Alternatives for managing wastes from reactors and post-fission operations in the LWR fuel cycle. Volume 5. Appendices

Energy Technology Data Exchange (ETDEWEB)

1976-05-01

Volume V of the five-volume report consists of appendices, which provide supplementary information, with emphasis on characteristics of geologic formations that might be used for final storage or disposal. Appendix titles are: selected glossary; conversion factors; geologic isolation, including, (a) site selection factors for repositories of wastes in geologic media, (b) rock types--geologic occurrence, (c) glossary of geohydrologic terms, and (d) 217 references; the ocean floor; and, government regulations pertaining to the management of radioactive materials. (JGB)

Benefit-Cost Analysis of Integrated Paratransit Systems : Volume 6. Technical Appendices.

Science.gov (United States)

1979-09-01

This last volume, includes five technical appendices which document the methodologies used in the benefit-cost analysis. They are the following: Scenario analysis methodology; Impact estimation; Example of impact estimation; Sensitivity analysis; Agg...

Assessment of accident risks in the CRBRP. Volume 2. Appendices

Energy Technology Data Exchange (ETDEWEB)

None

1977-03-01

Appendices to Volume I include core-related accident-sequence definition, CRBRP risk-assessment sequence-probability determinations, failure-probability data, accident scenario evaluation, radioactive material release analysis, ex-core accident analysis, safety philosophy and design features, calculation of reactor accident consequences, sensitivity study, and risk from fires.

Airborne gamma-ray spectrometer and magnetometer survey: Monument Valley B, Utah, detail area. Volume II B. Final report

International Nuclear Information System (INIS)

1983-01-01

Volume II B contains appendices for: flight line maps; geology maps; explanation of geologic legend; flight line/geology maps; radiometric contour maps; magnetic contour maps; and geochemical factor analysis maps

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.

Portsmouth Gaseous Diffusion Plant expansion: final environmental statement. Volume 2. Appendices

International Nuclear Information System (INIS)

1977-09-01

Volume 2 is comprised of appendices: Portsmouth Gaseous Diffusion Plant Existing Facilities; Ecology; Civic Involvement; Social Analysis; Population Projections; Toxicity of Air Pollutants to Biota at Portsmouth Gaseous Diffusion Plant; and Assessment of Noise Effects of an Add-On to the Portsmouth Gaseous Diffusion Plant

Advanced Neutron Source enrichment study. Volume 2: Appendices -- Final report, Revision 12/94

International Nuclear Information System (INIS)

Bari, R.A.; Ludewig, H.; Weeks, J.

1994-01-01

A study has been performed of the impact on performance of using low enriched uranium (20% 235 U) or medium enriched uranium (35% 235 U) as an alternative fuel for the Advanced Neutron Source, which is currently designed to use uranium enriched to 93% 235 U. Higher fuel densities and larger volume cores were evaluated at the lower enrichments in terms of impact on neutron flux, safety, safeguards, technical feasibility, and cost. The feasibility of fabricating uranium silicide fuel at increasing material density was specifically addressed by a panel of international experts on research reactor fuels. The most viable alternative designs for the reactor at lower enrichments were identified and discussed. Several sensitivity analyses were performed to gain an understanding of the performance of the reactor at parametric values of power, fuel density, core volume, and enrichment that were interpolations between the boundary values imposed on the study or extrapolations from known technology. Volume 2 of this report contains 26 appendices containing results, meeting minutes, and fuel panel presentations. There are 26 appendices in this volume

Socioeconomic effects of the DOE Gas Centrifuge Enrichment Plant. Volume 2: appendices

International Nuclear Information System (INIS)

1979-01-01

Volume 2 contains 18 appendices: schools; fire protection; law enforcement; water and sewer systems; solid waste; health care; transportation; recreation; labor force; economic effects; finance; school finance; bibliography; contacts; project methodology; service impacts; reference tables; and response to comments

No-migration variance petition. Appendices C--J: Volume 5, Revision 1

Energy Technology Data Exchange (ETDEWEB)

1990-03-01

Volume V contains the appendices for: closure and post-closure plans; RCRA ground water monitoring waver; Waste Isolation Division Quality Program Manual; water quality sampling plan; WIPP Environmental Procedures Manual; sample handling and laboratory procedures; data analysis; and Annual Site Environmental Monitoring Report for the Waste Isolation Pilot Plant.

Yucca Mountain transportation routes: Preliminary characterization and risk analysis; Volume 2, Figures [and] Volume 3, Technical Appendices

Energy Technology Data Exchange (ETDEWEB)

Souleyrette, R.R. II; Sathisan, S.K.; di Bartolo, R. [Nevada Univ., Las Vegas, NV (United States). Transportation Research Center

1991-05-31

This report presents appendices related to the preliminary assessment and risk analysis for high-level radioactive waste transportation routes to the proposed Yucca Mountain Project repository. Information includes data on population density, traffic volume, ecologically sensitive areas, and accident history.

The environmental impact statement for the Nevada Test Site and off-site locations in the State of Nevada. Volume 1, Appendices A-F

International Nuclear Information System (INIS)

1996-01-01

This volume contains appendices to the named document. The Appendices are entitled (A) Description of Projects and Activities, (2) Federal Register Notice, (C) Relevant Regulatory Requirements, (D) Distribution Lists, (E) Impact Assessment Methods, and (F) Project-Specific Environmental Analysis

2004 Power marketing program final EIS - final environmental impact statement. Volume 2 - appendices

International Nuclear Information System (INIS)

1997-02-01

This volume contains appendices to the Final Environmental Impact Statement (FEIS) for the Power Marketing Program proposal of the Western Area Power Administration. The FEIS identified peaking power scheduling as the environmentally preferred alternative, and presented the analysis of alternatives and environmental impacts. Sixteen appendices to the FEIS are included in this document. The appendices are: Statutory and Legal Framework; Sierra Nevada Region Customer Groups and Economic Regions; Renewable Technology Cost Information Matrix; Hydrological Assumptions; Recreation Resources; Archaeological and Historical Resources; Incremental Power Resources; Air Quality Regulatory Structure; Energy Generation; Stage Contents Relationships for Regulating Reservoirs; Power Costs; Socioeconomic Impacts; Projected Air Resource Impacts; Land use, Water Quality, and Solid Waste Impact Factors; Draft Environmental Impact Statement Comments and Responses, and Contractor Disclosure Statements. 21 figs., 24 tabs

Airborne gamma-ray spectrometer and magnetometer survey: Monument Valley A, Utah, detail area. Volume II B. Final report

International Nuclear Information System (INIS)

1983-01-01

Volume II B contains appendices for: flight line maps; geology maps; explanation of geologic legend; flight line/geology maps; radiometric contour maps; magnetic contour maps; multi-variant analysis maps; and geochemical factor analysis maps

Developing maintainability for tokamak fusion power systems. Phase I report. Volume II. Appendices

International Nuclear Information System (INIS)

Zahn, H.S.

1977-10-01

This volume contains the following appendices: (1) baseline large module time estimates, (2) baseline intermediate module time estimates, (3) baseline small module time estimates, (4) alternate concept estimates, (5) maintenance equipment concepts, (6) additional reactor design definition, and (7) TOCOMO supplements

No-migration variance petition. Appendices A--B: Volume 2, Revision 1

Energy Technology Data Exchange (ETDEWEB)

1990-03-01

Volume II contains Appendix A, emergency plan and Appendix B, waste analysis plan. The Waste Isolation Pilot Plant (WIPP) Emergency plan and Procedures (WP 12-9, Rev. 5, 1989) provides an organized plan of action for dealing with emergencies at the WIPP. A contingency plan is included which is in compliance with 40 CFR Part 265, Subpart D. The waste analysis plan provides a description of the chemical and physical characteristics of the wastes to be emplaced in the WIPP underground facility. A detailed discussion of the WIPP Waste Acceptance Criteria and the rationale for its established units are also included.

Developing maintainability for tokamak fusion power systems. Phase I report. Volume II. Appendices

Energy Technology Data Exchange (ETDEWEB)

Zahn, H.S.

1977-10-01

This volume contains the following appendices: (1) baseline large module time estimates, (2) baseline intermediate module time estimates, (3) baseline small module time estimates, (4) alternate concept estimates, (5) maintenance equipment concepts, (6) additional reactor design definition, and (7) TOCOMO supplements. (MOW)

Alternative fuels for vehicles fleet demonstration program. Final report, volume 2: Appendices

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-06-01

The Alternative Fuels for Vehicles Fleet Demonstration Program (AFV-FDP) was a multiyear effort to collect technical data for use in determining the costs and benefits of alternative-fuel vehicles (AFVs) in typical applications in New York State. This report, Volume 2, includes 13 appendices to Volume 1 that expand upon issues raised therein. Volume 1 provides: (1) Information about the purpose and scope of the AFV-FDP; (2) A summary of AFV-FDP findings organized on the basis of vehicle type and fuel type; (3) A short review of the status of AFV technology development, including examples of companies in the State that are active in developing AFVs and AFV components; and (4) A brief overview of the status of AFV deployment in the State. Volume 3 provides expanded reporting of AFV-FDP technical details, including the complete texts of the brochure Garage Guidelines for Alternative Fuels and the technical report Fleet Experience Survey Report, plus an extensive glossary of AFV terminology. The appendices cover a wide range of issues including: emissions regulations in New York State; production and health effects of ozone; vehicle emissions and control systems; emissions from heavy-duty engines; reformulated gasoline; greenhouse gases; production and characteristics of alternative fuels; the Energy Policy Act of 1992; the Clean Fuel Fleet Program; garage design guidelines for alternative fuels; surveys of fleet managers using alternative fuels; taxes on conventional and alternative fuels; and zero-emission vehicle technology.

Analysis of some nuclear waste management options. Volume II. Appendices

International Nuclear Information System (INIS)

Berman, L.E.; Ensminger, D.A.; Giuffre, M.S.; Koplik, C.M.; Oston, S.G.; Pollak, G.D.; Ross, B.I.

1978-01-01

This report describes risk analyses performed on that portion of a nuclear fuel cycle which begins following solidification of high-level waste. Risks associated with handling, interim storage and transportation of the waste are assessed, as well as the long term implications of disposal in deep mined cavities. The risk is expressed in terms of expected dose to the general population and peak dose to individuals in the population. This volume consists of appendices which provide technical details of the work performed

Analysis of some nuclear waste management options. Volume II. Appendices

Energy Technology Data Exchange (ETDEWEB)

Berman, L.E.; Ensminger, D.A.; Giuffre, M.S.; Koplik, C.M.; Oston, S.G.; Pollak, G.D.; Ross, B.I.

1978-10-10

This report describes risk analyses performed on that portion of a nuclear fuel cycle which begins following solidification of high-level waste. Risks associated with handling, interim storage and transportation of the waste are assessed, as well as the long term implications of disposal in deep mined cavities. The risk is expressed in terms of expected dose to the general population and peak dose to individuals in the population. This volume consists of appendices which provide technical details of the work performed.

An Evaluation of Project Learning Tree in British Columbia. Appendices.

Science.gov (United States)

Conry, Robert F.; And Others

The volume contains seven appendices (A-G) which accompany the first volume. Appendix A provides a list of project personnel and of teachers who participated in the unit development workshop. Appendix B, composed of six sections, includes the unit lesson plans and teachers' guides used in the field study for grades 3, 5, and 7. The grade materials…

Recommendations for a Department of Energy Nuclear Energy R and D Agenda Volume 2 Appendices

International Nuclear Information System (INIS)

1997-01-01

The current US nuclear energy policy is primarily formulated as part of the nation's overall energy policy. In addition, nuclear energy policy is impacted by other US policies, such as those for defense and environment, and by international obligations through their effects on nuclear weapons dismantlement and stewardship, continued reliance on space and naval nuclear power sources, defense waste cleanup, and on nuclear nonproliferation. This volume is composed of the following appendices: Appendix 1--Objectives of the Federal Government Nuclear Energy Related Policies and Research and Development Programs; Appendix 2--Nuclear Energy and Related R and D in the US; Appendix 3--Summary of Issues That Drive Nuclear Energy Research and Development; Appendix 4: Options for Policy and Research and Development; Appendix 5--Pros and Cons of Objectives and Options; and Appendices 6--Recommendations

Recommendations for a Department of Energy Nuclear Energy R and D Agenda Volume 2 Appendices

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-12-01

The current US nuclear energy policy is primarily formulated as part of the nation`s overall energy policy. In addition, nuclear energy policy is impacted by other US policies, such as those for defense and environment, and by international obligations through their effects on nuclear weapons dismantlement and stewardship, continued reliance on space and naval nuclear power sources, defense waste cleanup, and on nuclear nonproliferation. This volume is composed of the following appendices: Appendix 1--Objectives of the Federal Government Nuclear Energy Related Policies and Research and Development Programs; Appendix 2--Nuclear Energy and Related R and D in the US; Appendix 3--Summary of Issues That Drive Nuclear Energy Research and Development; Appendix 4: Options for Policy and Research and Development; Appendix 5--Pros and Cons of Objectives and Options; and Appendices 6--Recommendations.

