrusts. They are (1) the recently completed upgrades to the Recycler and Main Injector (MI) for the NOvA experiment, (2) the Proton Improvement Plan [3] currently underway, and (3) the Project X Reference Design [4]. Note that: The Proton Improvement Plan (PIP) consolidates a set of improvements to the existing Linac, Booster, and Main Injector (MI) aimed at supporting 15 Hz Booster beam operation. In combination, the NOvA upgrades and PIP create a capability of delivering 700 kW beam power from the Main Injector at 120 GeV; The scope of the Project X Reference Design Report was aimed well beyond PIP. It described a complete concept for a multi-MW proton facility that could support a broad particle physics program based on neutrino, kaon, muon, and nucleon experiments [5,6]. The Project X conceptual design has evolved over a number of years, incorporating continuous input on physics research goals and advances in the underlying technology development programs [7,8,9]. PIP-II, to high degree, inherits these goals as the goals for future developments and upgrades. This document (PIP-II Reference Design Report) describes an initial step in the development of the Fermilab accelerating complex. The plan described in this Report balances the far-term goals of the Laboratory

Review of Section XI inservice inspection program effectiveness

International Nuclear Information System (INIS)

Cook, J.F. Sr.

1993-08-01

To evaluate the effectiveness of Section XI, Division 1, open-quotes Rules for Inservice Inspection of Nuclear Power Plant Components,close quotes of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, searches were performed of the Licensing Event Report and Nuclear Plant Reliability Data System computerized data bases, and a review was made of inservice inspection summary reports. It was found that the Section XI examinations and tests detect flaws in welds and plant components and result in subsequent corrective action. This study also shows that the format and topics of information provided in Section XI-prescribed inservice inspection summary reports vary widely

Review of Section XI inservice inspection program effectiveness

Energy Technology Data Exchange (ETDEWEB)

Cook, J.F. Sr.

1993-08-01

To evaluate the effectiveness of Section XI, Division 1, {open_quotes}Rules for Inservice Inspection of Nuclear Power Plant Components,{close_quotes} of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, searches were performed of the Licensing Event Report and Nuclear Plant Reliability Data System computerized data bases, and a review was made of inservice inspection summary reports. It was found that the Section XI examinations and tests detect flaws in welds and plant components and result in subsequent corrective action. This study also shows that the format and topics of information provided in Section XI-prescribed inservice inspection summary reports vary widely.

Report to the U.S. Congress on the Outcomes of the Nonmotorized Transportation Pilot Program SAFETEA-LU Section 1807

Science.gov (United States)

2012-04-30

Section 1807 of the Safe, Accountable, Flexible Efficient Transportation Equity Act: A Legacy for Users : (SAFETEA-LU) P.L. 109-59 established the Nonmotorized Transportation Pilot Program (NTPP) in : August 2005. Over the span of 4 years, the NTPP p...

1992 Resource Program, 10 Year Plan : Draft II.

Energy Technology Data Exchange (ETDEWEB)

United States. Bonneville Power Administration.

1992-05-01

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

1992 Resource Program, 10 Year Plan : Draft II.

Energy Technology Data Exchange (ETDEWEB)

United States. Bonneville Power Administration.

1992-05-01

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

The CDF SVX II upgrade for the Tevatron Run II

International Nuclear Information System (INIS)

Bortoletto, Daniela

1997-01-01

A microstrip silicon detector SVX II has been proposed for the upgrade of CDF to be installed in 1999 for Run II of the Tevatron. Three barrels of five layers of double-sided silicon microstrip detectors will cover the interaction region. A description of the project status will be presented. Emphasis will be given to the R and D program for silicon sensors which includes capacitance minimization, the study of coupling capacitor integrity, the operation of the detectors in conjunction with the SVXH and SVX2 readout chips in two beam tests and the determination of the detectors performance deterioration due to radiation damage

Graphics gems II

CERN Document Server

Arvo, James

1991-01-01

Graphics Gems II is a collection of articles shared by a diverse group of people that reflect ideas and approaches in graphics programming which can benefit other computer graphics programmers.This volume presents techniques for doing well-known graphics operations faster or easier. The book contains chapters devoted to topics on two-dimensional and three-dimensional geometry and algorithms, image processing, frame buffer techniques, and ray tracing techniques. The radiosity approach, matrix techniques, and numerical and programming techniques are likewise discussed.Graphics artists and comput

Differential electron scattering cross sections for the 3 (2)S to 3 (2)P0 h, k transitions in Mg II - Comparison of experiment and theory

Science.gov (United States)

Williams, I. D.; Chutjian, A.; Msezane, A. Z.; Henry, R. J. W.

1985-01-01

Angular differential electron scattering cross sections are reported for the unresolved inelastic 3s (2)S to 3p (2)P0 h, k transitions in Mg II for the first time. Relative differential cross sections have been measured at 35 eV and 50 eV in the angular range of Theta between 6 and 17 deg using the newly developed electron energy loss technique in a crossed electron-ion beam geometry. Theoretical values have been calculated in a five-state close-coupling approximation in which 3s, 3p, 3d, 4s, and 4p states were included, and to which measurements were normalized at Theta = 12 deg.

FORTRAN 4 programs for the extraction of potential well parameters from the energy dependence of total elastic scattering cross sections

Science.gov (United States)

Labudde, R. A.

1972-01-01

An attempt has been made to keep the programs as subroutine oriented as possible. Usually only the main programs are directly concerned with the problem of total cross sections. In particular the subroutines POLFIT, BILINR, GASS59/MAXLIK, SYMOR, MATIN, STUDNT, DNTERP, DIFTAB, FORDIF, EPSALG, REGFAL and ADSIMP are completely general, and are concerned only with the problems of numerical analysis and statistics. Each subroutine is independently documented.

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

International Nuclear Information System (INIS)

1981-10-01

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

Artificial heart development program. Volume II. System support. Phase III summary report, July 1, 1973--September 30, 1977

International Nuclear Information System (INIS)

1977-01-01

Volume 2 covers major activities of the Artificial Heart Development program that supported the design, fabrication, and test of the system demonstration units. Section A.1.0 provides a listing beyond that of the body of the report on the components needed for an implantation. It also presents glove box sterilization calibration results and results of an extensive mock circulation calibration. Section A.2.0 provides detailed procedures for assembly, preparing for use, and the use of the system and major components. Section A.3.0 covers the component research and development activities undertaken to improve components of the existing system units and to prepare for a future prototype system. Section A.4.0 provides a listing of the top assembly drawings of the major systems variations fabricated and tested

Artificial heart development program. Volume II. System support. Phase III summary report, July 1, 1973--September 30, 1977

Energy Technology Data Exchange (ETDEWEB)

1977-01-01

Volume 2 covers major activities of the Artificial Heart Development program that supported the design, fabrication, and test of the system demonstration units. Section A.1.0 provides a listing beyond that of the body of the report on the components needed for an implantation. It also presents glove box sterilization calibration results and results of an extensive mock circulation calibration. Section A.2.0 provides detailed procedures for assembly, preparing for use, and the use of the system and major components. Section A.3.0 covers the component research and development activities undertaken to improve components of the existing system units and to prepare for a future prototype system. Section A.4.0 provides a listing of the top assembly drawings of the major systems variations fabricated and tested.

EBR-II: search for the lost subassembly

International Nuclear Information System (INIS)

King, R.W.; Buschman, H.W.; Poloncsik, J.; Remsburg, J.S.; Sine, H.W.

1983-01-01

Experimental Breeder Reactor II (EBR-II) has been operating for nearly 20 years as part of the foundation of the US Department of Energy's LMFBR development program. During that time, the EBR-II fuel-handling system has performed extremely well, especially considering the conditions under which much of the system operates and the reliability required to maintain the high plant factor routinely demonstrated by EBR-II. Since EBR-II is a pool-type reactor, much of the fuel handling is done remotely within the sodium-filled primary tank at 371 0 C. Activities involved in locating a misplaced fuel subassembly in the primary tank are described

FDA (Food and Drug Administration) compliance program guidance manual and updates (FY 86). Section 4. Medical and radiological devices. Irregular report

International Nuclear Information System (INIS)

1986-01-01

The FDA Compliance Program Guidance Manual provides a system for issuing and filing program plans and instructions directed to Food and Drug Administration Field operations for project implementation. Section IV provides those chapters of the Compliance Program Guidance Manual which pertain to the areas of medical and radiological devices. Some of the areas of coverage include laser and sunlamp standards inspections, compliance testing of various radiation-emitting products such as television receivers and microwave ovens, emergency response planning and policy, premarket approval and device manufacturers inspections, device problem reporting, sterilization of devices, and consumer education programs on medical and radiological devices

Modern programming language

Science.gov (United States)

Feldman, G. H.; Johnson, J. A.

1980-01-01

Structural-programming language is especially-tailored for producing assembly language programs for MODCOMP II and IV mini-computes. Modern programming language consists of set of simple and powerful control structures that include sequencing alternative selection, looping, sub-module linking, comment insertion, statement continuation, and compilation termination capabilities.

Neutron cross section measurements for the Fast Breeder Program

International Nuclear Information System (INIS)

Block, R.C.

1979-06-01

This research was concerned with the measurement of neutron cross sections of importance to the Fast Breeder Reactor. The capture and total cross sections of fission products ( 101 102 104 Ru, 143 145 Nd, 149 Sm, 95 97 Mo, Cs, Pr, Pd, 107 Pd, 99 Tc) and tag gases (Kr, 78 80 Kr) were measured up to 100 keV. Filtered neutron beams were used to measure the capture cross section of 238 U (with an Fe filter) and the total cross section of Na (with a Na filter). A radioactive neutron capture detector was developed. A list of publications is included

Evolution of thermal-hydraulics testing in EBR-II

International Nuclear Information System (INIS)

Golden, G.H.; Planchon, H.P.; Sackett, J.I.; Singer, R.M.

1987-01-01

A thermal-hydraulics testing and modeling program has been underway at the Experimental Breeder Reactor-II (EBR-II) for 12 years. This work culminated in two tests of historical importance to commercial nuclear power, a loss of flow without scram and a loss of heat sink wihout scram, both from 100% initial power. These tests showed that natural processes will shut EBR-II down and maintain cooling without automatic control rod action or operator intervention. Supporting analyses indicate that these results are characteristic of a range of sizes of liquid metal cooled reactors (LMRs), if these reactors use metal driver fuel. This type of fuel is being developed as part of the Integral Fast Reactor Program at Argonne National Laboratory. Work is now underway at EBR-II to exploit the inherent safety of metal-fueled LMRs with regard to development of improved plant control strategies. (orig.)

RAWS II: A MULTIPLE REGRESSION ANALYSIS PROGRAM,

Science.gov (United States)

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

EBR-II high-ramp transients under computer control

International Nuclear Information System (INIS)

Forrester, R.J.; Larson, H.A.; Christensen, L.J.; Booty, W.F.; Dean, E.M.

1983-01-01

During reactor run 122, EBR-II was subjected to 13 computer-controlled overpower transients at ramps of 4 MWt/s to qualify the facility and fuel for transient testing of LMFBR oxide fuels as part of the EBR-II operational-reliability-testing (ORT) program. A computer-controlled automatic control-rod drive system (ACRDS), designed by EBR-II personnel, permitted automatic control on demand power during the transients

Elliptical cross section fuel rod study II; Estudio de barras combustibles de seccion eliptica II

Energy Technology Data Exchange (ETDEWEB)

Taboada, H; Marajofsky, A [Comision Nacional de Energia Atomica, San Martin (Argentina). Unidad de Actividad Combustibles Nucleares

1997-12-31

In this paper it is continued the behavior analysis and comparison between cylindrical fuel rods of circular and elliptical cross sections. Taking into account the accepted models in the literature, the fission gas swelling and release were studied. An analytical comparison between both kinds of rod reveals a sensible gas release reduction in the elliptical case, a 50% swelling reduction due to intragranular bubble coalescence mechanism and an important swelling increase due to migration bubble mechanism. From the safety operation point of view, for the same linear power, an elliptical cross section rod is favored by lower central temperatures, lower gas release rates, greater gas store in ceramic matrix and lower stored energy rates. (author). 6 refs., 8 figs., 1 tab.

Recent results of high p(T) physics at the CDF II

Energy Technology Data Exchange (ETDEWEB)

Tsuno, Soushi; /Okayama U.

2005-02-01

The Tevatron Run II program has been in progress since 2001. The CDF experiment has accumulated roughly five times as much data as did Run I, with much improved detectors. Preliminary results from the CDF experiment are presented. The authors focus on recent high p{sub T} physics results in the Tevatron Run II program.

Measuring impact of JAMA Dermatology Practice Gaps section on training in US dermatology residency programs.

Science.gov (United States)

Britton, Kristina M; Stratman, Erik J

2013-07-01

JAMA Dermatology Practice Gaps commentaries are intended to aid in the interpretation of the literature to make it more practical and applicable to daily patient care. Practice Gaps commentaries have had an impact on physician clinical practice and dermatology residency curricula. To assess the impact of JAMA Dermatology Practice Gaps commentaries on dermatology residency training programs in the United States, including journal club discussions and local quality improvement activities. A web-based questionnaire of 17 questions was sent via e-mail to US dermatology residency program directors (PDs) in February 2012. Program director report of incorporating Practice Gaps themes and discussions into resident journal club activities, clinical practice, quality improvement activities, or research projects in the residency programs, as a result of a Practice Gaps commentary. Of the 114 surveys distributed to US dermatology residency PDs, 48 were completed (42% response rate). Sixty percent of PDs reported familiarity with the Practice Gaps section of JAMA Dermatology, and 56% discuss these commentaries during resident journal club activities. Quality improvement and research projects have been initiated as a result of Practice Gaps commentaries. Practice Gaps commentaries are discussed during most dermatology residency journal club activities. Practice Gaps have had an impact on physician practice and dermatology residency curricula and can serve as a tool for enhanced continuing medical education and quality improvement initiatives.