Backfilling and sealing of tunnels, shafts and boreholes. Volume 2: Appendices

International Nuclear Information System (INIS)

Studer, J.; Ammann, W.; Meier, P.; Mueller, Ch.; Glauser, E.

1984-12-01

The present report is a synthesis of the state of knowledge regarding backfilling and sealing of nuclear waste repositories. It is based on an evaluation of both the general and special publications concerning this problem (articles in scientific journals, research reports, conference papers and textbooks) and represents the state of knowledge up to summer 1984. In addition, it contains an outlook on the continuing work. This will serve to broaden the scientific base and to achieve the technical as well as economical optimization. The report consists of two volumes: Volume 1 Main Part, Volume 2 Appendices. Starting with the functions of backfilling and sealing in the safety concept assessment criteria and from these, taking into consideration the given conditions in the project 'Gewaehr 1985' ('Guarantee'), the requirements for the backfilling and sealing materials are formulated. The properties of several materials under consideration are discussed in the Appendix together with a detailed description of the most important of these materials. The reasons are given for the choice of the proposed materials for the project 'Gewaehr 1985'. Alternative backfilling and sealing concepts for repositories Type B and Type C are presented and reasons are given for the selected variants for the project 'Gewaehr 1985'. Chapter 10 represents a review of the report. This report is intended as a reference work for the corresponding chapters in the NGB reports (cf. /NGB 85-03, 1985/, /NGB 85-06, 1985/). (author)

Technical area status report for chemical/physical treatment. Volume 2, Appendices

Energy Technology Data Exchange (ETDEWEB)

Brown, C.H. Jr. [Oak Ridge National Lab., TN (United States); Schwinkendorf, W.E. [BDM Federal, Inc., Arlington, VA (United States)

1993-08-01

These Appendices describe various technologies that may be applicable to the Mixed Waste Treatment Plant (MWTP) Chemical/Physical Treatment System (CPTS). These technologies were identified by the CPTS Technical Support Group (TSG) as potentially applicable to a variety of separation, volume reduction, and decontamination requirements. The purpose was to identify all available and developing technologies, and their characteristics, for subsequent evaluation for specific requirements identified for the CPTS. However, the technologies described herein are not necessarily all inclusive, nor are they necessarily all applicable.

Probabilistic accident consequence uncertainty analysis: Food chain uncertainty assessment. Volume 2: Appendices

Energy Technology Data Exchange (ETDEWEB)

Brown, J. [National Radiological Protection Board (United Kingdom); Goossens, L.H.J.; Kraan, B.C.P. [Delft Univ. of Technology (Netherlands)] [and others

1997-06-01

This volume is the second of a two-volume document that summarizes a joint project by the US Nuclear Regulatory and the Commission of European Communities to assess uncertainties in the MACCS and COSYMA probabilistic accident consequence codes. These codes were developed primarily for estimating the risks presented by nuclear reactors based on postulated frequencies and magnitudes of potential accidents. This two-volume report, which examines mechanisms and uncertainties of transfer through the food chain, is the first in a series of five such reports. A panel of sixteen experts was formed to compile credible and traceable uncertainty distributions for food chain transfer that affect calculations of offsite radiological consequences. Seven of the experts reported on transfer into the food chain through soil and plants, nine reported on transfer via food products from animals, and two reported on both. The expert judgment elicitation procedure and its outcomes are described in these volumes. This volume contains seven appendices. Appendix A presents a brief discussion of the MAACS and COSYMA model codes. Appendix B is the structure document and elicitation questionnaire for the expert panel on soils and plants. Appendix C presents the rationales and responses of each of the members of the soils and plants expert panel. Appendix D is the structure document and elicitation questionnaire for the expert panel on animal transfer. The rationales and responses of each of the experts on animal transfer are given in Appendix E. Brief biographies of the food chain expert panel members are provided in Appendix F. Aggregated results of expert responses are presented in graph format in Appendix G.

Probabilistic accident consequence uncertainty analysis: Food chain uncertainty assessment. Volume 2: Appendices

International Nuclear Information System (INIS)

Brown, J.; Goossens, L.H.J.; Kraan, B.C.P.

1997-06-01

This volume is the second of a two-volume document that summarizes a joint project by the US Nuclear Regulatory and the Commission of European Communities to assess uncertainties in the MACCS and COSYMA probabilistic accident consequence codes. These codes were developed primarily for estimating the risks presented by nuclear reactors based on postulated frequencies and magnitudes of potential accidents. This two-volume report, which examines mechanisms and uncertainties of transfer through the food chain, is the first in a series of five such reports. A panel of sixteen experts was formed to compile credible and traceable uncertainty distributions for food chain transfer that affect calculations of offsite radiological consequences. Seven of the experts reported on transfer into the food chain through soil and plants, nine reported on transfer via food products from animals, and two reported on both. The expert judgment elicitation procedure and its outcomes are described in these volumes. This volume contains seven appendices. Appendix A presents a brief discussion of the MAACS and COSYMA model codes. Appendix B is the structure document and elicitation questionnaire for the expert panel on soils and plants. Appendix C presents the rationales and responses of each of the members of the soils and plants expert panel. Appendix D is the structure document and elicitation questionnaire for the expert panel on animal transfer. The rationales and responses of each of the experts on animal transfer are given in Appendix E. Brief biographies of the food chain expert panel members are provided in Appendix F. Aggregated results of expert responses are presented in graph format in Appendix G

Siting, design and cost of shallow land burial facilities in Northern New England. Volume 2. Appendices A-G

International Nuclear Information System (INIS)

1985-05-01

Volume 2 comprises the following Appendices: Existing Environmental Data Base in Maine; Wetland Definition and Classification; Marine Clay; Screening Study; Basal Till Screening Study; Engineering Design Specifications and Costing; New York State Low-Level Radioactive Waste Management; and Maine Yankee's Cost of Low-Level Waste Disposal - 1973-1983

Data package for the Low-Level Waste Disposal Development and Demonstration Program environmental impact statement: Volume 2, Appendices E-O

Energy Technology Data Exchange (ETDEWEB)

Ketelle, R.H.

1988-09-01

This volume contains 11 appendices to the main document in Volume 1. Topics in Volume 2 include hydrologic data for a proposed solid waste storage area, soil characterizations, well logs, surface water discharge data, water quality data, atmospheric precipitation and stream flow, a small mammal survey, and general ecological information. (TEM)

Solar central receiver hybrid power system, Phase I. Volume 3. Appendices. Final technical report, October 1978-August 1979

Energy Technology Data Exchange (ETDEWEB)

None

1979-09-01

A design study for a central receiver/fossil fuel hybrid power system using molten salts for heat transfer and heat storage is presented. This volume contains the appendices: (A) parametric salt piping data; (B) sample heat exchanger calculations; (C) salt chemistry and salt/materials compatibility evaluation; (D) heliostat field coordinates; (E) data lists; (F) STEAEC program input data; (G) hybrid receiver design drawings; (H) hybrid receiver absorber tube thermal math model; (I) piping stress analysis; (J) 100-MWe 18-hour storage solar central receiver hybrid power system capital cost worksheets; and (K) 500-MWe 18-hour solar central receiver hybrid power system cost breakdown. (WHK)

N+3 Aircraft Concept Designs and Trade Studies. Volume 2; Appendices-Design Methodologies for Aerodynamics, Structures, Weight, and Thermodynamic Cycles

Science.gov (United States)

Greitzer, E. M.; Bonnefoy, P. A.; delaRosaBlanco, E.; Dorbian, C. S.; Drela, M.; Hall, D. K.; Hansman, R. J.; Hileman, J. I.; Liebeck, R. H.; Lovegren, J.;

Remedial actions at the former Vanadium Corporation of America uranium mill site, Durango, La Plata County, Colorado. Volume II. Appendices. Final Environmental Impact Statement

International Nuclear Information System (INIS)

1985-10-01

Volume 2 contains the following: addendums to Appendices A - Conceptual Designs and Engineering Evaluations for Remedial Action Alternative 3b, D - Meteorological and Air-Quality Information, F - Water Resources Information, H - Radiological Information, I - Information on Populations, Socioeconomics, and Land Use; Appendix K - List of Agencies, Organizations, and Persons Receiving Copies of this Statement; Appendix L - Wildlife Mitigation Plan; Appendix M - Seismic Evaluation; Appendix N - Tourism Evaluation; and Appendix O - Permits, Licenses, and Approvals

Assessment of LWR spent fuel disposal options. Volume 3. Study bases and system design considerations (Appendices). Technical report

Energy Technology Data Exchange (ETDEWEB)

1979-07-01

Volume 3 (Appendices) provides a tabulation of the bases and assumptions used in the study as well as preconceptual design description and cost estimates of the facilities and transportation systems necessary to implement the various study cases.

Assessment of LWR spent fuel disposal options. Volume 3. Study bases and system design considerations (Appendices). Technical report

International Nuclear Information System (INIS)

1979-07-01

Volume 3 (Appendices) provides a tabulation of the bases and assumptions used in the study as well as preconceptual design description and cost estimates of the facilities and transportation systems necessary to implement the various study cases

Advisory Committee on human radiation experiments. Supplemental Volume 2a, Sources and documentation appendices. Final report

International Nuclear Information System (INIS)

1995-01-01

This large document provides a catalog of the location of large numbers of reports pertaining to the charge of the Presidential Advisory Committee on Human Radiation Research and is arranged as a series of appendices. Titles of the appendices are Appendix A- Records at the Washington National Records Center Reviewed in Whole or Part by DoD Personnel or Advisory Committee Staff; Appendix B- Brief Descriptions of Records Accessions in the Advisory Committee on Human Radiation Experiments (ACHRE) Research Document Collection; Appendix C- Bibliography of Secondary Sources Used by ACHRE; Appendix D- Brief Descriptions of Human Radiation Experiments Identified by ACHRE, and Indexes; Appendix E- Documents Cited in the ACHRE Final Report and other Separately Described Materials from the ACHRE Document Collection; Appendix F- Schedule of Advisory Committee Meetings and Meeting Documentation; and Appendix G- Technology Note

Advisory Committee on human radiation experiments. Supplemental Volume 2a, Sources and documentation appendices. Final report

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-01-01

This large document provides a catalog of the location of large numbers of reports pertaining to the charge of the Presidential Advisory Committee on Human Radiation Research and is arranged as a series of appendices. Titles of the appendices are Appendix A- Records at the Washington National Records Center Reviewed in Whole or Part by DoD Personnel or Advisory Committee Staff; Appendix B- Brief Descriptions of Records Accessions in the Advisory Committee on Human Radiation Experiments (ACHRE) Research Document Collection; Appendix C- Bibliography of Secondary Sources Used by ACHRE; Appendix D- Brief Descriptions of Human Radiation Experiments Identified by ACHRE, and Indexes; Appendix E- Documents Cited in the ACHRE Final Report and other Separately Described Materials from the ACHRE Document Collection; Appendix F- Schedule of Advisory Committee Meetings and Meeting Documentation; and Appendix G- Technology Note.

MELSAR: a mesoscale air quality model for complex terrain. Volume 2. Appendices

Energy Technology Data Exchange (ETDEWEB)

Allwine, K.J.; Whiteman, C.D.

1985-04-01

This final report is submitted as part of the Green River Ambient Model Assessment (GRAMA) project conducted at the US Department of Energy's Pacific Northwest Laboratory for the US Environmental Protection Agency. The GRAMA Program has, as its ultimate goal, the development of validated air quality models that can be applied to the complex terrain of the Green River Formation of western Colorado, eastern Utah and southern Wyoming. The Green River Formation is a geologic formation containing large reserves of oil shale, coal, and other natural resources. Development of these resources may lead to a degradation of the air quality of the region. Air quality models are needed immediately for planning and regulatory purposes to assess the magnitude of these regional impacts. This report documents one of the models being developed for this purpose within GRAMA - specifically a model to predict short averaging time (less than or equal to 24 h) pollutant concentrations resulting from the mesoscale transport of pollutant releases from multiple sources. MELSAR has not undergone any rigorous operational testing, sensitivity analyses, or validation studies. Testing and evaluation of the model are needed to gain a measure of confidence in the model's performance. This report consists of two volumes. This volume contains the Appendices, which include listings of the FORTRAN code and Volume 1 contains the model overview, technical description, and user's guide. 13 figs., 10 tabs.

DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 2: Appendices

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-05-01

This volume contains the appendices that provide additional environment, safety, and health (ES and H) information to complement Volume 1 of this Standard. Appendix A provides a set of candidate DOE ES and H directives and external regulations, organized by hazard types that may be used to identify potentially applicable directives to a specific facility disposition activity. Appendix B offers examples and lessons learned that illustrate implementation of ES and H approaches discussed in Section 3 of Volume 1. Appendix C contains ISMS performance expectations to guide a project team in developing and implementing an effective ISMS and in developing specific performance criteria for use in facility disposition. Appendix D provides guidance for identifying potential Applicable or Relevant and Appropriate Requirements (ARARs) when decommissioning facilities fall under the Comprehensive Environmental Response, Compensation, Liability Act (CERCLA) process. Appendix E discusses ES and H considerations for dispositioning facilities by privatization. Appendix F is an overview of the WSS process. Appendix G provides a copy of two DOE Office of Nuclear Safety Policy and Standards memoranda that form the bases for some of the guidance discussed within the Standard. Appendix H gives information on available hazard analysis techniques and references. Appendix I provides a supplemental discussion to Sections 3.3.4, Hazard Baseline Documentation, and 3.3.6, Environmental Permits. Appendix J presents a sample readiness evaluation checklist.

DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 2: Appendices

International Nuclear Information System (INIS)

1998-05-01

This volume contains the appendices that provide additional environment, safety, and health (ES and H) information to complement Volume 1 of this Standard. Appendix A provides a set of candidate DOE ES and H directives and external regulations, organized by hazard types that may be used to identify potentially applicable directives to a specific facility disposition activity. Appendix B offers examples and lessons learned that illustrate implementation of ES and H approaches discussed in Section 3 of Volume 1. Appendix C contains ISMS performance expectations to guide a project team in developing and implementing an effective ISMS and in developing specific performance criteria for use in facility disposition. Appendix D provides guidance for identifying potential Applicable or Relevant and Appropriate Requirements (ARARs) when decommissioning facilities fall under the Comprehensive Environmental Response, Compensation, Liability Act (CERCLA) process. Appendix E discusses ES and H considerations for dispositioning facilities by privatization. Appendix F is an overview of the WSS process. Appendix G provides a copy of two DOE Office of Nuclear Safety Policy and Standards memoranda that form the bases for some of the guidance discussed within the Standard. Appendix H gives information on available hazard analysis techniques and references. Appendix I provides a supplemental discussion to Sections 3.3.4, Hazard Baseline Documentation, and 3.3.6, Environmental Permits. Appendix J presents a sample readiness evaluation checklist

Appendiceal Diverticulitis Clinically Masquerading as an Appendiceal Carcinoma

Directory of Open Access Journals (Sweden)

Tadashi Terada

2014-01-01

Full Text Available Appendiceal diverticulosis is a rare condition. Herein reported is a case of appendiceal diverticulosis and diverticulitis clinically masquerading as appendiceal carcinoma. A 62-year-old woman presented with abdominal pain. US and CT showed a tumor measuring 5 × 4 × 4 cm in vermiform appendix. Colon endoscopy showed mucosal elevation and irregularity in the orifice of vermiform appendix. A biopsy of the appendiceal mucosa showed no significant changes. Clinical diagnosis was appendiceal carcinoma and wide excision of terminal ileum, appendix, cecum, and ascending colon was performed. Grossly, the appendix showed a tumor measuring 5 × 3 × 4 cm. The appendiceal lumen was opened, and the appendiceal mucosa was elevated and irregular. The periappendiceal tissue showed thickening. Microscopically, the lesion was multiple appendiceal diverticula. The diverticula were penetrating the muscle layer. The mucosa showed erosions in places. Much fibrosis, abscess formations, and lymphocytic infiltration were seen in the subserosa. Abscesses were also seen in the diverticular lumens. Some diverticula penetrated into the subserosa. The pathologic diagnosis was appendiceal diverticulitis. When they encounter an appendiceal mass, clinicians should consider appendiceal diverticulitis as a differential diagnosis.

US Fish and Wildlife Service biomonitoring operations manual, Appendices A--K

Energy Technology Data Exchange (ETDEWEB)

Gianotto, D.F.; Rope, R.C.; Mondecar, M.; Breckenridge, R.P.; Wiersma, G.B.; Staley, C.S.; Moser, R.S.; Sherwood, R.; Brown, K.W.

1993-04-01

Volume 2 contains Appendices and Summary Sheets for the following areas: A-Legislative Background and Key to Relevant Legislation, B- Biomonitoring Operations Workbook, C-Air Monitoring, D-Introduction to the Flora and Fauna for Biomonitoring, E-Decontamination Guidance Reference Field Methods, F-Documentation Guidance, Sample Handling, and Quality Assurance/Quality Control Standard Operating Procedures, G-Field Instrument Measurements Reference Field Methods, H-Ground Water Sampling Reference Field Methods, I-Sediment Sampling Reference Field Methods, J-Soil Sampling Reference Field Methods, K-Surface Water Reference Field Methods. Appendix B explains how to set up strategy to enter information on the ``disk workbook``. Appendix B is enhanced by DE97006389, an on-line workbook for users to be able to make revisions to their own biomonitoring data.

Plan for studies of subsurface radionuclide migration at the Radioactive Waste Management Complex of the Idaho National Engineering Laboratory. Volume 2 of 2. Appendices

International Nuclear Information System (INIS)

1983-11-01

This document describes planned studies of subsurface radionuclide migration at the Radioactive Waste Management Complex of the Idaho National Engineering Laboratory. A plan is provided for each proposed study. The rational for arriving at the list of proposed studies is also presented. This document consists of two volumes. In the first volume, Sections 1 through 5 contain the introduction, the objectives of the proposed studies, and background information. The discussion is not comprehensive in detail; documents are referenced that discuss the background material in greater detail. Sections 6 through 9 identify and select the group of studies to be performed and discuss the peer review process. The second volume contains Appendices A and B, which present the assignment of responsibilities and the detailed plans, schedules, and costs for the proposed program

Research reactor core conversion guidebook. V. 4: Fuels (Appendices I-K)

International Nuclear Information System (INIS)

1992-04-01

Volume 4 consists of detailed Appendices I-K, which contain useful information on the properties, irradiation testing, and specifications and inspection procedures for fuels with reduced uranium enrichments. Summaries of these appendices can be found in Chapters 9-11 of Volume 1 of this guidebook. Refs, figs, tabs and samples

1986 resource strategy technical appendices. Volume 2

International Nuclear Information System (INIS)

1986-01-01

The following appendices are included: Decision Analysis Model Documentation; WNP-1 and WNP-3 Preservation Cost Analysis; Regional Costs vs. Net Benefits; Supplemental Conservation Results; National Science Foundation (NSF) Definition of Research and Development; Research and Development: ''Short-Term'' Need and ''Long-Term'' Capability Building; and Value of Energy

Review of energy policy. Vol. 1. A discussion paper; Vol. 2. Appendices

Energy Technology Data Exchange (ETDEWEB)

1986-01-01

Following the accident at the Chernobyl reactor in April 1986, the 1986 Annual Delegate Conference of the Institution of Professional Civil Servants set up a Working Party to review the Institution's energy policy, including safety and environmental factors. The review is presented in two volumes as the basis for discussion by the members. Volume I is the main report. Section A, the introduction, includes a summary of the detailed conclusions and recommendations of the Working Party. Section B (chapters 4-12) concerns all aspects of nuclear power including fuel reprocessing and waste management. Section C (chapters 13-16) considers the alternatives to nuclear power and Section D (chapters 17-24) looks at the economic and social aspects of energy policy. The appendices, which contain the detailed technical and source information used by the Working Party in reaching its conclusions, are printed separately in Volume II.

Alkaline Waterflooding Demonstration Project, Ranger Zone, Long Beach Unit, Wilmington Field, California. Fourth annual report, June 1979-May 1980. Volume 3. Appendices II-XVII

Energy Technology Data Exchange (ETDEWEB)

Carmichael, J.D.

1981-03-01

Volume 3 contains Appendices II through XVII: mixing instructions for sodium orthosilicate; oil displacement studies using THUMS C-331 crude oil and extracted reservoir core material from well B-110; clay mineral analysis of B-827-A cores; sieve analysis of 4 Fo sand samples from B-110-IA and 4 Fo sand samples from B-827-A; core record; delayed secondary caustic consumption tests; long-term alkaline consumption in reservoir sands; demulsification study for THUMS Long Beach Company, Island White; operating plans and instructions for DOE injection demonstration project, alkaline injection; caustic pilot-produced water test graphs; well test irregularities (6/1/79-5/31/80); alkaline flood pump changes (6/1/79-5/31/80); monthly DOE pilot chemical waterflood injection reports (preflush injection, alkaline-salt injection, and alkaline injection without salt); and caustic safety procedures-alkaline chemicals.

Kress indirect dry cooling system, Bethlehem Steel's Coke Plant demonstration at Sparrows Point, Maryland. Volume 2. Appendices G-N. Final report, February 1990-February 1992

International Nuclear Information System (INIS)

Ossman, A.G.

1993-05-01

The report provides an evaluation of the Kress Indirect Dry Cooling (KIDC) process. The KIDC process is an innovative system for the handling and cooling of coke produced from a slot type by-product coke oven battery. The report is based on the test work and demonstration of the system at Bethlehem Steel Corporation's Sparrows Point facility in 1991. The report covers both environmental and operational impacts of the KIDC process. The report, Volume 2, contains appendices G-N. Volume 1, PB93-191302, contains the technical report as well as appendices A-F. Volume 2 contains appendixes on coke quality data, blast furnace balwax model report, KIDC operating cost and maintenance requirements, Kress box thickness readings, KIDC coke discharge temperature, QA/QC program, door leak data, and coal data

State of the Art Report on Fracture Mechanics (Fracture in the Creep Range). Volume 2: Appendices A - G

International Nuclear Information System (INIS)

Ellison, E.G.; Musicco, G.G.; Pineau, A.

1988-01-01

A CEC State of the Art Report on Fracture Mechanics for Fast Breeder Reactors (Fracture below the Creep Range) has recently been published by Bhandari and coworkers (1984). There has also been a compilation of Creep Crack Growth Data from Germany, France and the U.K. for 304 and 316 stainles steel by Lloyd et al (1984). The present Report provides considerably more data and analytical techniques taken from Worldwide sources on creep crack initiation and propagation. Since the subject is moving quickly there is an emphasis on the most recent work; indeed research studies as yet unpublished are also included. The total Report is in 3 volumes. Volume 2 contains the most important and up-to-date information in some detail in Appendices A to G; this provides a sound base for the Report and for future workers

Laboratory Evaluation of In Situ Chemical Oxidation for Groundwater Remediation, Test Area North, Operable Unit 1-07B, Idaho National Engineering and Environmental Laboratory, Volume Two, Appendices C, D, and E

Energy Technology Data Exchange (ETDEWEB)

Cline, S.R.; Denton, D.L.; Giaquinto, J.M.; McCracken, M.K.; Starr, R.C.

1999-04-01

These appendices support the results and discussion of the laboratory work performed to evaluate the feasibility of in situ chemical oxidation for Idaho National Environmental and Engineering Laboratory's (INEEL) Test Area North (TAN) which is contained in ORNL/TM-1371 l/Vol. This volume contains Appendices C-E. Appendix C is a compilation of all recorded data and mathematical calculations made to interpret the data. For the Task 3 and Task 4 work, the spreadsheet column definitions are included immediately before the actual spreadsheet pages and are listed as ''Sample Calculations/Column Definitions'' in the table of contents. Appendix D includes the chronological order in which the experiments were conducted and the final project costs through October 1998. Appendix E is a compilation of the monthly progress reports submitted to INEEL during the course of the project.