Comparative analysis of Carnaval II Library

International Nuclear Information System (INIS)

Santos Bastos, W. dos

1981-01-01

The Carnaval II cross sections library from the french fast reactor calculation system is evaluated in two ways: 1 0 ) a comparative analysis of the calculations system for fast reactors at IEN (Instituto de Engenharia Nuclear) using a 'benchmark' model is done; 2 0 ) a comparative analysis in relation to the french system itself is also done, using calculations realized with two versions of the french library: the SETR-II and the CARNAVAL IV, the first one being anterior and the second one posterior to the Carnaval II version, the one used by IEN. (Author) [pt

Lithium ion beam driven hohlraums for PBFA II

International Nuclear Information System (INIS)

Dukart, R.J.

1994-01-01

In our light ion inertial confinement fusion (ICF) program, fusion capsules are driven with an intense x-ray radiation field produced when an intense beam of ions penetrates a radiation case and deposits energy in a foam x-ray conversion region. A first step in the program is to generate and measure these intense fields on the Particle Beam Fusion Accelerator II (PBFA II). Our goal is to generate a 100-eV radiation temperature in lithium ion beam driven hohlraums, the radiation environment which will provide the initial drive temperature for ion beam driven implosion systems designed to achieve high gain. In this paper, we describe the design of such hohlraum targets and their predicted performance on PBFA II as we provide increasing ion beam intensities

Research in Aeroelasticity EFP-2007-II

DEFF Research Database (Denmark)

is demonstrated. For attached flow over thin airfoils (18%) 2D computations provide good results while a combination of Detached Eddy Simulation and laminar/ turbulent transition modeling improve the results in stalled conditions for a thick airfoil. • The unsteady flow in the nacelle region of a wind turbine......This report contains results from the EFP-2007-II project "Program for Research in Applied Aeroelasticity". The main results can be summed up into the following bullets: • 2D CFD was used to investigate tower shadow effects on both upwind and downwind turbines, and was used to validate the tower...... is dominated by large flow gradients caused by unsteady shedding of vortices from the root sections of the blades. • The averaged nacelle wind speed compares well to the freestream wind speed, whereas the nacelle flow angle is highly sensitive to vertical positioning and tilt in the inflow. • The trailing edge...

Developmental status of bioassays in genetic toxicology: a report of Phase II of the US Environmental Protection Agency Gene-Tox program

Energy Technology Data Exchange (ETDEWEB)

Brusick, D; Auletta, A

1985-01-01

The Gene-Tox Program was structured around two phases of genetic test data evaluation. The first phase consisted of 36 Work Group reports, each evaluating the results and performance of a specific bioassay. The second phase consisted of a plan to summarize the information provided by the Work Groups. The Gene-Tox Coordinating Committee was to be responsible for Phase II, and several subgroups were assigned specific goals in implementing this analysis. This report deals with Goal I which is to identify the developmental status of the individual bioassays reviewed by the Gene-Tox Work Groups in the first phase of the Program. 5 references, 6 tables.

Teaching science content in nursing programs in Australia: a cross-sectional survey of academics.

Science.gov (United States)

Birks, Melanie; Ralph, Nicholas; Cant, Robyn; Hillman, Elspeth; Chun Tie, Ylona

2015-01-01

Professional nursing practice is informed by biological, social and behavioural sciences. In undergraduate pre-registration nursing programs, biological sciences typically include anatomy, physiology, microbiology, chemistry, physics and pharmacology. The current gap in the literature results in a lack of information about the content and depth of biological sciences being taught in nursing curricula. The aim of this study was to establish what priority is given to the teaching of science topics in these programs in order to inform an understanding of the relative importance placed on this subject area in contemporary nursing education. This study employed a cross-sectional survey method. This paper reports on the first phase of a larger project examining science content in nursing programs. An existing questionnaire was modified and delivered online for completion by academics who teach science to nurses in these programs. This paper reports on the relative priority given by respondents to the teaching of 177 topics contained in the questionnaire. Of the relatively small population of academics who teach science to nursing students, thirty (n = 30) completed the survey. Findings indicate strong support for the teaching of science in these programs, with particular priority given to the basic concepts of bioscience and gross system anatomy. Of concern, most science subject areas outside of these domains were ranked as being of moderate or low priority. While the small sample size limited the conclusions able to be drawn from this study, the findings supported previous studies that indicated inadequacies in the teaching of science content in nursing curricula. Nevertheless, these findings have raised questions about the current philosophy that underpins nursing education in Australia and whether existing practices are clearly focused on preparing students for the demands of contemporary nursing practice. Academics responsible for the design and implementation of

Reduced enrichment program for the FRM-II, status 2004

International Nuclear Information System (INIS)

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

2005-01-01

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

EBR-II Data Digitization

Energy Technology Data Exchange (ETDEWEB)

Yoon, Su-Jong [Idaho National Lab. (INL), Idaho Falls, ID (United States); Rabiti, Cristian [Idaho National Lab. (INL), Idaho Falls, ID (United States); Sackett, John [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2014-08-01

1. Objectives To produce a validation database out of those recorded signals it will be necessary also to identify the documents need to reconstruct the status of reactor at the time of the beginning of the recordings. This should comprehends the core loading specification (assemblies type and location and burn-up) along with this data the assemblies drawings and the core drawings will be identified. The first task of the project will be identify the location of the sensors, with respect the reactor plant layout, and the physical quantities recorded by the Experimental Breeder Reactor-II (EBR-II) data acquisition system. This first task will allow guiding and prioritizing the selection of drawings needed to numerically reproduce those signals. 1.1 Scopes and Deliverables The deliverables of this project are the list of sensors in EBR-II system, the identification of storing location of those sensors, identification of a core isotopic composition at the moment of the start of system recording. Information of the sensors in EBR-II reactor system was summarized from the EBR-II system design descriptions listed in Section 1.2.

Polarized electron cyclotron emission in the Tokapole II Tokamak

International Nuclear Information System (INIS)

Sengstacke, M.A.; Dexter, R.N.; Prager, S.C.

1984-06-01

To examine the effect of wall reflections we have measured the polarization of second harmonic cyclotron emission (at omega = 2 omega/sub ce/) in the Tokapole II tokamak both with and without a microwave absorber installed within the field of view of the receiving antenna. Indeed, the local elimination of wall reflections markedly enhances the polarization, as described in section II. Section III describes observations consistent with right-hand cutoff effects and an attempt to infer the electron temperature from cyclotron emission in an optically thin plasma

Calculation of self-shielding factors for cross-sections in the unresolved resonance region using the GRUCON applied program package

International Nuclear Information System (INIS)

Sinitsa, V.V.

1984-11-01

The author gives a scheme for the calculation of the self-shielding factors in the unresolved resonance region using the GRUCON applied program package. This package is especially created to be used in the conversion of evaluated neutron cross-section data, as available in existing data libraries, into multigroup microscopic constants. A detailed description of the formulae and algorithms used in the programs is given. Some typical examples of calculation are considered and the results are compared with those of other authors. The calculation accuracy is better than 2%

A taxonomic and phylogenetic revision of Penicillium section Aspergilloides

DEFF Research Database (Denmark)

Houbraken, J.; Visagie, C.M.; Meijer, M.

2014-01-01

(CaM) and RNA polymerase II second largest subunit (RPB2) sequences. Section Aspergilloides is subdivided into 12 clades and 51 species. Twenty-five species are described here as new and P. yezoense, a species originally described without a Latin diagnosis, is validated. Species belonging to section...

Evaluation of the impact of a breast cancer awareness program in rural Ghana: a cross-sectional survey.

Science.gov (United States)

Mena, Marisa; Wiafe-Addai, Beatrice; Sauvaget, Catherine; Ali, Ibrahim A; Wiafe, Seth A; Dabis, François; Anderson, Benjamin O; Malvy, Denis; Sasco, Annie J

2014-02-15

Community awareness is crucial to early detection of breast cancer in low- and middle-income countries. In Ghana 60% of the cases are detected at late stages. Breast Care International (BCI) is a Ghanaian non-governmental organization dedicated to raising breast cancer awareness. A cross-sectional survey was designed to assess the impact of BCI program on knowledge, attitudes and practices (KAP) toward breast cancer among women from rural communities of Ghana. A total of 232 women were interviewed in June 2011 in the Ashanti region; of these 131 participants were from a community that received the BCI program in August 2010 (intervention group) and 101 from another community that received the program post-survey (referent group). Data analysis was performed using Epi-Info version 3.5.3. Knowledge about breast cancer among participants who received the program was better than among those who did not. Only 53.5% of participants from the referent group knew that breast cancer usually appears as painless breast lump when compared to 82.3% from the intervention group. Participants who attended the program were significantly more likely to obtain higher knowledge scores (odds ratio (OR) = 2.10, 95% confidence interval (CI) = 1.14-3.86) and to state practicing breast self-examination (OR = 12.29, 95% CI = 5.31-28.48). The BCI program improved KAP toward breast cancer. Further research is warranted to provide stronger evidence that the program improves breast cancer early detection. © 2013 UICC.

Electroweak physics prospects for CDF in Run II

International Nuclear Information System (INIS)

Eric James

2003-01-01

The CDF collaboration will vigorously pursue a comprehensive program of electroweak physics during Run II at the Tevatron based strongly on the successful Run I program. The Run IIa integrated luminosity goal of 2 fb -1 will lead to a CDF dataset twenty times larger than that collected in Run I. In addition, an increase in the energy of the colliding beams from √s = 1.80 TeV to √s = 1.96 TeV for Run II provides a 10% increase in the W and Z boson production cross sections and a corresponding enlargement of the electroweak event samples. In the near term, CDF expects to collect a dataset with 2-3 times the integrated luminosity of Run I by September of 2003. Utilizing these new datasets CDF will be able to make improved, precision measurements of Standard Model electroweak parameters including M W , M top , Λ W , and sin 2 θ W eff . The goal of these measurements will be to improve our understanding of the self-consistency of the Standard Model and knowledge of the Higgs boson mass within the model. The top plot in Fig. 1 illustrates our current knowledge of the Standard Model Higgs mass based on measurements of M W and M top . The constraints imposed by combined CDF and D0 Run I measurements of M W (80.456 ± 0.059GeV/c 2 ) and M top (174.3 ± 5.1GeV/c 2 ) are illustrated by the shaded oval region on the plot. The hatched rectangle shows the additional constraint imposed by the recent LEP2 measurement of M W . The bottom plot in Fig. 1 illustrates the expected improvement in these constraints based on Run II CDF measurements utilizing a 2 fb -1 dataset. The shaded oval region in this plot is based on current estimates of a 40 MeV/c 2 uncertainty for measuring M W and a 2-3 GeV/c 2 uncertainty for measuring M top

SIMMER-II: A computer program for LMFBR disrupted core analysis

Energy Technology Data Exchange (ETDEWEB)

Bohl, W.R.; Luck, L.B.

1990-06-01

SIMMER-2 (Version 12) is a computer program to predict the coupled neutronic and fluid-dynamics behavior of liquid-metal fast reactors during core-disruptive accident transients. The modeling philosophy is based on the use of general, but approximate, physics to represent interactions of accident phenomena and regimes rather than a detailed representation of specialized situations. Reactor neutronic behavior is predicted by solving space (r,z), energy, and time-dependent neutron conservation equations (discrete ordinates transport or diffusion). The neutronics and the fluid dynamics are coupled via temperature- and background-dependent cross sections and the reactor power distribution. The fluid-dynamics calculation solves multicomponent, multiphase, multifield equations for mass, momentum, and energy conservation in (r,z) or (x,y) geometry. A structure field with nine density and five energy components; a liquid field with eight density and six energy components; and a vapor field with six density and on energy component are coupled by exchange functions representing a modified-dispersed flow regime with a zero-dimensional intra-cell structure model.

SIMMER-II: A computer program for LMFBR disrupted core analysis

International Nuclear Information System (INIS)

Bohl, W.R.; Luck, L.B.

1990-06-01

SIMMER-2 (Version 12) is a computer program to predict the coupled neutronic and fluid-dynamics behavior of liquid-metal fast reactors during core-disruptive accident transients. The modeling philosophy is based on the use of general, but approximate, physics to represent interactions of accident phenomena and regimes rather than a detailed representation of specialized situations. Reactor neutronic behavior is predicted by solving space (r,z), energy, and time-dependent neutron conservation equations (discrete ordinates transport or diffusion). The neutronics and the fluid dynamics are coupled via temperature- and background-dependent cross sections and the reactor power distribution. The fluid-dynamics calculation solves multicomponent, multiphase, multifield equations for mass, momentum, and energy conservation in (r,z) or (x,y) geometry. A structure field with nine density and five energy components; a liquid field with eight density and six energy components; and a vapor field with six density and on energy component are coupled by exchange functions representing a modified-dispersed flow regime with a zero-dimensional intra-cell structure model

Measurement of Nuclear Recoils in the CDMS II Dark Matter Search

Energy Technology Data Exchange (ETDEWEB)

Fallows, Scott Mathew [Univ. of Minnesota, Minneapolis, MN (United States)

2014-12-01

The Cryogenic Dark Matter Search (CDMS) experiment is designed to directly detect elastic scatters of weakly-interacting massive dark matter particles (WIMPs), on target nuclei in semiconductor crystals composed of Si and Ge. These scatters would occur very rarely, in an overwhelming background composed primarily of electron recoils from photons and electrons, as well as a smaller but non-negligible background of WIMP-like nuclear recoils from neutrons. The CDMS II generation of detectors simultaneously measure ionization and athermal phonon signals from each scatter, allowing discrimination against virtually all electron recoils in the detector bulk. Pulse-shape timing analysis allows discrimination against nearly all remaining electron recoils taking place near detector surfaces. Along with carefully limited neutron backgrounds, this experimental program allowed for \\background- free" operation of CDMS II at Soudan, with less than one background event expected in each WIMP-search analysis. As a result, exclusionary upper-limits on WIMP-nucleon interaction cross section were placed over a wide range of candidate WIMP masses, ruling out large new regions of parameter space.

Irradiations at RTNS-II

International Nuclear Information System (INIS)

Heikkinen, D.W.; Logan, C.M.

1982-01-01

The RTNS-II 14-MeV neutron source facility at Lawrence Livermore National Laboratory is described. Average neutron source parameters are outlined. A brief general description of the irradiation program to the present time is given. A short discussion of guidelines for prospective users is also given

Technology Commercialization Program 1991

Energy Technology Data Exchange (ETDEWEB)

1991-11-01

This reference compilation describes the Technology Commercialization Program of the Department of Energy, Defense Programs. The compilation consists of two sections. Section 1, Plans and Procedures, describes the plans and procedures of the Defense Programs Technology Commercialization Program. The second section, Legislation and Policy, identifies legislation and policy related to the Program. The procedures for implementing statutory and regulatory requirements are evolving with time. This document will be periodically updated to reflect changes and new material.

Phase II clinical development of new drugs

CERN Document Server

Ting, Naitee; Ho, Shuyen; Cappelleri, Joseph C

2017-01-01

This book focuses on how to appropriately plan and develop a Phase II program, and how to design Phase II clinical trials and analyze their data. It provides a comprehensive overview of the entire drug development process and highlights key questions that need to be addressed for the successful execution of Phase II, so as to increase its success in Phase III and for drug approval. Lastly it warns project team members of the common potential pitfalls and offers tips on how to avoid them.

La Materia. Nivel II. Basado en el curso de estudios de Ciencia de Montgomery County Public Schools. (Matter. Level II. Based on the Montgomery County Public Schools Science Studies Program).

Science.gov (United States)

Gerstman, M. Linda

This curriculum unit is for use in an elementary school foreign language immersion program in Montgomery County, Maryland. The unit is geared toward the second grade science classroom. It includes instructional and performance objectives, vocabulary lists, optional language structure sections, illustrations, activities, evaluation suggestions, and…

Transport with Astra in TJ-II

International Nuclear Information System (INIS)

Lopez-Bruna, D.; Castejon, F.; Fontdecaba, J. M.

2004-01-01

This report describes the adaptation of the numerical transport shell ASTRA for performing plasma calculations in the TJ-II stellarator device. Firstly, an approximation to the TJ-II geometry is made and a simple transport model is shared with two other codes in order to compare these codes (PROCTR, PRETOR-Stellarator) with ASTRA as calculation tool for TJ-II plasmas are provided: interpretative and predictive transport. The first consists in estimating the transport coefficients from real experimental data, thes being taken from three TJ-II discharges. The predictive facet is illustrated using a model that is able to includes self-consistently the dynamics of transport barriers. The report includes this model, written in the ASTRA programming language, to illustrate the use of ASTRA. (Author) 26 refs

HistoStitcher© : An Interactive Program for Accurate and Rapid Reconstruction of Digitized Whole Histological Sections from Tissue Fragments

Science.gov (United States)

Chappelow, Jonathan; Tomaszewski, John E.; Feldman, Michael; Shih, Natalie; Madabhushi, Anant

2011-01-01

We present an interactive program called HistoStitcher© for accurate and rapid reassembly of histology fragments into a pseudo-whole digitized histological section. HistoStitcher© provides both an intuitive graphical interface to assist the operator in performing the stitch of adjacent histology fragments by selecting pairs of anatomical landmarks, and a set of computational routines for determining and applying an optimal linear transformation to generate the stitched image. Reconstruction of whole histological sections from images of slides containing smaller fragments is required in applications where preparation of whole sections of large tissue specimens is not feasible or efficient, and such whole mounts are required to facilitate (a) disease annotation and (b) image registration with radiological images. Unlike manual reassembly of image fragments in a general purpose image editing program (such as Photoshop), HistoStitcher© provides memory efficient operation on high resolution digitized histology images and a highly flexible stitching process capable of producing more accurate results in less time. Further, by parameterizing the series of transformations determined by the stitching process, the stitching parameters can be saved, loaded at a later time, refined, or reapplied to multi-resolution scans, or quickly transmitted to another site. In this paper, we describe in detail the design of HistoStitcher© and the mathematical routines used for calculating the optimal image transformation, and demonstrate its operation for stitching high resolution histology quadrants of a prostate specimen to form a digitally reassembled whole histology section, for 8 different patient studies. To evaluate stitching quality, a 6 point scoring scheme, which assesses the alignment and continuity of anatomical structures important for disease annotation, is employed by three independent expert pathologists. For 6 studies compared with this scheme, reconstructed sections

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.

Effects of Recruiting Midwives into a Family Physician Program on Women's Awareness and Preference for Mode of Delivery and Caesarean Section Rates in Rural Areas of Kurdistan.

Science.gov (United States)

Hajizadeh, Shayesteh; Tehrani, Fahimeh Ramezani; Simbar, Masoumeh; Farzadfar, Farshad

2016-01-01

The accepted rate rate of caesarean section is 15%. It is expected that an increase in the density of midwives in the family physician program lead to a decrease in this indicator. This study aimed to compare the rates of caesarean section and women's awareness and preference for mode of delivery before and after the implementation of the family physician program in health centres with and without an increase in midwives density. In this cross-sectional study, using multistage cluster sampling method a total of 668 mothers with two-month-old children were selected from among all mothers with two-month-old children who were living in rural areas of Kurdistan province. Using the difference-in-differences model and Matchit statistical model, the factors associated with caesarean section rates and women's awareness and preference for mode of delivery were compared in centres with and without an increase in midwives density after the implementation of the family physician program. To compare the changes before and after the program, we used the data collected from the same number of women in 2005 as the baseline. After adjusting for baseline data collected in 2005, the resutls showed no significant change in caesarean section rates and women's awareness and preference for mode of delivery in the centres with and without an increase in midwives density after the implementation of the family physician program. The Matchit model showed a significant mean increase 14%(0.03-0.25) in women's awareness of the benefits of natural childbirth between 2005 and 2013 in health centres where the density of midwives increased compared with health centres where it did not. The difference-in-differences model showed that the odds ratio of women's preference for caesarean section decreased by 41% among participants who were aware of the benefits of natural childbirth, (OR = 0.59, 95% CI: (0.22-0.85); P>0.001). The results of this study showed that an increase in the density of midwives

Battle Staff Training System II: Computer-Based Instruction Supporting the Force XXI Training Program

National Research Council Canada - National Science Library

Wampler, Richard

1998-01-01

This report documents the methodology and lessons learned in the development of the Innovative Tools and Techniques for Brigade and Below Staff Training II - Battle Staff Training System II (ITTBBST-BSTS II...

Heavy-Section Steel Irradiation Program. Volume 5, No. 2, Progress report, April 1994--September 1994

International Nuclear Information System (INIS)

Corwin, W.R.

1995-07-01

The Heavy-Section Steel Irradiation (HSSI) Program has been established with its primary goal to provide a thorough, quantitative assessment of the effects of neutron irradiation on the material behavior and the fracture toughness properties of typical pressure-vessel steels as they relate to light-water RPV integrity. Effects of specimen size; material chemistry; product form and microstructure; irradiation fluence, flux, temperature, and spectrum; and postirradiation annealing are being examined on a wide range of fracture properties. The HSSI Program is arranged into 14 tasks: (1) program management, (2) fracture toughness curve shift in high-copper weldments (Series 5 and 6), (3) K lc and K la curve shifts in low upper-shelf (LUS) welds (Series 8), (4) irradiation effects in a commercial LUS weld (Series 10), (5) irradiation effects on weld heat-affected zone and plate materials (Series 11), (6) annealing effects in LUS welds (Series 9), (7) microstructural and microfracture analysis of irradiation effects, (8) in-service irradiated and aged material evaluations, (9) Japan Power Development Reactor (JPDR) steel examination, (10) fracture toughness curve shift method, (11) special technical assistance, (12) technical assistance for Joint Coordinating Committee on Civilian Nuclear Reactor Safety (JCCCNRS) Working Groups 3 and 12, (13) correlation monitor materials, and (14) test reactor coordination. Progress on each task is reported

Heavy-Section Steel Irradiation Program: Progress report for April--September 1995. Volume 6, Number 2

International Nuclear Information System (INIS)

Corwin, W.R.

1996-08-01

The goal of the Heavy-Section Steel Irradiation Program is to provide a thorough, quantitative assessment of effects of neutron irradiation on material behavior, and in particular the fracture toughness properties, of typical pressure vessel steels as they relate to light-water reactor pressure-vessel integrity. Effects of specimen size, material chemistry, product form and microstructure, irradiation fluence, flux, temperature and spectrum, and post-irradiation annealing are being examined on a wide range of fracture properties. The HSSI Program is arranged into 14 tasks: (1) program management, (2) fracture toughness (K Ic ) curve shift in high-copper welds, (3) crack-arrest toughness (K Ia ) curve shift in high-copper welds, (4) irradiation effects on cladding, (5) K Ic and K Ia curve shifts in low upper-shelf welds, (6) annealing effects in low upper-shelf welds, (7) irradiation effects in a commercial low upper-shelf weld, (8) microstructural analysis of irradiation effects, (9) in-service aged material evaluations, (10) correlation monitor materials, (11) special technical assistance, (12) JPDR steel examination, (13) technical assistance for JCCCNRS Working Groups 3 and 12, and (14) additional requirements for materials. This report provides an overview of the activities within each of these task from April through September 1995

Risk Factors Accompanied with Nephropathy in Patients with Type II Diabetes; Test of the Biopsychosocial Model

Directory of Open Access Journals (Sweden)

I. Rahimian Boogar

2012-07-01

Full Text Available Introduction & Objective: The study of biopsychosocial factors influencing nephropathy as a most serious complication of type II diabetes is important. This study aimed to investigate risk factors accompanied with nephropathy in patients with type II diabetes based on the biopsychosocial model. Materials & Methods: In a cross-sectional descriptive study, 295 patients with type II diabetes were selected by convenience sampling in Tehran Shariati hospital outpatient clinics. The data were collected by demographical information questionnaire along with disease characteristics and depression anxiety stress scales (dass, quality of life scale (who- qol- bref, diabetes self-management scale (dsms, and diabetes knowledge scale (dks, then analyzed by chi-square, independent t-test and logistic regression with pasw software. Results: Hypertension (OR=3.841 & P0.05.Conclusion: It is important to pay attention to hypertension, glycated hemoglobin, body mass index, diabetes self-management, depression, quality of life, and diabetes knowledge for therapeutic intervention programming and diabetes complications control protocols for diabetic patients.(Sci J Hamadan Univ Med Sci 2012;19(2:44-53

Factors related to leader implementation of a nationally disseminated community-based exercise program: a cross-sectional study

Directory of Open Access Journals (Sweden)

Economos Christina D

2008-12-01

Full Text Available Abstract Background The benefits of community-based health programs are widely recognized. However, research examining factors related to community leaders' characteristics and roles in implementation is limited. Methods The purpose of this cross-sectional study was to use a social ecological framework of variables to explore and describe the relationships between socioeconomic, personal/behavioral, programmatic, leadership, and community-level social and demographic characteristics as they relate to the implementation of an evidence-based strength training program by community leaders. Eight-hundred fifty-four trained program leaders in 43 states were invited to participate in either an online or mail survey. Corresponding community-level characteristics were also collected. Programmatic details were obtained from those who implemented. Four-hundred eighty-seven program leaders responded to the survey (response rate = 57%, 78% online and 22% by mail. Results Of the 487 respondents, 270 implemented the program (55%. One or more factors from each category – professional, socioeconomic, personal/behavioral, and leadership characteristics – were significantly different between implementers and non-implementers, determined by chi square or student's t-tests as appropriate. Implementers reported higher levels of strength training participation, current and lifetime physical activity, perceived support, and leadership competence (all p Conclusion Among this sample of trained leaders, several factors within the professional, socioeconomic, personal/behavioral, and leadership categories were related to whether they implemented a community-based exercise program. It may benefit future community-based physical activity program disseminations to consider these factors when selecting and training leaders.

PARIS II: Computer Aided Solvent Design for Pollution Prevention

Science.gov (United States)

This product is a summary of U.S. EPA researchers' work developing the solvent substitution software tool PARIS II (Program for Assisting the Replacement of Industrial Solvents, version 2.0). PARIS II finds less toxic solvents or solvent mixtures to replace more toxic solvents co...

Heavy-Section Steel Technology Program: Recent developments in crack initiation and arrest research

International Nuclear Information System (INIS)

Pennell, W.E.

1991-01-01

Technology for the analysis of crack initiation and arrest is central to the reactor pressure vessel fracture-margin-assessment process. Regulatory procedures for nuclear plants utilize this technology to assure the retention of adequate fracture-prevention margins throughout the plant operating license period. As nuclear plants age and regulatory procedures dictate that fracture-margin assessments be performed, interest in the fracture-mechanics technology incorporated into those procedures has heightened. This has led to proposals from a number of sources for development and refinement of the underlying crack-initiation and arrest-analysis technology. This paper presents an overview of ongoing Heavy-Section Steel Technology (HSST) Program research aimed at refining the fracture toughness data used in the analysis of fracture margins under pressurized-thermal-shock loading conditions. 33 refs., 13 figs

Small Business Innovation Research, Post-Phase II Opportunity Assessment

Science.gov (United States)

Nguyen, Hung D.; Steele, Gynelle C.

2015-01-01

This report outlines current Small Business Innovation Research (SBIR) Post-Phase II opportunity contract award results for the SBIR technology program from 2007 to 2011 for NASA's Aeronautics Research Mission Directorate (ARMD), Human Exploration and Operations Mission Directorate (HEOMD), Science Mission Directorate (SMD), and Space Technology Mission Directorate (STMD). The report provides guidelines for incorporating SBIR technology into NASA programs and projects and provides a quantitative overview of the post-Phase II award patterns that correspond with each mission directorate at NASA Glenn Research Center (GRC). In recent years, one of NASA's goals has been to not only transfer SBIR technologies to commercial industries, but to ensure that NASA mission directorates incorporate SBIR technologies into their program and project activities. Before incorporating technologies into MD programs, it is important to understand each mission directorate structure because each directorate has different objectives and needs. The directorate program structures follow.