Report to Congress on the feasibility of establishing a heating oil component to the Strategic Petroleum Reserve. Volume 2: Appendices

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-06-01

Nine appendices to the main report are included in this volume. They are: Northeastern US distillate supply systems; New England fuel oil storage capacities and inventories; Characteristics of the northeast natural gas market; Documentation of statistical models and calculation of benefits; Regional product reserve study; Other countries` experience with refined product storage; Global refining supply demand appraisal; Summary of federal authorities relevant to the establishment of petroleum product reserves; Product stability and turnover requirements.

Compliance problems of small utility systems with the Powerplant and Industrial Fuel Use Act of 1978: volume II - appendices

Energy Technology Data Exchange (ETDEWEB)

None

1981-01-01

A study of the problems of compliance with the Powerplant and Industrial Fuel Use Act of 1978 experienced by electric utility systems which have a total generating capacity of less than 2000 MW is presented. This volume presents the following appendices: (A) case studies (Farmington, New Mexico; Lamar, Colorado; Dover, Delaware; Wolverine Electric Cooperative, Michigan; Central Telephone and Utilities, Kansas; Sierra Pacific Power Company, Nevada; Vero Beach, Florida; Lubbock, Texas; Western Farmers Cooperative, Oklahoma; and West Texas Utilities Company, Texas); (B) contacts and responses to study; (C) joint action legislation chart; (D) Texas Municipal Power Agency case study; (E) existing generating units jointly owned with small utilities; (F) future generating units jointly owned with small utilities; (G) Federal Register Notice of April 17, 1980, and letter of inquiry to utilities; (H) small utility responses; and (I) Section 744, PIFUA. (WHK)

Characterization of Class A low-level radioactive waste 1986--1990. Volume 7: Appendices K--P

Energy Technology Data Exchange (ETDEWEB)

Dehmel, J.C.; Loomis, D.; Mauro, J. [S. Cohen & Associates, Inc., McLean, VA (United States); Kaplan, M. [Eastern Research Group, Inc., Lexington, MA (United States)

1994-01-01

Under contract to the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, the firms of S. Cohen & Associates, Inc. (SC&A) and Eastern Research Group (ERG) have compiled a report that describes the physical, chemical, and radiological properties of Class-A low-level radioactive waste. The report also presents information characterizing various methods and facilities used to treat and dispose non-radioactive waste. A database management program was developed for use in accessing, sorting, analyzing, and displaying the electronic data provided by EG&G. The program was used to present and aggregate data characterizing the radiological, physical, and chemical properties of the waste from descriptions contained in shipping manifests. The data thus retrieved are summarized in tables, histograms, and cumulative distribution curves presenting radionuclide concentration distributions in Class-A waste as a function of waste streams, by category of waste generators, and regions of the United States. The report also provides information characterizing methods and facilities used to treat and dispose non-radioactive waste, including industrial, municipal, and hazardous waste regulated under Subparts C and D of the Resource Conservation and Recovery Act (RCRA). The information includes a list of disposal options, the geographical locations of the processing and disposal facilities, and a description of the characteristics of such processing and disposal facilities. Volume 1 contains the Executive Summary, Volume 2 presents the Class-A waste database, Volume 3 presents the information characterizing non-radioactive waste management practices and facilities, and Volumes 4 through 7 contain Appendices A through P with supporting information.

BPA/Lower Valley transmission project. Final environmental impact statement. Appendices A, B, D, E, G-N

International Nuclear Information System (INIS)

1998-06-01

Bonneville Power Administration is investigating the feasibility of constructing an additional transmission line, which for the most part will be adjacent to the existing transmission line. This would require the construction or acquisition of additional access roads, used for routine and emergency maintenance and construction activities. A survey was conducted to map any occurrences of threatened, endangered and sensitivity plant species and weed species along the Swan Valley-Teton Line. This report contains Appendices A, B, D, E, G--N

Final Generic Environmental Impact Statement. Handling and storage of spent light water power reactor fuel. Volume 2. Appendices

International Nuclear Information System (INIS)

1979-08-01

This volume contains the following appendices: LWR fuel cycle, handling and storage of spent fuel, termination case considerations (use of coal-fired power plants to replace nuclear plants), increasing fuel storage capacity, spent fuel transshipment, spent fuel generation and storage data, characteristics of nuclear fuel, away-from-reactor storage concept, spent fuel storage requirements for higher projected nuclear generating capacity, and physical protection requirements and hypothetical sabotage events in a spent fuel storage facility

Airborne gamma-ray spectrometer and magnetometer survey: Monument Valley B, Utah, detail area. Volume II A. Final report

International Nuclear Information System (INIS)

1983-01-01

Volume II A contains appendices for: stacked profiles; geologic histograms; geochemical histograms; speed and altitude histograms; geologic statistical tables; geochemical statistical tables; magnetic and ancillary profiles; and test line data

Demonstration, testing, and evaluation of in situ heating of soil. Final report, Volume 2, Appendices A to E

International Nuclear Information System (INIS)

Dev, H.; Enk, J.; Jones, D.; Sabato, W.

1996-01-01

This is a final report presented in two volumes. Volume I contains the technical report and Volume II contains appendices with background information and data. In this project approximately 300 cubic yards of clayey soil containing a low concentration plume of volatile organic chemicals was heated in situ by the application of electrical energy. It was shown that as a result of heating the effective permeability of soil to air flow was increased such that in situ soil vapor extraction could be performed. The initial permeability of soil was so low that the soil gas flow rate was immeasurably small even at high vacuum levels. It was demonstrated that the mass flow rate of the volatile organic chemicals was enhanced in the recovered soil gas as a result of heating. When scaled up, this process can be used for the environmental clean up and restoration of DOE sites contaminated with VOC's and other organic chemicals. Although it may be applied to many types of soil formations, it is particularly attractive for low permeability clayey soil where conventional in situ venting techniques are limited by air flow

Demonstration, testing, and evaluation of in situ heating of soil. Final report, Volume 2, Appendices A to E

Energy Technology Data Exchange (ETDEWEB)

Dev, H.; Enk, J.; Jones, D.; Sabato, W.

1996-04-05

This is a final report presented in two volumes. Volume I contains the technical report and Volume II contains appendices with background information and data. In this project approximately 300 cubic yards of clayey soil containing a low concentration plume of volatile organic chemicals was heated in situ by the application of electrical energy. It was shown that as a result of heating the effective permeability of soil to air flow was increased such that in situ soil vapor extraction could be performed. The initial permeability of soil was so low that the soil gas flow rate was immeasurably small even at high vacuum levels. It was demonstrated that the mass flow rate of the volatile organic chemicals was enhanced in the recovered soil gas as a result of heating. When scaled up, this process can be used for the environmental clean up and restoration of DOE sites contaminated with VOC`s and other organic chemicals. Although it may be applied to many types of soil formations, it is particularly attractive for low permeability clayey soil where conventional in situ venting techniques are limited by air flow.

Final report from VFL Technologies for the pilot-scale thermal treatment of Lower East Fork Poplar Creek floodplain soils. LEFPC appendices. Volume 6. Appendix VI-X

International Nuclear Information System (INIS)

1994-09-01

This final report from VFL Technologies for the pilot-scale thermal treatment of lower East Fork Poplar Creek floodplain soils dated September 1994 contains LEFPC Appendices, Volume 6, Appendix VI - X. These appendices cover the following areas: chain of custody, miscellaneous process calculations (residence time and orifice plate calculations), waste management (mercury and radiation confirmatory testing before and after final verification run), health and safety (training, respirator fit test and radiation work permits), and transportation (soil receipt documentation)

Stirling Space Engine Program. Volume 2; Appendixes A, B, C and D

Science.gov (United States)

Dhar, Manmohan

1999-01-01

The objective of this program was to develop the technology necessary for operating Stirling power converters in a space environment and to demonstrate this technology in full-scale engine tests. Volume 2 of the report includes the following appendices: Appendix A: Heater Head Development (Starfish Heater Head Program, 1/10th Segment and Full-Scale Heat Pipes, and Sodium Filling and Processing); Appendix B: Component Test Power Converter (CTPC) Component Development (High-temperature Organic Materials, Heat Exchanger Fabrication, Beryllium Issues, Sodium Issues, Wear Couple Tests, Pressure Boundary Penetrations, Heating System Heaters, and Cooler Flow Test); Appendix C: Udimet Testing (Selection of the Reference Material for the Space Stirling Engine Heater Head, Udimet 720LI Creep Test Result Update, Final Summary of Space Stirling Endurance Engine Udimet 720L1 Fatigue Testing Results, Udimet 720l1 Weld Development Summary, and Udimet 720L1 Creep Test Final Results Summary), and Appendix D: CTPC Component Development Photos.

Initial Northwest Power Act Power Sales Contracts : Final Environmental Impact Statement. Volume 2, Appendices A--L.

Energy Technology Data Exchange (ETDEWEB)

United States. Bonneville Power Administration.

1992-01-01

This report consists of appendices A-L of the final environmental impact statement for the Bonneville Power Administration. The appendices provide information on the following: Ninth circuit Court opinion in Forelaws on Board v. Johnson; guide to Northwest Power act contracts; guide to hydro operations; glossary; affected environment supporting documentation; environmental impacts of generic resource types; information on models used; technical information on analysis; public involvement activities; bibliography; Pacific Northwest Electric Power Planning and Conservation Act; and biological assessment. (CBS)

Technology, safety and costs of decommissioning a reference boiling water reactor power station. Volume 2. Appendices. Technical report, September 1977-October 1979

International Nuclear Information System (INIS)

Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

1980-06-01

Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWE. This volume contains the appendices

Technology, safety and costs of decommissioning a reference boiling water reactor power station. Volume 2. Appendices. Technical report, September 1977-October 1979

Energy Technology Data Exchange (ETDEWEB)

Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

1980-06-01

Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWE. This volume contains the appendices.

Design tradeoff studies and sensitivity analysis. Appendices B1-B4. [HYBRID

Energy Technology Data Exchange (ETDEWEB)

1979-05-25

These four appendices to the report on the Near-Term Hybrid Vehicle (NTHV) report contain information on: HYBRID computer program documentation; material substitution study for advanced hybrid vehicles; NTHV market potential; battery compartment weight distribution; and vehicle handling dynamics. (LCL)

Theoretical studies of fusion physics. Volume II. Appendices. Final report

International Nuclear Information System (INIS)

1983-01-01

The following appendices are given: (1) absorption of waves near the cyclotron frequency by relativistic electrons in EBT, (2) power balance in a stable, adiabatic hot electron annulus, (3) whistler instability in a relativistic electron annulus, and (4) adiabatic limit on electron temperature in the EBT annulus

Demonstration, testing, & evaluation of in situ heating of soil. Draft final report, Volume II: Appendices A to E

Energy Technology Data Exchange (ETDEWEB)

Dev, H.; Enk, J.; Jones, D.; Saboto, W.

1996-02-12

This document is a draft final report for US DOE contract entitled, {open_quotes}Demonstration Testing and Evaluation of In Situ Soil Heating,{close_quotes} Contract No. DE-AC05-93OR22160, IITRI Project No. C06787. This report is presented in two volumes. Volume I contains the technical report This document is Volume II, containing appendices with background information and data. In this project approximately 300 cu. yd. of clayey soil containing a low concentration plume of volatile organic chemicals was heated in situ by the application of electrical energy. It was shown that as a result of heating the effective permeability of soil to air flow was increased such that in situ soil vapor extraction could be performed. The initial permeability of soil was so low that the soil gas flow rate was immeasurably small even at high vacuum levels. When scaled up, this process can be used for the environmental clean up and restoration of DOE sites contaminated with VOCs and other organic chemicals boiling up to 120{degrees}to 130{degrees}C in the vadose zone. Although it may applied to many types of soil formations, it is particularly attractive for low permeability clayey soil where conventional in situ venting techniques are limited by low air flow.

RF model of the distribution system as a communication channel, phase 2. Volume 3: Appendices

Science.gov (United States)

Rustay, R. C.; Gajjar, J. T.; Rankin, R. W.; Wentz, R. C.; Wooding, R.

1982-01-01

Program documentation concerning the design, implementation, and verification of a computerized model for predicting the steady-state sinusoidal response of radial configured distribution feeders is presented in these appendices.

Final environmental impact statement, Beaufort Sea oil and gas development/Northstar Project. Appendices B through K

International Nuclear Information System (INIS)

1999-02-01

BP Exploration (Alaska) Inc. (BPXA) submitted a permit application to the US. Army Engineer District, Alaska to initiate the review process for BPXA's plans to develop and produce oil and gas from the Northstar Unit. This report contains Appendices B--K of an Environmental Impact Statement which was undertaken to identify and evaluate the potential effects the proposed project may have on the environment

WECC Variable Generation Planning Reference Book: Appendices

Energy Technology Data Exchange (ETDEWEB)

Makarov, Yuri V.; Du, Pengwei; Etingov, Pavel V.; Ma, Jian; Vyakaranam, Bharat

2013-05-13

The document titled “WECC Variable Generation Planning Reference Book”. This book is divided into two volumes; one is the main document (volume 1)and the other is appendices (volume 2). The main document is a collection of the best practices and the information regarding the application and impact of variables generation on power system planning. This volume (appendices) has additional information on the following topics: Probabilistic load flow problems. 2. Additional useful indices. 3. high-impact low-frequency (HILF) events. 4. Examples of wide-area nomograms. 5. Transmission line ratings, types of dynamic rating methods. 6. Relative costs per MW-km of different electric power transmission technologies. 7. Ultra-high voltage (UHV) transmission. 8.High voltage direct current (VSC-HVDC). 9. HVDC. 10. Rewiring of existing transmission lines. 11. High-temperature low sag (HTLS) conductors. 12. The direct method and energy functions for transient stability analysis in power systems. 13.Blackouts caused by voltage instability. 14. Algorithm for parameter continuation predictor-corrector methods. 15. Approximation techniques available for security regions. 16. Impacts of wind power on power system small signals stability. 17. FIDVR. 18. FACTS. 19. European planning standard and practices. 20. International experience in wind and solar energy sources. 21. Western Renewable Energy Zones (WREZ). 22. various energy storage technologies. 23. demand response. 24. BA consolidation and cooperation options. 25. generator power management requirements and 26. European planning guidelines.

Business plan: Supplemental draft environmental impact statement. Volume 2. Appendices

International Nuclear Information System (INIS)

1995-02-01

This document contains the appendices for the Bonneville Power Administration (BPA) Business Plan: Supplemental Draft Environmental Impact Statement. Included are: BPA products and services; Rate design; Methodology and assumptions for numerical analysis; Retail utility operations; Comments and responses to the draft business plan EIS

Business Plan : Supplemental Draft Environmental Impact Statement, Volume 2, Appendices.

Energy Technology Data Exchange (ETDEWEB)

United States. Bonneville Power Administration.

1995-02-01

This document contains the appendices for the Bonneville Power Administration (BPA) Business Plan: Supplemental Draft Environmental Impact Statement. Included are: BPA products and services; Rate design; Methodology and assumptions for numerical analysis; Retail utility operations; Comments and responses to the draft business plan EIS.

Demonstration, testing, ampersand evaluation of in situ heating of soil. Draft final report, Volume II: Appendices A to E

International Nuclear Information System (INIS)

Dev, H.; Enk, J.; Jones, D.; Saboto, W.

1996-01-01

This document is a draft final report for US DOE contract entitled, open-quotes Demonstration Testing and Evaluation of In Situ Soil Heating,close quotes Contract No. DE-AC05-93OR22160, IITRI Project No. C06787. This report is presented in two volumes. Volume I contains the technical report This document is Volume II, containing appendices with background information and data. In this project approximately 300 cu. yd. of clayey soil containing a low concentration plume of volatile organic chemicals was heated in situ by the application of electrical energy. It was shown that as a result of heating the effective permeability of soil to air flow was increased such that in situ soil vapor extraction could be performed. The initial permeability of soil was so low that the soil gas flow rate was immeasurably small even at high vacuum levels. When scaled up, this process can be used for the environmental clean up and restoration of DOE sites contaminated with VOCs and other organic chemicals boiling up to 120 degrees to 130 degrees C in the vadose zone. Although it may applied to many types of soil formations, it is particularly attractive for low permeability clayey soil where conventional in situ venting techniques are limited by low air flow

Severe accident risks: An assessment for five US nuclear power plants: Appendices A, B, and C

International Nuclear Information System (INIS)

1990-12-01

This report summarizes an assessment of the risks from severe accidents in five commercial nuclear power plants in the United States. These risks are measured in a number of ways, including: the estimated frequencies of core damage accidents from internally initiated accidents and externally initiated accidents for two or the plants; the performance of containment structures under severe accident loadings; the potential magnitude of radionuclide release and offsite consequences of such accidents; and the overall risk (the product of accident frequencies and consequences). Supporting this summary report are a large number of reports written under contract to NRC that provide the detailed discussion of the methods used and results obtained in these risk studies. Volume 2 of this report contains three appendices, providing greater detail on the methods used, an example risk calculation, and more detailed discussion of particular technical issues found important in the risk studies

NASA Aerospace Flight Battery Program: Wet Life of Nickel-Hydrogen (Ni-H2) Batteries. Volume 2, Part 3; Appendices

Science.gov (United States)

Jung, David S,; Lee, Leonine S.; Manzo, Michelle A.

2010-01-01

This NASA Aerospace Flight Battery Systems Working Group was chartered within the NASA Engineering and Safety Center (NESC). The Battery Working Group was tasked to complete tasks and to propose proactive work to address battery related, agency-wide issues on an annual basis. In its first year of operation, this proactive program addressed various aspects of the validation and verification of aerospace battery systems for NASA missions. Studies were performed, issues were discussed and in many cases, test programs were executed to generate recommendations and guidelines to reduce risk associated with various aspects of implementing battery technology in the aerospace industry. This document contains Part 3 - Volume II Appendices to Part 3 - Volume I.

State of the Art Report on Fracture Mechanics (Fracture in the Creep Range). Volume 3: Appendices H - M

International Nuclear Information System (INIS)

Ellison, E.G.; Musicco, G.G.; Pineau, A.

1988-01-01

A CEC State of the Art Report on Fracture Mechanics for Fast Breeder Reactors (Fracture below the Creep Range) has recently been published by Bhandari and coworkers (1984). There has also been a compilation of Creep Crack Growth Data from Germany, France and the U.K. for 304 and 316 stainles steel by Lloyd et al (1984). The present Report provides considerably more data and analytical techniques taken from Worldwide sources on creep crack initiation and propagation. Since the subject is moving quickly there is an emphasis on the most recent work; indeed research studies as yet unpublished are also included. The total Report is in 3 volumes. Volume 3 contains the most important and up-to-date information in some detail in Appendices H to M; this provides a sound base for the Report and for future workers

Empirical Model Development for Predicting Shock Response on Composite Materials Subjected to Pyroshock Loading. Volume 2, Part 1; Appendices

Science.gov (United States)

Gentz, Steven J.; Ordway, David O.; Parsons, David S.; Garrison, Craig M.; Rodgers, C. Steven; Collins, Brian W.

2015-01-01

The NASA Engineering and Safety Center (NESC) received a request to develop an analysis model based on both frequency response and wave propagation analyses for predicting shock response spectrum (SRS) on composite materials subjected to pyroshock loading. The model would account for near-field environment (approximately 9 inches from the source) dominated by direct wave propagation, mid-field environment (approximately 2 feet from the source) characterized by wave propagation and structural resonances, and far-field environment dominated by lower frequency bending waves in the structure. This document contains appendices to the Volume I report.

Component Fragility Research Program: Phase 1, Demonstration tests: Volume 2, Appendices

International Nuclear Information System (INIS)

Holman, G.S.; Chou, C.K.; Shipway, G.D.; Glozman, V.

1987-08-01

Appendices are presented which contain information concerning: details of controller and relay installation; resonance search transmissibility plots; time-history data from runs 17, 31, 46, and 56; and response spectra from runs 17, 31, 46, and 56

The backfilling and sealing of radioactive waste repositories. V. 2. Figure - Tables - Appendices

International Nuclear Information System (INIS)

1984-01-01

The two volumes of this report present a review study about backfilling and sealing of radioactive waste repositories in granites, argillaceous and salt formations. Volume 2 contains all the figures, table and appendices A detailed account of candidate backfill materials is given in a standardized format

Application of SLIM-MAUD: A test of an interactive computer-based method for organizing expert assessment of human performance and reliability: Volume 2, Appendices

International Nuclear Information System (INIS)

Spettell, C.M.; Rosa, E.A.; Humphreys, P.C.; Embrey, D.E.

1986-10-01

The US Nuclear Regulatory Commission (NRC) has been conducting a multiyear research program to investigate different methods for using expert judgments to estimate human error probabilities (HEPs) in nuclear power plants. One of the methods investigated, derived from multi-attribute utility theory, is the Success Likelihood Index Methodolocy implemented through Multi-Attribute Utility Decomposition (SLIM-MAUD). This report describes a systematic test application of the SLIM-MAUD methodology. The test application is evaluated on the basis of three criteria: practicality, acceptability, and usefulness. Volume I of this report represents an overview of SLIM-MAUD, describes the procedures followed in the test application, and provides a summary of the results obtained. Volume II consists of technical appendices to support in detail the materials contained in Volume I, and the users' package of explicit procedures to be followed in implementing SLIM-MAUD. The results obtained in the test application provide support for the application of SLIM-MAUD to a wide variety of applications requiring estimates of human errors

Supplemental site inspection for Air Force Plant 59, Johnson City, New York, Volume 3: Appendices F-Q

Energy Technology Data Exchange (ETDEWEB)

Nashold, B.; Rosenblatt, D.; Hau, J. [and others

1995-08-01

This summary describes a Supplemental Site Inspection (SSI) conducted by Argonne National Laboratory (ANL) at Air Force Plant 59 (AFP 59) in Johnson City, New York. All required data pertaining to this project were entered by ANL into the Air Force-wide Installation Restoration Program Information System (IRPIMS) computer format and submitted to an appropriate authority. The work was sponsored by the United States Air Force as part of its Installation Restoration Program (IRP). Previous studies had revealed the presence of contaminants at the site and identified several potential contaminant sources. Argonne`s study was conducted to answer questions raised by earlier investigations. This volume consists of appendices F-Q, which contain the analytical data from the site characterization.

Probabilistic accident consequence uncertainty analysis -- Late health effects uncertain assessment. Volume 2: Appendices

Energy Technology Data Exchange (ETDEWEB)

Little, M.P.; Muirhead, C.R. [National Radiological Protection Board (United Kingdom); Goossens, L.H.J.; Kraan, B.C.P.; Cooke, R.M. [Delft Univ. of Technology (Netherlands); Harper, F.T. [Sandia National Labs., Albuquerque, NM (United States); Hora, S.C. [Univ. of Hawaii, Hilo, HI (United States)

1997-12-01

The development of two new probabilistic accident consequence codes, MACCS and COSYMA, was completed in 1990. These codes estimate the consequence from the accidental releases of radiological material from hypothesized accidents at nuclear installations. In 1991, the US Nuclear Regulatory Commission and the Commission of the European Communities began cosponsoring a joint uncertainty analysis of the two codes. The ultimate objective of this joint effort was to systematically develop credible and traceable uncertainty distributions for the respective code input variables. A formal expert judgment elicitation and evaluation process was identified as the best technology available for developing a library of uncertainty distributions for these consequence parameters. This report focuses on the results of the study to develop distribution for variables related to the MACCS and COSYMA late health effects models. This volume contains appendices that include (1) a summary of the MACCS and COSYMA consequence codes, (2) the elicitation questionnaires and case structures, (3) the rationales and results for the expert panel on late health effects, (4) short biographies of the experts, and (5) the aggregated results of their responses.

Probabilistic accident consequence uncertainty analysis -- Early health effects uncertainty assessment. Volume 2: Appendices

Energy Technology Data Exchange (ETDEWEB)

Haskin, F.E. [Univ. of New Mexico, Albuquerque, NM (United States); Harper, F.T. [Sandia National Labs., Albuquerque, NM (United States); Goossens, L.H.J.; Kraan, B.C.P. [Delft Univ. of Technology (Netherlands)

1997-12-01

The development of two new probabilistic accident consequence codes, MACCS and COSYMA, was completed in 1990. These codes estimate the consequence from the accidental releases of radiological material from hypothesized accidents at nuclear installations. In 1991, the US Nuclear Regulatory Commission and the Commission of the European Communities began cosponsoring a joint uncertainty analysis of the two codes. The ultimate objective of this joint effort was to systematically develop credible and traceable uncertainty distributions for the respective code input variables. A formal expert judgment elicitation and evaluation process was identified as the best technology available for developing a library of uncertainty distributions for these consequence parameters. This report focuses on the results of the study to develop distribution for variables related to the MACCS and COSYMA early health effects models. This volume contains appendices that include (1) a summary of the MACCS and COSYMA consequence codes, (2) the elicitation questionnaires and case structures, (3) the rationales and results for the panel on early health effects, (4) short biographies of the experts, and (5) the aggregated results of their responses.