The prevalence of microalbuminuria among patients with type II ...

African Journals Online (AJOL)

This cross-sectional community-based study was carried out to determine the prevalence of microalbuminuria among patients with type II diabetes mellitus in a primary care setting, and to study the association between various risk factors and the presence of microalbuminuria. All patients with type II diabetes mellitus who ...

[Atomic Vapor Laser Isotope Separation (AVLIS) program]. Final report, [January--July 1992

Energy Technology Data Exchange (ETDEWEB)

1992-12-04

This report summarizes work performed for the Atomic Vapor Laser Isotope Separation (AVLIS) program from January through July, 1992. Each of the tasks assigned during this period is described, and results are presented. Section I details work on sensitivity matrices for the UDS relay telescope. These matrices show which combination of mirror motions may be performed in order to effect certain changes in beam parameters. In Section II, an analysis is given of transmission through a clipping aperture on the launch telescope deformable mirror. Observed large transmission losses could not be simulated in the analysis. An EXCEL spreadsheet program designed for in situ analysis of UDS optical systems is described in Section III. This spreadsheet permits analysis of changes in beam first-order characteristics due to changes in any optical system parameter, simple optimization to predict mirror motions needed to effect a combination of changes in beam parameters, and plotting of a variety of first-order data. Optical systems may be assembled directly from OSSD data. A CODE V nonsequential model of the UDS optical system is described in Section IV. This uses OSSD data to build the UDS model; mirror coordinates may thus be verified. Section V summarizes observations of relay telescope performance. Possible procedures which allow more accurate assessment of relay telescope performance are given.

Internet Image Viewer (iiV)

International Nuclear Information System (INIS)

Lee, Joel T; Munch, Kristin R; Carlis, John V; Pardo, José V

2008-01-01

Visualizing 3-dimensional (3-D) datasets is an important part of modern neuroimaging research. Many tools address this problem; however, they often fail to address specific needs and flexibility, such as the ability to work with different data formats, to control how and what data are displayed, to interact with values, and to undo mistakes. iiV, an interactive software program for displaying 3-D brain images, is described. This tool was programmed to solve basic problems in 3-D data visualization. It is written in Java so it is extensible, is platform independent, and can display images within web pages. iiV displays 3-D images as 2-dimensional (2-D) slices with each slice being an independent object with independent features such as location, zoom, colors, labels, etc. Feature manipulation becomes easier by having a full set of editing capabilities including the following: undo or redo changes; drag, copy, delete and paste objects; and save objects with their features to a file for future editing. It can read multiple standard positron emission tomography (PET) and magnetic resonance imaging (MRI) file formats like ECAT, ECAT7, ANALYZE, NIfTI-1 and DICOM. We present sample applications to illustrate some of the features and capabilities. iiV is an image display tool with many useful features. It is highly extensible, platform independent, and web-compatible. This report summarizes its features and applications, while illustrating iiV's usefulness to the biomedical imaging community

Programming an interim report on the SETL project. Part I: generalities. Part II: the SETL language and examples of its use

Energy Technology Data Exchange (ETDEWEB)

Schwartz, J T

1975-06-01

A summary of work during the past several years on SETL, a new programming language drawing its dictions and basic concepts from the mathematical theory of sets, is presented. The work was started with the idea that a programming language modeled after an appropriate version of the formal language of mathematics might allow a programming style with some of the succinctness of mathematics, and that this might ultimately enable one to express and experiment with more complex algorithms than are now within reach. Part I discusses the general approach followed in the work. Part II focuses directly on the details of the SETL language as it is now defined. It describes the facilities of SETL, includes short libraries of miscellaneous and of code optimization algorithms illustrating the use of SETL, and gives a detailed description of the manner in which the set-theoretic primitives provided by SETL are currently implemented. (RWR)

Monte Carlo-based validation of the ENDF/MC2-II/SDX cell homogenization path

International Nuclear Information System (INIS)

Wade, D.C.

1979-04-01

The results are presented of a program of validation of the unit cell homogenization prescriptions and codes used for the analysis of Zero Power Reactor (ZPR) fast breeder reactor critical experiments. The ZPR drawer loading patterns comprise both plate type and pin-calandria type unit cells. A prescription is used to convert the three dimensional physical geometry of the drawer loadings into one dimensional calculational models. The ETOE-II/MC 2 -II/SDX code sequence is used to transform ENDF/B basic nuclear data into unit cell average broad group cross sections based on the 1D models. Cell average, broad group anisotropic diffusion coefficients are generated using the methods of Benoist or of Gelbard. The resulting broad (approx. 10 to 30) group parameters are used in multigroup diffusion and S/sub n/ transport calculations of full core XY or RZ models which employ smeared atom densities to represent the contents of the unit cells

Monte Carlo; based validation of the ENDF/MC2-II/SDX cell homogenization path

International Nuclear Information System (INIS)

Wade, D.C.

1978-11-01

The results are summarized of a program of validation of the unit cell homogenization prescriptions and codes used for the analysis of Zero Power Reactor (ZPR) fast breeder reactor critical experiments. The ZPR drawer loading patterns comprise both plate type and pin-calandria type unit cells. A prescription is used to convert the three dimensional physical geometry of the drawer loadings into one dimensional calculational models. The ETOE-II/MC 2 -II/SDX code sequence is used to transform ENDF/B basic nuclear data into unit cell average broad group cross sections based on the 1D models. Cell average, broad group anisotropic diffusion coefficients are generated using the methods of Benoist or of Gelbard. The resulting broad (approx. 10 to 30) group parameters are used in multigroup diffusion and S/sub n/ transport calculations of full core XY or RZ models which employ smeared atom densities to represent the contents of the unit cells

Centrifuge workers study. Phase II, completion report

International Nuclear Information System (INIS)

Wooten, H.D.

1994-09-01

Phase II of the Centrifuge Workers Study was a follow-up to the Phase I efforts. The Phase I results had indicated a higher risk than expected among centrifuge workers for developing bladder cancer when compared with the risk in the general population for developing this same type of cancer. However, no specific agent could be identified as the causative agent for these bladder cancers. As the Phase II Report states, Phase I had been limited to workers who had the greatest potential for exposure to substances used in the centrifuge process. Phase II was designed to expand the survey to evaluate the health of all employees who had ever worked in Centrifuge Program Departments 1330-1339 but who had not been interviewed in Phase I. Employees in analytical laboratories and maintenance departments who provided support services for the Centrifuge Program were also included in Phase II. In December 1989, the Oak Ridge Associated Universities (ORAU), now known as Oak Ridge Institute for Science and Education (ORISE), was contracted to conduct a follow-up study (Phase II). Phase H of the Centrifuge Workers Study expanded the survey to include all former centrifuge workers who were not included in Phase I. ORISE was chosen because they had performed the Phase I tasks and summarized the corresponding survey data therefrom

Centrifuge workers study. Phase II, completion report

Energy Technology Data Exchange (ETDEWEB)

Wooten, H.D.

1994-09-01

Phase II of the Centrifuge Workers Study was a follow-up to the Phase I efforts. The Phase I results had indicated a higher risk than expected among centrifuge workers for developing bladder cancer when compared with the risk in the general population for developing this same type of cancer. However, no specific agent could be identified as the causative agent for these bladder cancers. As the Phase II Report states, Phase I had been limited to workers who had the greatest potential for exposure to substances used in the centrifuge process. Phase II was designed to expand the survey to evaluate the health of all employees who had ever worked in Centrifuge Program Departments 1330-1339 but who had not been interviewed in Phase I. Employees in analytical laboratories and maintenance departments who provided support services for the Centrifuge Program were also included in Phase II. In December 1989, the Oak Ridge Associated Universities (ORAU), now known as Oak Ridge Institute for Science and Education (ORISE), was contracted to conduct a follow-up study (Phase II). Phase H of the Centrifuge Workers Study expanded the survey to include all former centrifuge workers who were not included in Phase I. ORISE was chosen because they had performed the Phase I tasks and summarized the corresponding survey data therefrom.

A computer program with graphical user interface to plot the multigroup cross sections of WIMS-D library

International Nuclear Information System (INIS)

Thiyagarajan, T.K.; Ganesan, S.; Jagannathan, V.; Karthikeyan, R.

2002-01-01

As a result of the IAEA Co-ordinated Research Programme entitled 'Final Stage of the WIMS Library Update Project', new and updated WIMS-D libraries based upon ENDF/B-VI.5, JENDL-3.2 and JEF-2.2 have become available. A project to prepare an exhaustive handbook of WIMS-D cross sections from old and new libraries has been taken up by the authors. As part of this project, we have developed a computer program XnWlup with user-friendly graphical interface to help the users of WIMS-D library to enable quick visualization of the plots of the energy dependence of the multigroup cross sections of any nuclide of interest. This software enables the user to generate and view the histogram of 69 multi-group cross sections as a function of neutron energy under Microsoft Windows environment. This software is designed using Microsoft Visual C++ and Microsoft Foundation Classes Library. The current features of the software, on-line help manual and future plans for further development are described in this paper

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

Science.gov (United States)

1980-09-15

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

Time-dependent, Bianchi II, rotating universe

International Nuclear Information System (INIS)

Reboucas, M.J.

1981-01-01

An exact cosmological solution of Einstein's equations which has time-dependent rotation is presented. The t-constant sections are of Bianchi type II. The source of this geometry is a fluid which has not been thermalized. (Author) [pt

Type II Supernova Spectral Diversity. II. Spectroscopic and Photometric Correlations

Science.gov (United States)

Gutiérrez, Claudia P.; Anderson, Joseph P.; Hamuy, Mario; González-Gaitan, Santiago; Galbany, Lluis; Dessart, Luc; Stritzinger, Maximilian D.; Phillips, Mark M.; Morrell, Nidia; Folatelli, Gastón

2017-11-01

We present an analysis of observed trends and correlations between a large range of spectral and photometric parameters of more than 100 type II supernovae (SNe II), during the photospheric phase. We define a common epoch for all SNe of 50 days post-explosion, where the majority of the sample is likely to be under similar physical conditions. Several correlation matrices are produced to search for interesting trends between more than 30 distinct light-curve and spectral properties that characterize the diversity of SNe II. Overall, SNe with higher expansion velocities are brighter, have more rapidly declining light curves, shorter plateau durations, and higher 56Ni masses. Using a larger sample than previous studies, we argue that “Pd”—the plateau duration from the transition of the initial to “plateau” decline rates to the end of the “plateau”—is a better indicator of the hydrogen envelope mass than the traditionally used optically thick phase duration (OPTd: explosion epoch to end of plateau). This argument is supported by the fact that Pd also correlates with s 3, the light-curve decline rate at late times: lower Pd values correlate with larger s 3 decline rates. Large s 3 decline rates are likely related to lower envelope masses, which enables gamma-ray escape. We also find a significant anticorrelation between Pd and s 2 (the plateau decline rate), confirming the long standing hypothesis that faster declining SNe II (SNe IIL) are the result of explosions with lower hydrogen envelope masses and therefore have shorter Pd values. This paper includes data gathered with the 6.5 m Magellan Telescopes located at Las Campanas Observatory, Chile; and the Gemini Observatory, Cerro Pachon, Chile (Gemini Program GS- 2008B-Q-56). Based on observations collected at the European Organisation for Astronomical Research in the Southern Hemisphere, Chile (ESO Programs 076.A-0156, 078.D-0048, 080.A-0516, and 082.A-0526).

Sodium technology at EBR-II

International Nuclear Information System (INIS)

Holmes, J.T.; Smith, C.R.F.; Olson, W.H.

1976-01-01

Since the installation of purity monitoring systems in 1967, the control of the purity of the primary and secondary sodium and cover gas systems at the Experimental Breeder Reactor II (EBR-II) has been excellent. A rigorous monitoring program is being used to assure that operating limits for more than 25 chemical and radioactive impurities are not exceeded. The program involves the use of sophisticated sampling and analysis techniques and on-line monitors for both sodium and cover gas systems. Sodium purity control is accomplished by essentially continuous cold trapping of a small side stream of the total circulating sodium. The cold traps have been found to be very effective for the removal of the major chemical impurities (oxygen and hydrogen) and tritium but are almost ineffective for 131 I and 137 Cs that enter the sodium from fuel cladding breaks. Purging with pure argon maintains the cover gas purity

Synthesis and characterisation of Cu(II), Ni(II), Mn(II), Zn(II) and VO(II ...

Indian Academy of Sciences (India)

Unknown

Synthesis and characterisation of Cu(II), Ni(II), Mn(II), Zn(II) and VO(II) Schiff base complexes derived from o-phenylenediamine and acetoacetanilide. N RAMAN*, Y PITCHAIKANI RAJA and A KULANDAISAMY. Department of Chemistry, VHNSN College, Virudhunagar 626 001, India e-mail: ra_man@123india.com.

International Photovoltaic Program Plan. Volume II. Appendices

Energy Technology Data Exchange (ETDEWEB)

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

1979-12-01

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

Biologically active new Fe(II, Co(II, Ni(II, Cu(II, Zn(II and Cd(II complexes of N-(2-thienylmethylenemethanamine

Directory of Open Access Journals (Sweden)

C. SPÎNU

2008-04-01

Full Text Available Iron(II, cobalt(II, nickel (II, copper (II, zinc(II and cadmium(II complexes of the type ML2Cl2, where M is a metal and L is the Schiff base N-(2-thienylmethylenemethanamine (TNAM formed by the condensation of 2-thiophenecarboxaldehyde and methylamine, were prepared and characterized by elemental analysis as well as magnetic and spectroscopic measurements. The elemental analyses suggest the stoichiometry to be 1:2 (metal:ligand. Magnetic susceptibility data coupled with electronic, ESR and Mössbauer spectra suggest a distorted octahedral structure for the Fe(II, Co(II and Ni(II complexes, a square-planar geometry for the Cu(II compound and a tetrahedral geometry for the Zn(II and Cd(II complexes. The infrared and NMR spectra of the complexes agree with co-ordination to the central metal atom through nitrogen and sulphur atoms. Conductance measurements suggest the non-electrolytic nature of the complexes, except for the Cu(II, Zn(II and Cd(II complexes, which are 1:2 electrolytes. The Schiff base and its metal chelates were screened for their biological activity against Escherichia coli, Staphylococcus aureus and Pseudomonas aeruginosa and the metal chelates were found to possess better antibacterial activity than that of the uncomplexed Schiff base.