Probabilistic accident consequence uncertainty analysis -- Uncertainty assessment for internal dosimetry. Volume 2: Appendices

Energy Technology Data Exchange (ETDEWEB)

Goossens, L.H.J.; Kraan, B.C.P.; Cooke, R.M. [Delft Univ. of Technology (Netherlands); Harrison, J.D. [National Radiological Protection Board (United Kingdom); Harper, F.T. [Sandia National Labs., Albuquerque, NM (United States); Hora, S.C. [Univ. of Hawaii, Hilo, HI (United States)

1998-04-01

The development of two new probabilistic accident consequence codes, MACCS and COSYMA, was completed in 1990. These codes estimate the consequence from the accidental releases of radiological material from hypothesized accidents at nuclear installations. In 1991, the US Nuclear Regulatory Commission and the Commission of the European Communities began cosponsoring a joint uncertainty analysis of the two codes. The ultimate objective of this joint effort was to systematically develop credible and traceable uncertainty distributions for the respective code input variables. A formal expert judgment elicitation and evaluation process was identified as the best technology available for developing a library of uncertainty distributions for these consequence parameters. This report focuses on the results of the study to develop distribution for variables related to the MACCS and COSYMA internal dosimetry models. This volume contains appendices that include (1) a summary of the MACCS and COSYMA consequence codes, (2) the elicitation questionnaires and case structures, (3) the rationales and results for the panel on internal dosimetry, (4) short biographies of the experts, and (5) the aggregated results of their responses.

Appendiceal Abscesses Reduced in Size by Drainage of Pus from the Appendiceal Orifice during Colonoscopy: A Report of Three Cases

Directory of Open Access Journals (Sweden)

Shinjiro Kobayashi

2014-11-01

Full Text Available Interval appendectomy (IA for appendiceal abscesses is useful for avoiding extended surgery and preventing postoperative complications. However, IA has problems in that it takes time before an abscess is reduced in size in some cases and in that elective surgery may result in a delay in treatment in patients with a malignant tumor of the appendix. In order to rule out malignancy, we performed colonoscopy on three patients with an appendiceal abscess that did not decrease in size 5 or more days after IA. After malignancy had been ruled out by examination of the area of the appendiceal orifice, the appendiceal orifice was compressed with a colonoscope, and a catheter was inserted through the orifice. Then, drainage of pus was observed from the appendiceal orifice into the cecal lumen. Computed tomography performed 3 days after colonoscopy revealed a marked reduction in abscess size in all patients. No endoscopy-related complication was noted. Colonoscopy in patients with an appendiceal abscess may not only differentiate malignant tumors, but also accelerate reduction in abscess size.

Research reactor core conversion guidebook. V.2: Analysis (Appendices A-F)

International Nuclear Information System (INIS)

1992-04-01

Volume 2 consists of detailed Appendices, covering safety analyses for generic 10 MW reactor, safety analysis - probabilistic methods, methods for preventing LOCA, radiological consequence analyses, examples of safety report amendments and safety specifications. Included in Volume 2 are example analyses for cores with with highly enriched uranium and low enriched uranium fuels showing differences that can be expected in the safety parameters and radiological consequences of postulated accidents. There are seven examples of licensing documents related to core conversion and two examples of methods for determining power limits for safety specifications in the document. Refs, figs, bibliographies and tabs

Probabilistic accident consequence uncertainty analysis: Dispersion and deposition uncertainty assessment, appendices A and B

International Nuclear Information System (INIS)

Harper, F.T.; Young, M.L.; Miller, L.A.; Hora, S.C.; Lui, C.H.; Goossens, L.H.J.; Cooke, R.M.; Paesler-Sauer, J.; Helton, J.C.

1995-01-01

The development of two new probabilistic accident consequence codes, MACCS and COSYMA, completed in 1990, estimate the risks presented by nuclear installations based on postulated frequencies and magnitudes of potential accidents. In 1991, the US Nuclear Regulatory Commission (NRC) and the Commission of the European Communities (CEC) began a joint uncertainty analysis of the two codes. The objective was to develop credible and traceable uncertainty distributions for the input variables of the codes. Expert elicitation, developed independently, was identified as the best technology available for developing a library of uncertainty distributions for the selected consequence parameters. The study was formulated jointly and was limited to the current code models and to physical quantities that could be measured in experiments. To validate the distributions generated for the wet deposition input variables, samples were taken from these distributions and propagated through the wet deposition code model along with the Gaussian plume model (GPM) implemented in the MACCS and COSYMA codes. Resulting distributions closely replicated the aggregated elicited wet deposition distributions. Project teams from the NRC and CEC cooperated successfully to develop and implement a unified process for the elaboration of uncertainty distributions on consequence code input parameters. Formal expert judgment elicitation proved valuable for synthesizing the best available information. Distributions on measurable atmospheric dispersion and deposition parameters were successfully elicited from experts involved in the many phenomenological areas of consequence analysis. This volume is the second of a three-volume document describing the project and contains two appendices describing the rationales for the dispersion and deposition data along with short biographies of the 16 experts who participated in the project

Probabilistic accident consequence uncertainty analysis: Dispersion and deposition uncertainty assessment, appendices A and B

Energy Technology Data Exchange (ETDEWEB)

Harper, F.T.; Young, M.L.; Miller, L.A. [Sandia National Labs., Albuquerque, NM (United States); Hora, S.C. [Univ. of Hawaii, Hilo, HI (United States); Lui, C.H. [Nuclear Regulatory Commission, Washington, DC (United States); Goossens, L.H.J.; Cooke, R.M. [Delft Univ. of Technology (Netherlands); Paesler-Sauer, J. [Research Center, Karlsruhe (Germany); Helton, J.C. [and others

1995-01-01

The development of two new probabilistic accident consequence codes, MACCS and COSYMA, completed in 1990, estimate the risks presented by nuclear installations based on postulated frequencies and magnitudes of potential accidents. In 1991, the US Nuclear Regulatory Commission (NRC) and the Commission of the European Communities (CEC) began a joint uncertainty analysis of the two codes. The objective was to develop credible and traceable uncertainty distributions for the input variables of the codes. Expert elicitation, developed independently, was identified as the best technology available for developing a library of uncertainty distributions for the selected consequence parameters. The study was formulated jointly and was limited to the current code models and to physical quantities that could be measured in experiments. To validate the distributions generated for the wet deposition input variables, samples were taken from these distributions and propagated through the wet deposition code model along with the Gaussian plume model (GPM) implemented in the MACCS and COSYMA codes. Resulting distributions closely replicated the aggregated elicited wet deposition distributions. Project teams from the NRC and CEC cooperated successfully to develop and implement a unified process for the elaboration of uncertainty distributions on consequence code input parameters. Formal expert judgment elicitation proved valuable for synthesizing the best available information. Distributions on measurable atmospheric dispersion and deposition parameters were successfully elicited from experts involved in the many phenomenological areas of consequence analysis. This volume is the second of a three-volume document describing the project and contains two appendices describing the rationales for the dispersion and deposition data along with short biographies of the 16 experts who participated in the project.

Volume I. Environmental effects on contents of Cs-137 and Sr-90 in milk. Volume II. Appendices

International Nuclear Information System (INIS)

1981-01-01

Milk, animal fodders, soils, humans, livestock, and wildlife on or near 55 dairy farms in Utah were assayed for radionuclide content. Effects of soil chemistry, water supply, plant type, farming practices, geographic location, altitude, rainfall, and other ecological differences were sought by intensive analysis. Although many analyses have not been completed, several cause-effect relationships have been defined. Wet-lands yield more 137 Cs, 131 I, or 90 Sr to milk under like conditions of fallout intensity than dry-lands. In most cases, the station with the highest yield is also practicing wet grazing. 90 Sr and 137 Cs content of milk is enhanced by sandy soils. Increased altitude and higher rainfall lead to higher yields of 90 Sr and 137 Cs in milk. Levels of 137 Cs in milk increase from south to north, and Utah can be divided into several regions, each having a characteristic level of 90 Sr and 137 Cs in milk, meat, and fodders. Poor pastures (over-grazed to the extent that stem bases are eaten and much soil is exposed) yield more 137 Cs and 90 Sr than improved pastures. Feeding green chop alfalfa or putting the animals on the meadows causes marked but temporary increases in the 90 Sr and 137 Cs content of the milk. However, the annual yield for two stations of similar ecology in the same geographic area is essentially the same. Experimental details are presented in Volume I. The appendices in Volume II are made up primarily of the data compiled at the 78 stations

Draft Programmatic Environmental Impact Statement for alternative strategies for the long-term management and use of depleted uranium hexafluoride. Volume 2: Appendices

International Nuclear Information System (INIS)

1997-12-01

This PEIS assesses the potential impacts of alternative management of alternative management strategies for depleted uranium hexafluoride (UF 6 ) currently stored at three DOE sites: Paducah site near Paducah, Kentucky; Portsmouth site near Portsmouth, Ohio; and K-25 site on the Oak Ridge Reservation, Oak Ridge, Tennessee. The alternatives analyzed in the PEIS include no action, long-term storage as UF 6 , long-term storage as uranium oxide, use as uranium oxide, use as uranium metal, and disposal. The preferred alternative for the long-term management of depleted UF 6 is to use the entire inventory of material. This volume contains the appendices to volume I

Sizewell 'B' power station public inquiry: CEGB proof of evidence

International Nuclear Information System (INIS)

Wilson, A.

1982-11-01

The methods of establishing construction time, capital cost, availability and lifetime of different types of generating plant are described. In volume one assessments are presented for a new coal fired station, for a new AGR station and for a new PWR station - Sizewell B. Volume two, contains all diagrams, tables and appendices presented as evidence. (U.K.)

Iodine-131 Releases from Radioactive Lanthanum Processing at the X-10 Site in Oak Ridge, Tennessee (1944-1956)- An Assessment of Quantities released, Off-Site Radiation Doses, and Potential Excess Risks of Thyroid Cancer- APPENDICES Appendices-Volume 1A

International Nuclear Information System (INIS)

Apostoaei, A.I.; Burns, R.E.; Hoffman, F.O.; Ijaz, T.; Lewis, C.J.; Nair, S.K.; Widner, T.E.

1999-01-01

This report consists of all the appendices for the report described below: In the early 1990s, concern about the Oak Ridge Reservation's past releases of contaminants to the environment prompted Tennessee's public health officials to pursue an in-depth study of potential off-site health effects at Oak Ridge. This study, the Oak Ridge dose reconstruction, was supported by an agreement between the U.S. Department of Energy (DOE) and the State of Tennessee, and was overseen by a 12-member panel appointed by Tennessee's Commissioner of Health. One of the major contaminants studied in the dose reconstruction was radioactive iodine, which was released to the air by X-10 (now called Oak Ridge National Laboratory) as it processed spent nuclear reactor fuel from 1944 through 1956. The process recovered radioactive lanthanum for use in weapons development. Iodine concentrates in the thyroid gland so health concerns include various diseases of the thyroid, such as thyroid cancer. The large report, ''Iodine-131 Releases from Radioactive Lanthanum Processing at the X-10 Site in Oak Ridge, Tennessee (1944-1956) - An Assessment of Quantities Released, Off-site Radiation Doses, and Potential Excess Risks of Thyroid Cancer,'' is in two volumes. Volume 1 is the main body of the report, and Volume 1A, which has the same title, consists of 22 supporting appendices. Together, these reports serve the following purposes: (1) describe the methodologies used to estimate the amount of iodine-131 (I-131) released; (2) evaluate I-131's pathway from air to vegetation to food to humans; (3) estimate doses received by human thyroids; (4) estimate excess risk of acquiring a thyroid cancer during ones lifetime; and (5) provide equations, examples of historical documents used, and tables of calculated values as appendices. Results indicate that females born in 1952 who consumed milk from a goat pastured a few miles east of X-10 received the highest doses from I-131 and would have had the highest

Iodine-131 Releases from Radioactive Lanthanum Processing at the X-10 Site in Oak Ridge, Tennessee (1944-1956)- An Assessment of Quantities released, Off-Site Radiation Doses, and Potential Excess Risks of Thyroid Cancer- APPENDICES Appendices-Volume 1A

Energy Technology Data Exchange (ETDEWEB)

Apostoaei, A.I.; Burns, R.E.; Hoffman, F.O.; Ijaz, T.; Lewis, C.J.; Nair, S.K.; Widner, T.E.

1999-07-01

This report consists of all the appendices for the report described below: In the early 1990s, concern about the Oak Ridge Reservation's past releases of contaminants to the environment prompted Tennessee's public health officials to pursue an in-depth study of potential off-site health effects at Oak Ridge. This study, the Oak Ridge dose reconstruction, was supported by an agreement between the U.S. Department of Energy (DOE) and the State of Tennessee, and was overseen by a 12-member panel appointed by Tennessee's Commissioner of Health. One of the major contaminants studied in the dose reconstruction was radioactive iodine, which was released to the air by X-10 (now called Oak Ridge National Laboratory) as it processed spent nuclear reactor fuel from 1944 through 1956. The process recovered radioactive lanthanum for use in weapons development. Iodine concentrates in the thyroid gland so health concerns include various diseases of the thyroid, such as thyroid cancer. The large report, ''Iodine-131 Releases from Radioactive Lanthanum Processing at the X-10 Site in Oak Ridge, Tennessee (1944-1956) - An Assessment of Quantities Released, Off-site Radiation Doses, and Potential Excess Risks of Thyroid Cancer,'' is in two volumes. Volume 1 is the main body of the report, and Volume 1A, which has the same title, consists of 22 supporting appendices. Together, these reports serve the following purposes: (1) describe the methodologies used to estimate the amount of iodine-131 (I-131) released; (2) evaluate I-131's pathway from air to vegetation to food to humans; (3) estimate doses received by human thyroids; (4) estimate excess risk of acquiring a thyroid cancer during ones lifetime; and (5) provide equations, examples of historical documents used, and tables of calculated values as appendices. Results indicate that females born in 1952 who consumed milk from a goat pastured a few miles east of X-10 received the highest doses from

Mirror Fusion Test Facility-B (MFTF-B) axicell configuration: NbTi magnet system. Manufacturing/producibility final report. Volume 2

International Nuclear Information System (INIS)

Ritschel, A.J.; White, W.L.

1985-05-01

This Final MFTF-B Manufacturing/Producibility Report covers facilities, tooling plan, manufacturing sequence, schedule and performance, producibility, and lessons learned for the solenoid, axicell, and transition coils, as well as a deactivation plan, conclusions, references, and appendices

Survey of strong motion earthquake effects on thermal power plants in California with emphasis on piping systems. Volume 2, Appendices

International Nuclear Information System (INIS)

Stevenson, J.D.

1995-11-01

Volume 2 of the ''Survey of Strong Motion Earthquake Effects on Thermal Power Plants in California with Emphasis on Piping Systems'' contains Appendices which detail the detail design and seismic response of several power plants subjected to strong motion earthquakes. The particular plants considered include the Ormond Beach, Long Beach and Seal Beach, Burbank, El Centro, Glendale, Humboldt Bay, Kem Valley, Pasadena and Valley power plants. Included is a typical power plant piping specification and photographs of typical power plant piping specification and photographs of typical piping and support installations for the plants surveyed. Detailed piping support spacing data are also included

Sizewell 'B' power station public inquiry: CEGB proof of evidence

International Nuclear Information System (INIS)

Gittus, J.

1982-11-01

In volume one an analysis is presented of degraded core accidents involving the proposed Sizewell B PWR. Consideration is given to their estimated frequency, the course which they take, the release of radioisotopes from the plant and the radiological consequences of such a release. Volume two contains all the figures, tables and appendices presented as evidence. (U.K.)

Appendiceal Adenocarcinoma Presenting as a Rectal Polyp

Directory of Open Access Journals (Sweden)

Erin Fitzgerald

2016-02-01

Full Text Available Appendiceal adenocarcinoma typically presents as an incidentally noted appendiceal mass, or with symptoms of right lower quadrant pain that can mimic appendicitis, but local involvement of adjacent organs is uncommon, particularly as the presenting sign. We report on a case of a primary appendiceal cancer initially diagnosed as a rectal polyp based on its appearance in the rectal lumen. The management of the patient was in keeping with standard practice for a rectal polyp, and the diagnosis of appendiceal adenocarcinoma was made intraoperatively. The operative strategy had to be adjusted due to this unexpected finding. Although there are published cases of appendiceal adenocarcinoma inducing intussusception and thus mimicking a cecal polyp, there are no reports in the literature describing invasion of the appendix through the rectal wall and thus mimicking a rectal polyp. The patient is a 75-year-old female who presented with spontaneous hematochezia and, on colonoscopy, was noted to have a rectal polyp that appeared to be located within a diverticulum. When endoscopic mucosal resection was not successful, she was referred to colorectal surgery for a low anterior resection. Preoperative imaging was notable for an enlarged appendix adjacent to the rectum. Intraoperatively, the appendix was found to be densely adherent to the right lateral rectal wall. An en bloc resection of the distal sigmoid colon, proximal rectum and appendix was performed, with pathology demonstrating appendiceal adenocarcinoma that invaded through the rectal wall. The prognosis in this type of malignancy weighs heavily on whether or not perforation and spread throughout the peritoneal cavity have occurred. In this unusual presentation, an en bloc resection is required for a complete resection and to minimize the risk of peritoneal spread. Unusual appearing polyps do not always originate from the bowel wall. Abnormal radiographic findings adjacent to an area of

Shipping container response to severe highway and railway accident conditions: Appendices

International Nuclear Information System (INIS)

Fischer, L.E.; Chou, C.K.; Gerhard, M.A.; Kimura, C.Y.; Martin, R.W.; Mensing, R.W.; Mount, M.E.; Witte, M.C.

1987-02-01

Volume 2 contains the following appendices: Severe accident data; truck accident data; railroad accident data; highway survey data and bridge column properties; structural analysis; thermal analysis; probability estimation techniques; and benchmarking for computer codes used in impact analysis. (LN)

Probing Aircraft Flight Test Hazard Mitigation for the Alternative Fuel Effects on Contrails and Cruise Emissions (ACCESS) Research Team . Volume 2; Appendices

Science.gov (United States)

Kelly, Michael J.

2013-01-01

The Alternative Fuel Effects on Contrails and Cruise Emissions (ACCESS) Project Integration Manager requested in July 2012 that the NASA Engineering and Safety Center (NESC) form a team to independently assess aircraft structural failure hazards associated with the ACCESS experiment and to identify potential flight test hazard mitigations to ensure flight safety. The ACCESS Project Integration Manager subsequently requested that the assessment scope be focused predominantly on structural failure risks to the aircraft empennage (horizontal and vertical tail). This report contains the Appendices to Volume I.

Information needs for characterization of high-level waste repository sites in six geologic media. Volume 2. Appendices

Energy Technology Data Exchange (ETDEWEB)

NONE

1985-05-01

Volume II contains appendices for the following: (1) remote sensing and surface mapping techniques; (2) subsurface mapping methods for site characterization; (3) gravity technique; (4) audio-frequency magnetotelluric technique; (5) seismic refraction technique; (6) direct-current electrical resistivity method; (7) magnetic technique; (8) seismic reflection technique; (9) seismic crosshole method; (10) mechanical downhole seismic velocity survey method; (11) borehole geophysical logging techniques; (12) drilling and coring methods for precharacterization studies; (13) subsurface drilling methods for site characterization; (14) geomechanical/thermomechanical techniques for precharacterization studies; (15)geomechanical/thermal techniques for site characterization studies; (16) exploratory geochemical techniques for precharacterization studies; (17) geochemical techniques for site characterization; (18) hydrologic techniques for precharacterization studies; (19) hydrologic techniques for site characterization; and (20) seismological techniques.

Information needs for characterization of high-level waste repository sites in six geologic media. Volume 2. Appendices

International Nuclear Information System (INIS)

1985-05-01

Volume II contains appendices for the following: (1) remote sensing and surface mapping techniques; (2) subsurface mapping methods for site characterization; (3) gravity technique; (4) audio-frequency magnetotelluric technique; (5) seismic refraction technique; (6) direct-current electrical resistivity method; (7) magnetic technique; (8) seismic reflection technique; (9) seismic crosshole method; (10) mechanical downhole seismic velocity survey method; (11) borehole geophysical logging techniques; (12) drilling and coring methods for precharacterization studies; (13) subsurface drilling methods for site characterization; (14) geomechanical/thermomechanical techniques for precharacterization studies; (15)geomechanical/thermal techniques for site characterization studies; (16) exploratory geochemical techniques for precharacterization studies; (17) geochemical techniques for site characterization; (18) hydrologic techniques for precharacterization studies; (19) hydrologic techniques for site characterization; and (20) seismological techniques

Report of the Bulletins and Orders Task Force. Volume II. Appendices

International Nuclear Information System (INIS)

1980-01-01

Appendices include: Office of Inspection and Enforcement bulletins; NRR status report on feedwater transients in BWR plants; orders on Babcock and Wilcox Company plants; letters lifting orders; letters issuing auxiliary feedwater system requirements; letter to licensees of all operating reactors, dated October 30, 1979 concerning short-term lessons learned requirements; and letters approving guidelines for preparation of small-break LOCA operating procedures

Space Propulsion Hazards Analysis Manual (SPHAM). Volume 2. Appendices

Science.gov (United States)

1988-10-01

Vanderwall, E.M. and Schaplowsky, R.F., USAF PROPELLANT HA& nBOOKS , Volume III, Part B, "Nitrogen Trifluoride, Bibliography," p. 4-508, Aerojeft Liquid...not economically desirable to maintain two different avionic configurations in the space-based program. Guidance and navigation information is

Acute abdominal pain presenting as a rare appendiceal duplication: a case report

Directory of Open Access Journals (Sweden)

Mahmood Ali

2012-03-01

Full Text Available Abstract Introduction Appendiceal duplication is a rare anomaly that can manifest as right lower quadrant pain. There are several variations described for this condition. We recommend aggressive operative management should this anatomical variation present in the presence of acute appendicitis. Case presentation We report the case of a 15-year-old African American girl who presented to our hospital with right lower quadrant pain and was subsequently found to have appendiceal duplication. Conclusion There are two categorical systems that have described and stratified appendiceal duplication. Both classification systems have been outlined and referenced in this case report. A computed tomography scan has been included to provide a visual aid to help identify true vermiform appendiceal duplication. The presence of this anatomical abnormality is not a reason for surgical intervention; however, should this be found in the setting of acute appendicitis, aggressive resection of both appendices is mandatory.

Resource Programs : Draft Environmental Impact Statement, Volume 2, Appendices.

Energy Technology Data Exchange (ETDEWEB)

United States. Bonneville Power Administration.

1992-03-01

Every two years, Bonneville Power Administration (BPA) prepares a Resource Program which identifies the resource actions BPA will take to meet its obligation to serve the forecasted power requirements of its customers. The Resource Program`s Environmental Impact Statement (RPEIS) is a programmatic environmental document which will support decisions made in several future Resource Programs. Environmental documents tiered to the EIS may be prepared on a site-specific basis. The RPEIS includes a description of the environmental effects and mitigation for the various resource types available in order to evaluate the trade-offs among them. It also assesses the environmental impacts of adding thirteen alternative combinations of resources to the existing power system. This report contains the appendices to the RPEIS.

US Department of Energy Nevada Operations Office annual site environmental report: 1993. Volume 2: Appendices

Energy Technology Data Exchange (ETDEWEB)

Black, S.C.; Glines, W.M.; Townsend, Y.E.

1994-09-01

This report is comprised of appendices which support monitoring and surveillance on and around the Nevada Test Site (NTS) during 1993. Appendix A contains onsite Pu-238, gross beta, and gamma-emitting radionuclides in air. Appendix B contains onsite tritium in air. Appendix C contains onsite Pu-238, Sr-90, gross alpha and beta, gamma-emitting radionuclides, Ra-226, Ra-228 and tritium in water. A summary of 1993 results of offsite radiological monitoring is included in Appendix D. Appendix E contains radioactive noble gases in air onsite. Appendix F contains onsite thermoluminescent dosimeter data. Historical trends in onsite thermoluminescent dosimeter data are contained in Appendix G. Appendix H summarizes 1993 compliance at the DOE/NV NTS and non-NTS facilities. Appendix I summarizes the 1993 results of non radiological monitoring.

US Department of Energy Nevada Operations Office annual site environmental report: 1993. Volume 2: Appendices

International Nuclear Information System (INIS)

Black, S.C.; Glines, W.M.; Townsend, Y.E.