TRANSWRAP II: problem definition manual

International Nuclear Information System (INIS)

Knittle, D.E.

1981-02-01

The TRANSWRAP II computer code, written in Fortran IV and described in this Problem Definition Manual, was developed to analytically predict the magnitude of pressure pulses of large scale sodium-wate reactions in LMFBR secondary systems. It is currently being used for the Clinch River Breeder Reactor Program. The code provides the options, flexibility and features necessary to consider any system configuration. The code methodology has been validated with the aid of extensive sodium-water reaction test programs

Verification of Imperative Programs by Constraint Logic Program Transformation

Directory of Open Access Journals (Sweden)

Emanuele De Angelis

2013-09-01

Full Text Available We present a method for verifying partial correctness properties of imperative programs that manipulate integers and arrays by using techniques based on the transformation of constraint logic programs (CLP. We use CLP as a metalanguage for representing imperative programs, their executions, and their properties. First, we encode the correctness of an imperative program, say prog, as the negation of a predicate 'incorrect' defined by a CLP program T. By construction, 'incorrect' holds in the least model of T if and only if the execution of prog from an initial configuration eventually halts in an error configuration. Then, we apply to program T a sequence of transformations that preserve its least model semantics. These transformations are based on well-known transformation rules, such as unfolding and folding, guided by suitable transformation strategies, such as specialization and generalization. The objective of the transformations is to derive a new CLP program TransfT where the predicate 'incorrect' is defined either by (i the fact 'incorrect.' (and in this case prog is not correct, or by (ii the empty set of clauses (and in this case prog is correct. In the case where we derive a CLP program such that neither (i nor (ii holds, we iterate the transformation. Since the problem is undecidable, this process may not terminate. We show through examples that our method can be applied in a rather systematic way, and is amenable to automation by transferring to the field of program verification many techniques developed in the field of program transformation.

Artificial heart development program. Volume II. System support. Phase III summary report. Period covered: July 1, 1973--September 30, 1977

International Nuclear Information System (INIS)

1977-01-01

Appendix A covers major activities of the Artificial Heart Development program that supported the design, fabrication, and test of the system demonstration units. Section A.1.0 provides a listing beyond that of the body of the report on the components needed for an implantation. It also presents glove box sterilization calibration results and results of an extensive mock circulation calibration. Section A.2.0 provides detail procedures for assembly, preparing for use, and the use of the system and major components. Section A.3.0 covers the component research and development activities undertaken to improve components of the existing system units and to prepare for a future prototype system. Section A.4.0 provides a listing of the top assembly drawings of the major systems variations fabricated and tested

Artificial heart development program. Volume II. System support. Phase III summary report. Period covered: July 1, 1973--September 30, 1977

Energy Technology Data Exchange (ETDEWEB)

1977-01-01

Appendix A covers major activities of the Artificial Heart Development program that supported the design, fabrication, and test of the system demonstration units. Section A.1.0 provides a listing beyond that of the body of the report on the components needed for an implantation. It also presents glove box sterilization calibration results and results of an extensive mock circulation calibration. Section A.2.0 provides detail procedures for assembly, preparing for use, and the use of the system and major components. Section A.3.0 covers the component research and development activities undertaken to improve components of the existing system units and to prepare for a future prototype system. Section A.4.0 provides a listing of the top assembly drawings of the major systems variations fabricated and tested.

VizieR Online Data Catalog: The Carnegie-Chicago Hubble Program. II. IC 1613 (Hatt+, 2017)

Science.gov (United States)

Hatt, D.; Beaton, R. L.; Freedman, W. L.; Madore, B. F.; Jang, I.-S.; Hoyt, T. J.; Lee, M. G.; Monson, A. J.; Rich, J. A.; Scowcroft, V.; Seibert, M.

2018-04-01

Observations of IC 1613 were obtained on 2015 June 12 using the Inamori-Magellan Areal Camera and Spectrograph (IMACS) on the 6.5m Magellan-Baade telescope at Las Campanas Observatory. We obtain a 15.46'x15.46' field of view with resolution of 0.2"/pixel and observed in the BVI filters. See section 2.1.1. We have made use of archival imaging of IC 1613 taken from the Local Cosmology from Isolated Dwarfs program (PID:GO10505, PI: Gallart; Gallart 2005, LCID). A single field was imaged over 24 orbits between 2006 August 28 and 30 approximately 5' west of the center of IC 1613 using the HST ACS/WFC instrument, which provides a 202"x202" field of view with 0.05"/pixel resolution. Each orbit was divided between two ~1200s exposures in the F475W and F814W passbands, resulting in 48 epochs per filter. See section 2.1.2. We obtained near-infrared imaging over 24 orbits between 2014 December 17 and 18 using the HST WFC3/IR instrument (PID:GO13691, PI: Freedman; Freedman W. 2014 HST Proposal). The orbits were divided between two overlapping 136"x123" WFC3/IR pointings with a native resolution of 0.135"/pixel. See section 2.1.3. In parallel with the observations described in the previous section were 24 orbits with the HST ACS/WFC instrument (PID:GO13691, PI: Freedman; Freedman 2014 W. HST Proposal). Each exposure in F606W and F814W spanned ~500s. See section 2.1.4. (2 data files).

[Shortened hospital stay for elective cesarean section after initiation of a fast-track program and midwifery home-care].

Science.gov (United States)

Gunnarsdottir, Johanna; Bjornsdottir, Thorbjörg Edda; Halldorsson, Thorhallur Ingi; Halldorsdottir, Gudrun; Geirsson, Reynir Tomas

2011-07-01

To audit whether hospital stay shortened without increasing readmissions after implementation of fast-track methodology for elective cesarean section and characterize what influences length of stay. A fast-track program was initiated in November 2008, with a one year clinical audit and satisfaction survey. Discharge criteria were predefined and midwife home visits included if discharge was within 48 hours. Hospital stay by parity for women with elective section for singleton pregnancy between 1.11. 2008 - 31.10. 2009 (n=213, fast-track 182) was compared to 2003 (n=199) and 2007 (n=183). Readmissions and outpatient visits 2007 and 2008-9 were counted. Reasons for longer stay were recorded in fast-track, and body mass index. Median hospital stay decreased significantly from 81 to 52 hours between 2007 and 2008-9. Readmissions were four in each period and outpatient visit rates similar. In 2008-9, 66% of all women were discharged within 48 hours. Women in the fast-track program were satisfied with early discharge. Hospital stay for parous women was shorter in 2007 compared to 2003, but unchanged for nulliparas. Parity had a minimal influence on length of stay in 2008-9, although nulliparous women ≤ 25 years were more likely to stay >48 hours. Body mass index did not correlate with length of stay. Pain was rarely the reason for a longer stay in the fast-track program and 90% were satisfied with pain-medication after discharge. Most healthy women can be discharged early after singleton birth by elective cesarean, without increasing readmissions.

Preliminary evaluation of the Section 1603 treasury grant program for renewable power projects in the United States

International Nuclear Information System (INIS)

Bolinger, Mark; Wiser, Ryan; Darghouth, Naim

2010-01-01

This article evaluates the first year of the Section 1603 Treasury cash grant program, which enables renewable power projects in the US to elect cash grants in lieu of the federal tax credits that are otherwise available. To date, the program has been heavily subscribed, particularly by wind power projects, which had received 86% of the nearly $2.6 billion in grants that had been disbursed as of March 1, 2010. As of that date, 6.2 GW of the 10 GW of new wind capacity installed in the US in 2009 had applied for grants in lieu of production tax credits. Roughly 2.4 GW of this wind capacity may not have otherwise been built in 2009 in the absence of the grant program; this 2.4 GW may have supported approximately 51,600 short-term full-time-equivalent (FTE) gross job-years in the US during the construction phase of these wind projects, and 3860 long-term FTE gross jobs during the operational phase. The program's popularity stems from the significant economic value that it provides to renewable power projects, relative to the otherwise available tax credits. Although grants reward investment rather than efficient performance, this evaluation finds no evidence at this time of either widespread 'gold-plating' or performance problems. (author)

The Efficacy of Ilioinguinal and Iliohypogastric Nerve Block for Postoperative Pain After Caesarean Section

Directory of Open Access Journals (Sweden)

Melike Sakallı

2010-01-01

Full Text Available Background:: The effect of ilioinguinal and iliohypogastric (II-IH nerve block on postoperative pain is well documented when applied before Caesarean section but the efficacy remains unclear when applied after the surgical procedure. Therefore we investigated the effect of II-IH nerve block on postoperative pain and analgesic consumption in patients when applied after Caesarean Section. Methods: Sixty ASA I-II patients, scheduled for elective C/S were included in the study. After general anaesthesia was performed, the patients were allocated into 2 groups randomly. In Group I (n=30, bilateral II-IH block had been applied after the skin closure, with 10 ml of 0.5% ropivacaine on each side. In Group II (n=30 sham block had been applied. For postoperative analgesia all patients received tramadol via i.v patient controlled analgesia. VAS scores, tramadol consumption and side effects at 0th, 2nd, 4th, 6th, 8th, 12th, 16th, 20th, 24th hours were noted. Results: There was no difference between groups regarding demographical data. The mean VAS scores in Group I were significantly lower than in Group II at 6th (p=0.003, 8th (p=0.019, 12th (p=0.024, 24th hours (p=0.004 at rest and at 6th (p=0.022, 8th hours (p=0.047 with movement. Tramadol usage in Group I was significantly less than in Group II at all estimated time intervals (P=0.001. Total tramadol consumption was 331 ± 82 mg in Group I and 622±107 mg in group II (P=0.001. Conclusions: We observed that II-IH nerve block when applied after the surgery may reduce analgesic consumption after C/S. Key Words: Caesarean section, postoperative analgesia, Ilioinguinal and Iliohypogastric (II-IH nerve block.

Report on the FY17 Development of Computer Program for ASME Section III, Division 5, Subsection HB, Subpart B Rules

Energy Technology Data Exchange (ETDEWEB)

Swindeman, M. J. [Argonne National Lab. (ANL), Argonne, IL (United States); Jetter, R. I. [Argonne National Lab. (ANL), Argonne, IL (United States); Sham, T. -L. [Argonne National Lab. (ANL), Argonne, IL (United States)

2017-01-01

One of the objectives of the high temperature design methodology activities is to develop and validate both improvements and the basic features of ASME Boiler and Pressure Vessel Code, Section III, Rules for Construction of Nuclear Facility Components, Division 5, High Temperature Reactors, Subsection HB, Subpart B (HBB). The overall scope of this task is to develop a computer program to aid assessment procedures of components under specified loading conditions in accordance with the elevated temperature design requirements for Division 5 Class A components. There are many features and alternative paths of varying complexity in HBB. The initial focus of this computer program is a basic path through the various options for a single reference material, 316H stainless steel. However, the computer program is being structured for eventual incorporation all of the features and permitted materials of HBB. This report will first provide a description of the overall computer program, particular challenges in developing numerical procedures for the assessment, and an overall approach to computer program development. This is followed by a more comprehensive appendix, which is the draft computer program manual for the program development. The strain limits rules have been implemented in the computer program. The evaluation of creep-fatigue damage will be implemented in future work scope.

Testing of a one dimensional model for Field II calibration

DEFF Research Database (Denmark)

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

2008-01-01

Field II is a program for simulating ultrasound transducer fields. It is capable of calculating the emitted and pulse-echoed fields for both pulsed and continuous wave transducers. To make it fully calibrated a model of the transducer’s electro-mechanical impulse response must be included. We...... examine an adapted one dimensional transducer model originally proposed by Willatzen [9] to calibrate Field II. This model is modified to calculate the required impulse responses needed by Field II for a calibrated field pressure and external circuit current calculation. The testing has been performed...... to the calibrated Field II program for 1, 4, and 10 cycle excitations. Two parameter sets were applied for modeling, one real valued Pz27 parameter set, manufacturer supplied, and one complex valued parameter set found in literature, Alguer´o et al. [11]. The latter implicitly accounts for attenuation. Results show...

Complexes of cobalt(II), nickel(II), copper(II), zinc(II), cadmium(II) and dioxouranium(II) with thiophene-2-aldehydethiosemicarbazone

International Nuclear Information System (INIS)

Singh, Balwan; Misra, Harihar

1986-01-01

Metal complexes of thiosemicarbazides have been known for their pharmacological applications. Significant antitubercular, fungicidal and antiviral activities have been reported for thiosemicarbazides and their derivatives. The present study describes the systhesis and characterisation of complexes of Co II , Cu II , Zn II ,Cd II and UO II with thiosemicarbazone obtained by condensing thiophene-2-aldehyde with thiosemicarbazide. 17 refs., 2 tables. (author)

AXMIX program for cross section mixing and library arrangement

International Nuclear Information System (INIS)

Haynes, G.C.

1976-03-01

AXMIX is a FORTRAN IV computer code written to provide the user a tool for creating cross-section data sets for ANISN and DOT from cross-section sets already available on cards, nuclide-organized libraries, and group-independent data sets. Numerous options, including adjointing, P/sub n/ adjustments, and changing table length, are available to give the user broad flexibility. The number of energy groups which will fit into the core allocated is determined first. If all groups will fit, the solution is straightforward; if not, then the maximum number of groups which will fit is processed repeatedly by using direct access I/O and storage disks. Some flexibility in applying AXMIX is lost when cross sections to be processed contain upscatter. A special section on upscatter is included in the report. AXMIX is written for IBM System 360 computers with at least 150K bytes of memory. Problems of a practical nature require from 2 to 20 seconds of CPU time on a 360/91 computer. Running time is inversely proportional to the number of groups of data which will fit into core memory. I/O time is 50 to 100 times CPU time

RTNS-II utilization

International Nuclear Information System (INIS)

Doran, D.G.; Panayotou, N.F.; Powell, R.W.

1979-12-01

The objective of the several RTNS-II irradation programs is to maximize information gained from the small test volume available in this unique irradiation facility for application in the fusion materials program. While this facility provides the highest 14 MeV neutron flux available, the flux is generally too low and the irradiation volume too small for testing of engineering materials. Emphasis, therefore, is on identifying damage mechanisms of high energy neutrons and correlating them quantitatively with effects produced by fission neutrons. The information gained will be used to evaluate and calibrate damage and correlation models under development. The scope of the program includes in-situ experiments, postirradiation experiments, irradiation temperatures ranging from 4 0 K to 1,000 0 K, and fluences ranging from 3 x 10 16 to about 3 x 10 19 n/cm 2

PISCES and ALT-II: Juelich PSI papers

International Nuclear Information System (INIS)

Conn, R.W.; Hirooka, Y.; LaBombard, B.

1988-08-01

This publication comprises papers from the PISCES and ALT-II Programs at UCLA which were presented at the International Plasma Surface Interactions Meeting held in Juelich, FRG, on May 2-6, 1988. A list of publications from the PISCES and ALT-II contained in this report are: Deuterium pumping and erosion behavior of selected graphite materials under high flux plasma bombardment in PISCES; Erosion and redeposition behavior of selected NET-candidate materials under high-flux hydrogen, deuterium plasma bombardment in PISCES; Presheath profiles in simulated tokamak edge plasmas; Boundary asymmetries and plasma flow to the ALT-II toroidal belt pump limiter; ALT-II toroidal belt pump limiter performance in TEXTOR; and An in-situ spectroscopic erosion yield measurement with applications to sputtering and surface morphology alterations

Lunar Quest in Second Life, Lunar Exploration Island, Phase II

Science.gov (United States)

Ireton, F. M.; Day, B. H.; Mitchell, B.; Hsu, B. C.

2010-12-01

Linden Lab’s Second Life is a virtual 3D metaverse created by users. At any one time there may be 40,000-50,000 users on line. Users develop a persona and are seen on screen as a human figure or avatar. Avatars move through Second Life by walking, flying, or teleporting. Users form communities or groups of mutual interest such as music, computer graphics, and education. These groups communicate via e-mail, voice, and text within Second Life. Information on downloading the Second Life browser and joining can be found on the Second Life website: www.secondlife.com. This poster details Phase II in the development of Lunar Exploration Island (LEI) located in Second Life. Phase I LEI highlighted NASA’s LRO/LCROSS mission. Avatars enter LEI via teleportation arriving at a hall of flight housing interactive exhibits on the LRO/ LCROSS missions including full size models of the two spacecraft and launch vehicle. Storyboards with information about the missions interpret the exhibits while links to external websites provide further information on the mission, both spacecraft’s instrument suites, and related EPO. Other lunar related activities such as My Moon and NLSI EPO programs. A special exhibit was designed for International Observe the Moon Night activities with links to websites for further information. The sim includes several sites for meetings, a conference stage to host talks, and a screen for viewing NASATV coverage of mission and other televised events. In Phase II exhibits are updated to reflect on-going lunar exploration highlights, discoveries, and future missions. A new section of LEI has been developed to showcase NASA’s Lunar Quest program. A new exhibit hall with Lunar Quest information has been designed and is being populated with Lunar Quest information, spacecraft models (LADEE is in place) and kiosks. A two stage interactive demonstration illustrates lunar phases with static and 3-D stations. As NASA’s Lunar Quest program matures further

Tower Shielding Reactor II design and operation report. Vol. 3. Assembling and testing of the control mechanism assembly

International Nuclear Information System (INIS)

Ward, D.R.; Holland, L.B.

1979-09-01

The mechanisms that are operated to control the reactivity of the Tower Shielding Reactor II(TSR-II) are mounted on a Control Mechanism Housing (CMH) that is centered inside the reactor core. The information required to procure, fabricate, inspect, and assemble a CMH is contained in the ORNL engineering drawings listed in the appropriate sections. The components are fabricated and inspected from these drawings in accordance with a Quality Assurance Plan and a Manufacturing Plan. The material in this report describes the acceptance and performance tests of CMH subassemblies used ty the Tower Shielding Facility (TSF) staff but it can also be used by personnel fabricating the components. This information which was developed and used before the advent of the formalized QA Program and Manufacturing Plans evolved during the fabrication and testing of the first five CMHs

1981 laser program annual report

Energy Technology Data Exchange (ETDEWEB)

1982-08-01

This report is published in sections that correspond to the division of technical activity in the Program. Section 1 provides a Program Overview, presenting highlights of the technical accomplishments of the elements of the Program, a summary of activities carried out under the Glass Laser Experiments Lead Laboratory Program, as well as discussions of Program resources and facilities. Section 2 covers the work on solid-state Nd:glass lasers, including systems operations and Nova and Novette systems development. Section 3 reports on target-design activities, plasma theory and simulation, code development, and atomic theory. Section 4 presents the accomplishments of the Target Fabrication group, Section 5 contains the results of our diagnostics development, and Section 6 reports the results of laser-target experiments conducted during the year, along with supporting research and development activities. Section 7 presents the results from laser research and development, including solid-state R and D and the theoretical and experimental research on advanced lasers. Section 8 contains the results of studies in areas of energy and military applications, including those relating to electrical energy production by inertial-confinement fusion systems.

1981 laser program annual report

International Nuclear Information System (INIS)

1982-08-01

This report is published in sections that correspond to the division of technical activity in the Program. Section 1 provides a Program Overview, presenting highlights of the technical accomplishments of the elements of the Program, a summary of activities carried out under the Glass Laser Experiments Lead Laboratory Program, as well as discussions of Program resources and facilities. Section 2 covers the work on solid-state Nd:glass lasers, including systems operations and Nova and Novette systems development. Section 3 reports on target-design activities, plasma theory and simulation, code development, and atomic theory. Section 4 presents the accomplishments of the Target Fabrication group, Section 5 contains the results of our diagnostics development, and Section 6 reports the results of laser-target experiments conducted during the year, along with supporting research and development activities. Section 7 presents the results from laser research and development, including solid-state R and D and the theoretical and experimental research on advanced lasers. Section 8 contains the results of studies in areas of energy and military applications, including those relating to electrical energy production by inertial-confinement fusion systems

WARRIOR II, a high performance modular electric robot system

International Nuclear Information System (INIS)

Downton, G.C.

1996-01-01

A high performance electric robot, WARRIOR, was built for in-reactor welding at the Oldbury nuclear power plant in the United Kingdom in the mid 1980s. WARRIOR II has been developed as a lighter, smaller diameter articulated welding robot which can be deployed on its umbilical down a stand pipe for remote docking with the manipulator system which delivers it to its work site. A key feature of WARRIOR II has been the development of a prototype spherical modular joint. The module provides the drive torque necessary to motivate the robot arm, acts as the joint bearing, has standard mechanical interfaces for the limb sections, accurately measures the joint angle and has cable services running through the centre. It can act either as a bend or rotate joint and the interconnecting limb sections need only to be simple tubular sections. A wide range of manipulator configurations to suit the access constraints of particular problems can be achieved with a set of joint modules and limb sections. A general purpose motion controller has also been developed which is capable of kinematically controlling any configuration of WARRIOR II thus contributing to the realisation of the concept of a general purpose tool which can be used over and over again, at short notice, in any situation where a high precision, light weight, versatile manipulator is required. (UK)

Heavy-Section Steel Irradiation Program on irradiation effects in light-water reactor pressure vessel materials

International Nuclear Information System (INIS)

Nanstad, R.K.; Corwin, W.R.; Alexander, D.J.; Haggag, F.M.; Iskander, S.K.; McCabe, D.E.; Sokolov, M.A.; Stoller, R.E.

1995-01-01

The safety of commercial light-water nuclear plants is highly dependent on the structural integrity of the reactor pressure vessel (RPV). In the absence of radiation damage to the RPV, fracture of the vessel is difficult to postulate. Exposure to high energy neutrons can result in embrittlement of radiation-sensitive RPV materials. The Heavy-Section Steel Irradiation (HSSI) Program at Oak Ridge National Laboratory, sponsored by the US Nuclear Regulatory Commission (USNRC), is assessing the effects of neutron irradiation on RPV material behavior, especially fracture toughness. The results of these and other studies are used by the USNRC in the evaluation of RPV integrity and regulation of overall nuclear plant safety. In assessing the effects of irradiation, prototypic RPV materials are characterized in the unirradiated condition and exposed to radiation under varying conditions. Mechanical property tests are conducted to provide data which can be used in the development of guidelines for structural integrity evaluations, while metallurgical examinations and mechanistic modeling are performed to improve understanding of the mechanisms responsible for embrittlement. The results of these investigations, in conjunction with results from commercial reactor surveillance programs, are used to develop a methodology for the prediction of radiation effects on RPV materials. This irradiation-induced degradation of the materials can be mitigated by thermal annealing, i.e., heating the RPV to a temperature above that of normal operation. Thus, thermal annealing and evaluation of reirradiation behavior are major tasks of the HSSI Program. This paper describes the HSSI Program activities by summarizing some past and recent results, as well as current and planned studies. 30 refs., 8 figs., 1 tab

High Resolution Autostereoscopic Cockpit Display, Phase II

Data.gov (United States)

National Aeronautics and Space Administration — During this Phase II program Dimension Technologies Inc. (DTI) proposes to design and build an autostereoscopic (glasses-free 3D) LCD based aircraft cockpit display...

Probing HeII Reionization at z>3.5 with Resolved HeII Lyman Alpha Forest Spectra

Science.gov (United States)

Worseck, Gabor

2017-08-01

The advent of GALEX and COS have revolutionized our view of HeII reionization, the final major phase transition of the intergalactic medium. COS spectra of the HeII Lyman alpha forest have confirmed with high confidence the high HeII transmission that signifies the completion of HeII reionization at z 2.7. However, the handful of z>3.5 quasars observed to date show a set of HeII transmission 'spikes' and larger regions with non-zero transmission that suggest HeII reionization was well underway by z=4. This is in striking conflict with predictions from state-of-the-art radiative transfer simulations of a HeII reionization driven by bright quasars. Explaining these measurements may require either faint quasars or more exotic sources of hard photons at z>4, with concomitant implications for HI reionization. However, many of the observed spikes are unresolved in G140L spectra and are significantly impacted by Poisson noise. Current data cannot reliably probe the ionization state of helium at z>3.5.We request 41 orbits to obtain science-grade G130M spectra of the two UV-brightest HeII-transmitting QSOs at z>3.5 to confirm and resolve their HeII transmission spikes as an unequivocal test of early HeII reionization. These spectra are complemented by recently obtained data from 8m telescopes: (1) Echelle spectra of the coeval HI Lya forest to map the underlying density field that modulates the HeII absorption, and (2) Our dedicated survey for foreground QSOs that may source the HeII transmission. Our recent HST programs revealed the only two viable targets to resolve the z>3.5 HeII Lyman alpha forest, and to conclusively solve this riddle.

Mn(II), Zn(II) and VO(II) Schiff

Indian Academy of Sciences (India)

Home; Journals; Journal of Chemical Sciences; Volume 113; Issue 3. Synthesis and characterisation of Cu(II), Ni(II), Mn(II), Zn(II) and VO(II) Schiff base complexes derived from o-phenylenediamine and acetoacetanilide. N Raman Y Pitchaikani Raja A Kulandaisamy. Inorganic Volume 113 Issue 3 June 2001 pp 183-189 ...

NSLS-II commissioning and operation

Energy Technology Data Exchange (ETDEWEB)

Wang, G., E-mail: gwang@bnl.gov; Shaftan, T.; Bassi, G.; Bengtsson, J.; Blednykh, A.; Blum, E.; Cheng, W.; Choi, J.; Davidsaver, M.; Doom, L.; Fliller, R.; Ganetis, G.; Guo, W.; Hidaka, Y.; Kramer, S.; Li, Y.; Podobedov, B.; Qian, K.; Rose, J.; Seletskiy, S. [Brookhaven National Laboratory, Upton, NY 11973 (United States); and others

2016-07-27

The National Synchrotron Light Source II at Brookhaven National Lab is a third-generation synchrotron radiation facility that has been commissioned in 2014. The facility is based on a 3 GeV electron storage ring, which will circulate 500 mA of beam current at 1 nm rad horizontal emittance. The storage ring is 792 meters in circumference and will accommodate more than 60 beamlines in the final built-out. The beamline sources range from insertion-devices located in straight sections, bending magnets or three-pole-wigglers configured in multiple branches. The NSLS-II storage ring commissioning was successfully completed in July 2014 and the facility delivered the first user light on October 23, 2014. Currently the storage ring reached 300 mA beam current and achieved 1 nm rad of horizontal emittance with 3 sets of Damping Wigglers. At this point six NSLS-II project beamlines are routinely taking photons with beam current at 150 mA. This paper reviews the NSLS-II accelerator design and commissioning experience.

Technical Support Section Instrument Support Program for nuclear and nonnuclear facilities with safety requirements

International Nuclear Information System (INIS)

Adkisson, B.P.; Allison, K.L.

1995-01-01

This document describes requirements, procedures, and supervisory responsibilities of the Oak Ridge National Laboratory (ORNL) Instrumentation and Controls (I ampersand C) Division's Technical Support Section (TSS) for instrument surveillance and maintenance in nonreactor nuclear facilities having identified Operational Safety Requirements (OSRs) or Limiting Conditions Document (LCDs). Implementation of requirements comply with the requirements of U.S. Department of Energy (DOE) Orders 5480.5, 5480.22, and 5481.1B; Martin Marietta Energy Systems, Inc. (Energy Systems), Policy Procedure ESS-FS-201; and ORNL SPP X-ESH-15. OSRs and LCDs constitute an agreement or contract between DOE and the facility operating management regarding the safe operation of the facility. One basic difference between OSRs and LCDs is that violation of an OSR is considered a Category II occurrence, whereas violation of an LCD requirement is considered a Category III occurrence (see Energy Systems Standard ESS-OP-301 and ORNL SPP X-GP-13). OSRs are required for high- and moderate-hazard nuclear facilities, whereas the less-rigorous LCDs are required for low-hazard nuclear facilities and selected open-quotes generally acceptedclose quotes operations. Hazard classifications are determined through a hazard screening process, which each division conducts for its facilities

Examination of DSM-5 Section III avoidant personality disorder in a community sample.

Science.gov (United States)

Sellbom, Martin; Carmichael, Kieran L C; Liggett, Jacqueline

2017-11-01

The current research evaluated the continuity between DSM-5 Section II and Section III diagnostic operationalizations of avoidant personality disorder (AvPD). More specifically, the study had three aims: (1) to examine which personality constructs comprise the optimal trait constellation for AvPD; (2) to investigate the utility of the proposed structure of the Section III AvPD diagnosis, in regard to combining functional impairment (criterion A) and a dimensional measure of personality (criterion B) variables; and (3) to determine whether AvPD-specific impairment confers incremental meaningful contribution above and beyond general impairment in personality functioning. A mixed sample of 402 university and community participants was recruited, and they were administered multiple measures of Section II PD, personality traits, and personality impairment. A latent measurement model approach was used to analyse data. Results supported the general continuity between Section II and Section III of the DSM-5; however, three of the four main criterion B traits were the stronger predictors. There was also some support for the trait unassertiveness augmenting the criterion B trait profile. The combination of using functional impairment criteria (criterion A) and dimensional personality constructs (criterion B) in operationalizing AvPD was supported; however, the reliance of disorder-specific over general impairment for criterion A was not supported. Copyright © 2017 John Wiley & Sons, Ltd. Copyright © 2017 John Wiley & Sons, Ltd.

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…

Silver Biocide Analysis & Control Device, Phase II

Data.gov (United States)

National Aeronautics and Space Administration — Rapid, accurate measurement and process control of silver ion biocide concentrations in future space missions is needed. The purpose of the Phase II program is to...

Jet physics at CDF Run II

Energy Technology Data Exchange (ETDEWEB)

Safonov, A.; /UC, Davis

2004-12-01

The latest results on jet physics at CDF are presented and discussed. Particular attention is paid to studies of the inclusive jet cross section using 177 pb{sup -1} of Run II data. Also discussed is a study of gluon and quark jet fragmentation.

Solar fusion cross sections II: the pp chain and CNO cycles

Energy Technology Data Exchange (ETDEWEB)

Adelberger, E G; Bemmerer, D; Bertulani, C A; Chen, J -W; Costantini, H; Couder, M; Cyburt, R; Davids, B; Freedman, S J; Gai, M; Garcia, A; Gazit, D; Gialanella, L; Greife, U; Hass, M; Heeger, K; Haxton, W C; Imbriani, G; Itahashi, T; Junghans, A; Kubodera, K; Langanke, K; Leitner, D; Leitner, M; Marcucci, L E; Motobayashi, T; Mukhamedzhanov, A; Nollett, Kenneth M; Nunes, F M; Park, T -S; Parker, P D; Prati, P; Ramsey-Musolf, M J; Hamish Robertson, R G; Schiavilla, R; Simpson, E C; Snover, K A; Spitaleri, C; Strieder, F; Suemmerer, K; Trautvetter, R E; Tribble, R E; Typel, S; Uberseder, E; Vetter, P; Wiescher, M

2011-04-01

The available data on nuclear fusion cross sections important to energy generation in the Sun and other hydrogen-burning stars and to solar neutrino production are summarized and critically evaluated. Recommended values and uncertainties are provided for key cross sections, and a recommended spectrum is given for 8B solar neutrinos. Opportunities for further increasing the precision of key rates are also discussed, including new facilities, new experimental techniques, and improvements in theory. This review, which summarizes the conclusions of a workshop held at the Institute for Nuclear Theory, Seattle, in January 2009, is intended as a 10-year update and supplement to 1998, Rev. Mod. Phys. 70, 1265.

Inclusive high-p_$\\perp$ b$\\bar{b}$cross section measurement at √s = 1.96-TeV

Energy Technology Data Exchange (ETDEWEB)

Galyaev, Eugene N. [Univ. of Notre Dame, IN (United States)

2006-11-01

The Run II physics program at the Tevatron started in the spring of 2001 with protons and antiprotons colliding at an energy of √s = 1.96 TeV, and is continuing with about 1.2 fb^-1 of data currently collected by the CDF and D0 experiments. A measurement of the b-jet cross section as function of jet transverse momentum p_$\\perp$ has been performed using 312 pb^-1 of D0 data. The results for this measurement were obtained and are presented herein. A neural network algorithm was used to identify b jets.

The Soreq Applied Research Accelerator Facility (SARAF): Overview, research programs and future plans

Science.gov (United States)

Mardor, Israel; Aviv, Ofer; Avrigeanu, Marilena; Berkovits, Dan; Dahan, Adi; Dickel, Timo; Eliyahu, Ilan; Gai, Moshe; Gavish-Segev, Inbal; Halfon, Shlomi; Hass, Michael; Hirsh, Tsviki; Kaiser, Boaz; Kijel, Daniel; Kreisel, Arik; Mishnayot, Yonatan; Mukul, Ish; Ohayon, Ben; Paul, Michael; Perry, Amichay; Rahangdale, Hitesh; Rodnizki, Jacob; Ron, Guy; Sasson-Zukran, Revital; Shor, Asher; Silverman, Ido; Tessler, Moshe; Vaintraub, Sergey; Weissman, Leo

2018-05-01

The Soreq Applied Research Accelerator Facility (SARAF) is under construction in the Soreq Nuclear Research Center at Yavne, Israel. When completed at the beginning of the next decade, SARAF will be a user facility for basic and applied nuclear physics, based on a 40 MeV, 5 mA CW proton/deuteron superconducting linear accelerator. Phase I of SARAF (SARAF-I, 4 MeV, 2 mA CW protons, 5 MeV 1 mA CW deuterons) is already in operation, generating scientific results in several fields of interest. The main ongoing program at SARAF-I is the production of 30 keV neutrons and measurement of Maxwellian Averaged Cross Sections (MACS), important for the astrophysical s-process. The world leading Maxwellian epithermal neutron yield at SARAF-I (5 × 10^{10} epithermal neutrons/s), generated by a novel Liquid-Lithium Target (LiLiT), enables improved precision of known MACSs, and new measurements of low-abundance and radioactive isotopes. Research plans for SARAF-II span several disciplines: precision studies of beyond-Standard-Model effects by trapping light exotic radioisotopes, such as 6He, 8Li and 18, 19, 23Ne, in unprecedented amounts (including meaningful studies already at SARAF-I); extended nuclear astrophysics research with higher energy neutrons, including generation and studies of exotic neutron-rich isotopes relevant to the rapid (r-) process; nuclear structure of exotic isotopes; high energy neutron cross sections for basic nuclear physics and material science research, including neutron induced radiation damage; neutron based imaging and therapy; and novel radiopharmaceuticals development and production. In this paper we present a technical overview of SARAF-I and II, including a description of the accelerator and its irradiation targets; a survey of existing research programs at SARAF-I; and the research potential at the completed facility (SARAF-II).

Transfer of modified 9Cr-1Mo steel technology through cooperative programs (1980-1985)

International Nuclear Information System (INIS)

Sikka, V.K.; DiStefano, J.R.; Patriarca, P.

1986-06-01

The principal objective of the United States Department of Energy (DOE) 9Cr-1Mo steel development program has been to provide the data and analyses required by designers for use of the alloy in advanced liquid metal reactors to reduce technical tasks and plant capital costs. It was recognized early that designers would not consider use of any material for nuclear applications unless there was a considerable body of experience already established. Toward this end, the plan has been to get the alloy accepted in Section I (Power Boilers), Section II (Materials Specifications), Section VIII (Pressure Vessels), and Section III (Nuclear power Plant Components) of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (BPV) Code as logical steps in the process. To achieve this objective, extensive interaction with the industrial community was considered mandatory. Accordingly, an intensive effort to achieve technology transfer was initiated, which resulted in the involvement of many organizations. This report is a compilation of 47 status sheets describing 35 participating organizations and funding sources, purpose of the interactions, material and product forms utilized, summary of the work completed, findings, and appropriate references. These interactions contributed significantly toward the fulfillment of the program goals

PREFACE: Focus section on superconducting power systems Focus section on superconducting power systems

Science.gov (United States)

Cardwell, D. A.; Amemiya, N.; Fair, R.

2012-01-01

This focus section of Superconductor Science and Technology looks at the properties, technology and applications of (RE)BCO and MgB2 based superconductors for power engineering systems. Both bulk and conductor forms of material are addressed, including elements of materials fabrication and processing, and the measurement of their applied properties for various levels of system application. The areas of research include ac losses in type II materials in power devices, cables and coated conductors, the development of high current dc cables and the application of superconductors in levitation devices, motors and fault current limiters. This focus section presents a broad cross-section of contemporary issues, that represent state-of-the-art for power applications of superconductors, and highlights the areas that require further development if commercial applications of these rapidly emerging materials are to be realised. It contains papers from some of the major groups in the field, including contributions from Europe, the USA and Japan, and describes devices that are relatively close to market.

PEP-II vacuum system pressure profile modeling using EXCEL

International Nuclear Information System (INIS)

Nordby, M.; Perkins, C.

1994-06-01

A generic, adaptable Microsoft EXCEL program to simulate molecular flow in beam line vacuum systems is introduced. Modeling using finite-element approximation of the governing differential equation is discussed, as well as error estimation and program capabilities. The ease of use and flexibility of the spreadsheet-based program is demonstrated. PEP-II vacuum system models are reviewed and compared with analytical models

100 group displacement cross sections from RECOIL data base

International Nuclear Information System (INIS)

Gopalakrishnan, V.

1995-01-01

Displacement cross sections in 100 neutron energy groups were calculated from the RECOIL data base using the RECOIL program, for use in DPA (Displacement Per Atom) calculations for FBTR and PFBR materials. 100 group displacement cross sections were calculated using RECOIL-Data Base and RECOIL Program. Modifications were made in the data base to reduce space requirement, and in the program for easy handling on a PC. 2 refs

Inclusive neutral current ep cross sections with HERA II and two-dimensional unfolding

International Nuclear Information System (INIS)

Fischer, David-Johannes

2011-06-01

In this thesis, the inclusive neutral current ep → eX cross section at small e - scattering angles has been measured using the electromagnetic SpaCal calorimeter in the backward region of the H1 detector. This calorimeter constructed of lead and scintillating fiber was designed to measure the scattered electron with high resolution in both energy and polar angle. The analysis comprises the kinematic range of 0.06 e 2 e 2 2 for the squared momentum exchange. The data sample consists of positron proton collisions of the years 2006 and 2007, adding up to an integrated luminosity of ∝141 pb -1 . Due to the high luminosity of the HERA II run phase the accuracy is no longer limited by the data statistics but rather by the detector resolution and systematics. The migration becomes increasingly influential; an effect which leads to distortions of the measured distribution as well as to statistical correlations between adjacent data points. At this stage, the correction of detector effects as well as the precise determination of statistical correlations become important features of a rigorous error treatment. In this analysis two-dimensional unfolding has been applied. This is a novel approach to H1 inclusive cross section measurements, which are usually based on a bin-by-bin efficiency correction (bin-by-bin method). With unfolding, the detector effect to the measurements is modelled by a linear transformation (''response matrix'') which is used to correct any distortion of the data. The inclusion of off-diagonal elements results in a coherent assessment of the statistical uncertainties and correlations. The model dependence can be optimally evaluated. In this context, the bin-by-bin method can be viewed as an approximation based on a diagonal response matrix. In a scenario of limited detector resolution, the unfolded data distributions will typically exhibit strong fluctuations and correlations between the data points. This issue can be addressed by smoothing

Inclusive neutral current ep cross sections with HERA II and two-dimensional unfolding

Energy Technology Data Exchange (ETDEWEB)

Fischer, David-Johannes

2011-06-15

In this thesis, the inclusive neutral current ep {yields} eX cross section at small e{sup -} scattering angles has been measured using the electromagnetic SpaCal calorimeter in the backward region of the H1 detector. This calorimeter constructed of lead and scintillating fiber was designed to measure the scattered electron with high resolution in both energy and polar angle. The analysis comprises the kinematic range of 0.06 < y{sub e} < 0.6 for the inelasticity and 14 GeV{sup 2} < Q{sub e}{sup 2} < 110 GeV{sup 2} for the squared momentum exchange. The data sample consists of positron proton collisions of the years 2006 and 2007, adding up to an integrated luminosity of {proportional_to}141 pb{sup -1}. Due to the high luminosity of the HERA II run phase the accuracy is no longer limited by the data statistics but rather by the detector resolution and systematics. The migration becomes increasingly influential; an effect which leads to distortions of the measured distribution as well as to statistical correlations between adjacent data points. At this stage, the correction of detector effects as well as the precise determination of statistical correlations become important features of a rigorous error treatment. In this analysis two-dimensional unfolding has been applied. This is a novel approach to H1 inclusive cross section measurements, which are usually based on a bin-by-bin efficiency correction (bin-by-bin method). With unfolding, the detector effect to the measurements is modelled by a linear transformation (''response matrix'') which is used to correct any distortion of the data. The inclusion of off-diagonal elements results in a coherent assessment of the statistical uncertainties and correlations. The model dependence can be optimally evaluated. In this context, the bin-by-bin method can be viewed as an approximation based on a diagonal response matrix. In a scenario of limited detector resolution, the unfolded data distributions will

20 CFR 404.1321 - Ninety-day active service requirement for post-World War II veterans.

Science.gov (United States)

2010-04-01

... post-World War II veterans. 404.1321 Section 404.1321 Employees' Benefits SOCIAL SECURITY... of the Uniformed Services Post-World War II Veterans § 404.1321 Ninety-day active service requirement for post-World War II veterans. (a) The 90 days of active service required for post-World War II...

Specification and R and D Program on Magnet Alignment Tolerances for NSLS-II

International Nuclear Information System (INIS)

Kramer, S.L.; Jain, A.K.

2009-01-01

The NSLS-II light source is a proposed 3 GeV storage ring, with the potential for ultra-low emittance. Despite the reduced emittance goal for the bare lattice, the closed orbit amplification factors are on average >55 in both planes, for random quadrupole alignment errors. The high chromaticity will also require strong sextupoles and the low 3 GeV energy will require large dynamic and momentum aperture to insure adequate lifetime. This will require tight alignment tolerances (∼ 30(micro)m) on the multipole magnets during installation. By specifying tight alignment tolerances of the magnets on the support girders, the random alignment tolerances of the girders in the tunnel can be significantly relaxed. Using beam based alignment to find the golden orbit through the quadrupole centers, the closed orbit offsets in the multipole magnets will then be reduced to essentially the alignment errors of the magnets, restoring much of the dynamic aperture and lifetime of the bare lattice. Our R and D program to achieve these tight alignment tolerances of the magnets on the girders using a vibrating wire technique, will be discussed and initial results presented.

Measurement of the Inclusive Jet Cross Section using the k(T) algorithm in p anti-p collisions at s**(1/2) = 1.96-TeV with the CDF II Detector

Energy Technology Data Exchange (ETDEWEB)

Abulencia, A.; /Illinois U., Urbana; Adelman, J.; /Chicago U., EFI; Affolder, Anthony Allen; /UC, Santa Barbara; Akimoto, T.; /Tsukuba U.; Albrow, Michael G.; /Fermilab; Ambrose, D.; /Fermilab; Amerio, S.; /Padua U.; Amidei, Dante E.; /Michigan U.; Anastassov, A.; /Rutgers U., Piscataway; Anikeev, Konstantin; /Fermilab; Annovi, A.; /Frascati /Comenius U.

2007-01-01

The authors report on measurements of the inclusive jet production cross section as a function of the jet transverse momentum in p{bar p} collisions at {radical}s = 1.96 TeV, using the k{sub T} algorithm and a data sample corresponding to 1.0 fb{sup -1} collected with the Collider Detector at Fermilab in Run II. The measurements are carried out in five different jet rapidity regions with |y{sup jet}| < 2.1 and transverse momentum in the range 54 < p{sub T}{sup jet} < 700 GeV/c. Next-to-leading order perturbative QCD predictions are in good agreement with the measured cross sections.

COMBINE7.0 - A Portable ENDF/B-VII.0 Based Neutron Spectrum and Cross-Section Generation Program

Energy Technology Data Exchange (ETDEWEB)

Woo Y. Yoon; David W. Nigg

2008-09-01

COMBINE7.0 is a FORTRAN 90 computer code that generates multigroup neutron constants for use in the deterministic diffusion and transport theory neutronics analysis. The cross-section database used by COMBINE7.0 is derived from the Evaluated Nuclear Data Files (ENDF/B-VII.0). The neutron energy range covered is from 20 MeV to 1.0E-5 eV. The Los Alamos National Laboratory NJOY code is used as the processing code to generate a 167 finegroup cross-section library in MATXS format for Bondarenko self-shielding treatment. Resolved resonance parameters are extracted from ENDF/B-VII.0 File 2 for a separate library to be used in an alternate Nordheim self-shielding treatment in the resolved resonance energy range. The equations solved for energy dependent neutron spectrum in the 167 fine-group structure are the B-3 or B-1 approximations to the transport equation. The fine group cross sections needed for the spectrum calculation are first prepared by Bondarenko selfshielding interpolation in terms of background cross section and temperature. The geometric lump effect, when present, is accounted for by augmenting the background cross section. Nordheim self-shielded fine group cross sections for a material having resolved resonance parameters overwrite correspondingly the existing self-shielded fine group cross sections when this option is used. The fine group cross sections in the thermal energy range are replaced by those selfshielded with the Amouyal/Benoist/Horowitz method in the three region geometry when this option is requested. COMBINE7.0 coalesces fine group cross sections into broad group macroscopic and microscopic constants. The coalescing is performed by utilizing fine-group fluxes and/or currents obtained by spectrum calculation as the weighting functions. The multigroup constant may be output in any of several standard formats including ANISN 14** free format, CCCC ISOTXS format, and AMPX working library format. ANISN-PC, a onedimensional, discrete

COMBINE7.0 - A Portable ENDF/B-VII.0 Based Neutron Spectrum and Cross-Section Generation Program

International Nuclear Information System (INIS)

Yoon, Woo Y.; Nigg, David W.

2008-01-01

COMBINE7.0 is a FORTRAN 90 computer code that generates multigroup neutron constants for use in the deterministic diffusion and transport theory neutronics analysis. The cross-section database used by COMBINE7.0 is derived from the Evaluated Nuclear Data Files (ENDF/B-VII.0). The neutron energy range covered is from 20 MeV to 1.0E-5 eV. The Los Alamos National Laboratory NJOY code is used as the processing code to generate a 167 finegroup cross-section library in MATXS format for Bondarenko self-shielding treatment. Resolved resonance parameters are extracted from ENDF/B-VII.0 File 2 for a separate library to be used in an alternate Nordheim self-shielding treatment in the resolved resonance energy range. The equations solved for energy dependent neutron spectrum in the 167 fine-group structure are the B-3 or B-1 approximations to the transport equation. The fine group cross sections needed for the spectrum calculation are first prepared by Bondarenko selfshielding interpolation in terms of background cross section and temperature. The geometric lump effect, when present, is accounted for by augmenting the background cross section. Nordheim self-shielded fine group cross sections for a material having resolved resonance parameters overwrite correspondingly the existing self-shielded fine group cross sections when this option is used. The fine group cross sections in the thermal energy range are replaced by those selfshielded with the Amouyal/Benoist/Horowitz method in the three region geometry when this option is requested. COMBINE7.0 coalesces fine group cross sections into broad group macroscopic and microscopic constants. The coalescing is performed by utilizing fine-group fluxes and/or currents obtained by spectrum calculation as the weighting functions. The multigroup constant may be output in any of several standard formats including ANISN 14** free format, CCCC ISOTXS format, and AMPX working library format. ANISN-PC, a onedimensional, discrete

Adsorption of Pb(II), Cu(II), Cd(II), Zn(II), Ni(II), Fe(II), and As(V) on bacterially produced metal sulfides.

Science.gov (United States)

Jong, Tony; Parry, David L

2004-07-01

The adsorption of Pb(II), Cu(II), Cd(II), Zn(II), Ni(II), Fe(II) and As(V) onto bacterially produced metal sulfide (BPMS) material was investigated using a batch equilibrium method. It was found that the sulfide material had adsorptive properties comparable with those of other adsorbents with respect to the specific uptake of a range of metals and, the levels to which dissolved metal concentrations in solution can be reduced. The percentage of adsorption increased with increasing pH and adsorbent dose, but decreased with increasing initial dissolved metal concentration. The pH of the solution was the most important parameter controlling adsorption of Cd(II), Cu(II), Fe(II), Ni(II), Pb(II), Zn(II), and As(V) by BPMS. The adsorption data were successfully modeled using the Langmuir adsorption isotherm. Desorption experiments showed that the reversibility of adsorption was low, suggesting high-affinity adsorption governed by chemisorption. The mechanism of adsorption for the divalent metals was thought to be the formation of strong, inner-sphere complexes involving surface hydroxyl groups. However, the mechanism for the adsorption of As(V) by BPMS appears to be distinct from that of surface hydroxyl exchange. These results have important implications to the management of metal sulfide sludge produced by bacterial sulfate reduction.

Measurement of the $W+$ jets differential cross-sections in $p\\bar{p}$ collisions at $\\sqrt{s} = 1.96$ TeV using the CDF II Detector

Energy Technology Data Exchange (ETDEWEB)

Driutti, Anna [Univ. of Udine (Italy)

2016-01-01

In this thesis the measurements of differential cross sections for the production of the $W$-boson in association with jets in $p\\bar{p}$ collisions at $\\sqrt{s} = 1.96$ TeV are presented. The measurements are based on 9.0 fb$^{-1}$ of CDF Run II data (i.e., the full dataset). Only events in which the W-boson decays leptonically (i.e., W → ev and W → μv)and at least one jet is present are considered. The lepton candidates are required to have a transverse energy $E^{\\ell}_T > 25$GeV and pseudorapidity in the range |n^ℓ| < 1 whereas, the jets are reconstructed using the JETCLU algorithm with a radius of 0.4 requiring transverse energy $E^{jet}_T > 25$GeV and pseudorapidity in the range |η^jet| < 2. The reconstructed W-boson transverse mass should be greater than 40GeV/c². The differential cross sections as a function of the jet multiplicity ($N$ > or = to 1, 2, 3, 4) and the leading jet transverse energy, are measured separately for each decay channel and then combined. For a meaningful comparison with theory the measured cross-sections are unfolded to remove detector effects. The resulting particle-level cross-sections are compared to theoretical predictions.

Cross sections of the lumped fission products for the AMZ library

International Nuclear Information System (INIS)

Ono, S.; Corcueca, R.P.; Nascimento, J.A.

1985-01-01

The preparation of the lumped fission product cross section for the AMZ library is described. For this purpose 100 nuclides were selected. The cross sections for each nuclide were generated by the NJOY code with evaluated nuclear data from ENDF/B-V, complemented with ENDF/B-IV data. A comparison is performed between the data obtained and the lumped fission product cross section of JFS-II [pt

Titanium Heat Pipe Thermal Plane, Phase II

Data.gov (United States)

National Aeronautics and Space Administration — The objective of the Phase II program is to complete the development of the titanium heat pipe thermal plane and establish all necessary steps for production of this...

Atlas of Comet Halley 1910 II

International Nuclear Information System (INIS)

Brandt, J.C.; Donn, B.

1986-01-01

An Atlas of Comet Halley 1910 II photographs and spectra is being prepared. The major section consists of 838 photographic observations from fifteen observatories around the world. Multiple images of many photographs are reproduced to bring out detail in the near nucleus region, in the coma and in the tail. The Atlas contains a total of 1209 photographic images of the 1910 apparition. In addition there are sections showing drawings from 1935 and 1910. A short section compares 1910 drawings and photographs. The final two sections display digitally processed images from 1910 and 1910 spectra. A three part appendix contains diagrams of various data associated with the 1910 apparition, a set of tables of all 1910 images and a bibliography

Corrosion and thermal plant section: 1983 review and 1984 programs

International Nuclear Information System (INIS)

Brown, J.

1984-01-01

The projects and achievements of the Corrosion and Thermal Plant Section in 1983 are reviewed. Proposed projects and objectives for 1984 are described in outline and an overview of the changes in direction of the work of the section is presented

Research on the display of nuclear cross-section library

International Nuclear Information System (INIS)

Huang Shien; Wang Kan; Yu Ganglin

2008-01-01

Minutely parsed the dot cross-section format (ACE format) data of the ENDF/ B-6.8 database, which is the foundation of the program that achieved the reading and related handling of ACE format data. This program achieved the plotting, zooming and comparing display functions of nuclear cross section-energy of ENDF/B-6.8 database. It also provides the standard picture formatting file output and/or standard text formatting file output of interesting nuclear data. It accomplished some appropriate validations of this program via the comparing between program results and reference data. (authors)

7 CFR 227.5 - Program funding.

Science.gov (United States)

2010-01-01

... Regulations of the Department of Agriculture (Continued) FOOD AND NUTRITION SERVICE, DEPARTMENT OF AGRICULTURE CHILD NUTRITION PROGRAMS NUTRITION EDUCATION AND TRAINING PROGRAM General § 227.5 Program funding. (a... related support personnel costs including fringe benefits and travel expenses, (ii) Undertaking a needs...

Fourier-transform infrared anisotropy in cross and parallel sections of tendon and articular cartilage

Directory of Open Access Journals (Sweden)

Bidthanapally Aruna

2008-10-01

Full Text Available Abstract Background Fourier Transform Infrared Imaging (FTIRI is used to investigate the amide anisotropies at different surfaces of a three-dimensional cartilage or tendon block. With the change in the polarization state of the incident infrared light, the resulting anisotropic behavior of the tissue structure is described here. Methods Thin sections (6 μm thick were obtained from three different surfaces of the canine tissue blocks and imaged at 6.25 μm pixel resolution. For each section, infrared imaging experiments were repeated thirteen times with the identical parameters except a 15° increment of the analyzer's angle in the 0° – 180° angular space. The anisotropies of amide I and amide II components were studied in order to probe the orientation of the collagen fibrils at different tissue surfaces. Results For tendon, the anisotropy of amide I and amide II components in parallel sections is comparable to that of regular sections; and tendon's cross sections show distinct, but weak anisotropic behavior for both the amide components. For articular cartilage, parallel sections in the superficial zone have the expected infrared anisotropy that is consistent with that of regular sections. The parallel sections in the radial zone, however, have a nearly isotropic amide II absorption and a distinct amide I anisotropy. Conclusion From the inconsistency in amide anisotropy between superficial to radial zone in parallel section results, a schematic model is used to explain the origins of these amide anisotropies in cartilage and tendon.