1994-09-01

This report is comprised of appendices which support monitoring and surveillance on and around the Nevada Test Site (NTS) during 1993. Appendix A contains onsite Pu-238, gross beta, and gamma-emitting radionuclides in air. Appendix B contains onsite tritium in air. Appendix C contains onsite Pu-238, Sr-90, gross alpha and beta, gamma-emitting radionuclides, Ra-226, Ra-228 and tritium in water. A summary of 1993 results of offsite radiological monitoring is included in Appendix D. Appendix E contains radioactive noble gases in air onsite. Appendix F contains onsite thermoluminescent dosimeter data. Historical trends in onsite thermoluminescent dosimeter data are contained in Appendix G. Appendix H summarizes 1993 compliance at the DOE/NV NTS and non-NTS facilities. Appendix I summarizes the 1993 results of non radiological monitoring

Case-study application of venture analysis: the integrated energy utility. Volume 3. Appendices

Energy Technology Data Exchange (ETDEWEB)

Fein, E; Gordon, T J; King, R; Kropp, F G; Shuchman, H L; Stover, J; Hausz, W; Meyer, C

1978-11-01

The appendices for a case-study application of venture analysis for an integrated energy utility for commercialization are presented. The following are included and discussed: utility interviews; net social benefits - quantitative calculations; the financial analysis model; market penetration decision model; international district heating systems; political and regulatory environment; institutional impacts.

Radiation dose to construction workers at operating nuclear power plant sites. Volume 2. Appendices A--F. Final report, September 1975--September 1978

International Nuclear Information System (INIS)

Endres, G.W.R.; Shipler, D.B.

1978-12-01

These appendices contain the dosimetry procedures and details of the personnel and environmental dosimeters used for the Radiation Dose to Construction Workers at Operating Nuclear Power Plant Sites Study. A printout of the computer codes used to analyze dosimeter data is included along with all the raw data obtained. Appendices C through F contain computer output and log-normal plots of dosimetry data for environmental location and construction worker groups

Airborne gamma-ray spectrometer and magnetometer survey, Durango D, Colorado. Final report Volume II B. Detail area

International Nuclear Information System (INIS)

1983-01-01

This volume comprises eight appendices containing the following information for the Durango D detail area: flight line maps, geology maps, explanation of geologic legend, flight line/geology maps, radiometric contour maps, magnetic contour maps, multi-variant analysis maps, and geochemical factor analysis maps

Bladder metastases of appendiceal mucinous adenocarcinoma: a case presentation

Directory of Open Access Journals (Sweden)

Giusti Guido

2010-02-01

Full Text Available Abstract Background Appendiceal adenocarcinoma is rare with a frequency of 0.08% of all surgically removed appendices. Few cases of appendiceal carcinoma infiltrating the bladder wall for spatial contiguity have been documented. Case Presentation A case is reported of a 45-years old woman with mucinous cystadenocarcinoma of the appendix with bladder metastasis. Although ultrasonography and voided urinary cytology were negative, abdomen computed tomography (CT scan and cystoscopy and subsequent pathological examination revealed a mass exclusively located in the anterior wall of the bladder. Histopathology of the transurethral bladder resection revealed a bladder adenocarcinoma [6 cm (at the maximum diameter × 2,5 cm; approximate weight: 10 gr] with focal mucinous aspects penetrating the muscle and perivisceral fat. Laparotomy evidenced the presence of a solid mass of the appendix (2,5 cm × 3 cm × 2 cm extending to the loco-regional lymph nodes. Appendectomy and right hemicolectomy, linfoadenectomy and partial cystectomy were performed. The subsequent pathological examination revealed a mucinous cystadenocarcinoma of the appendix with metastatic cells colonising the anterior bladder wall and several colic lymph nodes. Conclusions The rarity of the appendiceal carcinoma invading the urinary bladder and its usual involvement of nearest organs and the posterior bladder wall, led us to describe this case which demonstrates the ability of the appendiceal cancer to metastasize different regions of urinary bladder.

Bladder metastases of appendiceal mucinous adenocarcinoma: a case presentation

International Nuclear Information System (INIS)

Taverna, Gianluigi; Graziotti, Pierpaolo; Corinti, Matteo; Colombo, Piergiuseppe; Grizzi, Fabio; Severo, Mauro; Piccinelli, Alessando; Giusti, Guido; Benetti, Alessio; Zucali, Paolo A

2010-01-01

Appendiceal adenocarcinoma is rare with a frequency of 0.08% of all surgically removed appendices. Few cases of appendiceal carcinoma infiltrating the bladder wall for spatial contiguity have been documented. A case is reported of a 45-years old woman with mucinous cystadenocarcinoma of the appendix with bladder metastasis. Although ultrasonography and voided urinary cytology were negative, abdomen computed tomography (CT) scan and cystoscopy and subsequent pathological examination revealed a mass exclusively located in the anterior wall of the bladder. Histopathology of the transurethral bladder resection revealed a bladder adenocarcinoma [6 cm (at the maximum diameter) × 2,5 cm; approximate weight: 10 gr] with focal mucinous aspects penetrating the muscle and perivisceral fat. Laparotomy evidenced the presence of a solid mass of the appendix (2,5 cm × 3 cm × 2 cm) extending to the loco-regional lymph nodes. Appendectomy and right hemicolectomy, linfoadenectomy and partial cystectomy were performed. The subsequent pathological examination revealed a mucinous cystadenocarcinoma of the appendix with metastatic cells colonising the anterior bladder wall and several colic lymph nodes. The rarity of the appendiceal carcinoma invading the urinary bladder and its usual involvement of nearest organs and the posterior bladder wall, led us to describe this case which demonstrates the ability of the appendiceal cancer to metastasize different regions of urinary bladder

Cerebral Metastasis from a Previously Undiagnosed Appendiceal Adenocarcinoma

Directory of Open Access Journals (Sweden)

Antonio Biroli

2012-01-01

Full Text Available Brain metastases arise in 10%–40% of all cancer patients. Up to one third of the patients do not have previous cancer history. We report a case of a 67-years-old male patient who presented with confusion, tremor, and apraxia. A brain MRI revealed an isolated right temporal lobe lesion. A thorax-abdomen-pelvis CT scan showed no primary lesion. The patient underwent a craniotomy with gross-total resection. Histopathology revealed an intestinal-type adenocarcinoma. A colonoscopy found no primary lesion, but a PET-CT scan showed elevated FDG uptake in the appendiceal nodule. A right hemicolectomy was performed, and the specimen showed a moderately differentiated mucinous appendiceal adenocarcinoma. Whole brain radiotherapy was administrated. A subsequent thorax-abdomen CT scan revealed multiple lung and hepatic metastasis. Seven months later, the patient died of disease progression. In cases of undiagnosed primary lesions, patients present in better general condition, but overall survival does not change. Eventual identification of the primary tumor does not affect survival. PET/CT might be a helpful tool in detecting lesions of the appendiceal region. To the best of our knowledge, such a case was never reported in the literature, and an appendiceal malignancy should be suspected in patients with brain metastasis from an undiagnosed primary tumor.

Airborne gamma-ray spectrometer and magnetometer survey, Durango B, Colorado. Final report Volume II A. Detail area

International Nuclear Information System (INIS)

1983-01-01

The geology of the Durango B detail area, the radioactive mineral occurrences in Colorado and the geophysical data interpretation are included in this report. Seven appendices contain: stacked profiles, geologic histograms, geochemical histograms, speed and altitude histograms, geologic statistical tables, geochemical statistical tables, and test line data

CT features of appendiceal mucocele

Energy Technology Data Exchange (ETDEWEB)

Yu, Won Jong; Byun, Jae Young; Jung, Jung Im; Lee, Hae Gyu; Park, Young Ha; Shin, Kyung Sub [Catholic University Medical College, Seoul (Korea, Republic of)

1995-10-15

To evaluate the usefulness of CT features of appendiceal mucocele in the diagnosis and evaluation of complications. We retrospectively reviewed CT findings and compared with operative findings in 7 cases of pathologically proven appendiceal mucocele. CT findings such as location and extent of the lesion, tissue density, thickness or calcification of the wall, presence of adjacent inflammatory infiltration, and visualization of normal vermiform appendix were analyzed. Appendiceal mucocele was found as homogeneous low density cystic mass adjacent to the cecum, which has no surrounding inflammatory infiltration except in one case of perforation and one case of intussusception. Mean CT number measured in 4 cases was 21 Hounsfield unit. Thin curvilinear calcifications were noted along the cystic wall in 2 cases. Normal vermiform appendix couldn't be demonstrated in all cases. Appendiceal mucocele is characterized by homogeneously low density and thin walled cystic tumor adjacent to cecum without surrounding inflammatory infiltration, and absence of normal vermiform appendix on CT. Therefore, CT is valuable in preventing operative complications of appendiceal mucocele.

Technology, Safety and Costs of Decommissioning a Reference Low-Level Waste Burial Ground. Appendices

International Nuclear Information System (INIS)

None

1980-01-01

Safety and cost information are developed for the conceptual decommissioning of commercial low-level waste (LLW) burial grounds. Two generic burial grounds, one located on an arid western site and the other located on a humid eastern site, are used as reference facilities for the study. The two burial grounds are assumed to have the same site capacity for waste, the same radioactive waste inventory, and similar trench characteristics and operating procedures. The climate, geology. and hydrology of the two sites are chosen to be typical of real western and eastern sites. Volume 2 (Appendices) contains the detailed analyses and data needed to support the results given in Volume 1.

Precursors to potential severe core damage accidents: 1994, a status report. Volume 21: Main report and appendices A--H

International Nuclear Information System (INIS)

Belles, R.J.; Cletcher, J.W.; Copinger, D.A.; Vanden Heuvel, L.N.; Dolan, B.W.; Minarick, J.W.

1995-12-01

Nine operational events that affected eleven commercial light-water reactors (LWRs) during 1994 and that are considered to be precursors to potential severe core damage are described. All these events had conditional probabilities of subsequent severe core damage greater than or equal to 1.0 x 10 -6 . These events were identified by computer-screening the 1994 licensee event reports from commercial LWRs to identify those that could be potential precursors. Candidate precursors were then selected and evaluated in a process similar to that used in previous assessments. Selected events underwent engineering evaluation that identified, analyzed, and documented the precursors. Other events designated by the Nuclear Regulatory Commission (NRC) also underwent a similar evaluation. Finally, documented precursors were submitted for review by licensees and NRC headquarters and regional offices to ensure that the plant design and its response to the precursor were correctly characterized. This study is a continuation of earlier work, which evaluated 1969--1981 and 1984--1993 events. The report discusses the general rationale for this study, the selection and documentation of events as precursors, and the estimation of conditional probabilities of subsequent severe core damage for events. This document is bound in two volumes: Vol. 21 contains the main report and Appendices A--H; Vol. 22 contains Appendix 1

Magnetic Fusion Energy Program. Volume I. Introduction, technical summaries, list of publications, etc., Appendices A-K. Annual report

International Nuclear Information System (INIS)

Aamodt, R.E.; Byrne, R.N.; Catto, P.J.

1979-12-01

An abstract was prepared for the progress summary on transport theory for open and closed magnetic configurations. Seven abstracts were prepared for included appendices of more detailed work on individual devices. Also included is a list of publications, technical presentations, and DOE program contributions

Development of a dynamic model to evaluate economic recovery following a nuclear attack. Volume 2. Model equations (appendices C and D). Final report

International Nuclear Information System (INIS)

Peterson, D.W.; Silverman, W.S.; Weil, H.B.; Willard, S.

1980-11-01

A highly-robust, dynamic simulation model of the US economy has been constructed to evaluate the likely economic response after various nuclear attacks or other severe disruptions, under various policies and assumptions. The model consists of a large system of nonlinear, recursive, time-difference equations. The solution-interval of the model is adjustable, with a maximum value of three weeks. The model represents the economy in thirteen sectors. Each sector contains a detailed representation of production, distribution, supply constraints, finance, employment, pricing, and wages. Also included are a full input-output representation of the interconnections among the sectors, and the psychological responses of corporate planners, consumers, and the labor force. The model's equations are formulated to remain consistent and realistic for all values of the variables, including the most extreme conditions. Therefore, the model can realistically simulate any degree or time sequence of nuclear attacks, pre-attack surges, mobilization, or policy shifts. Simulation experiments with the model suggest that the economy is highly vulnerable to nuclear attack, and that recovery requires extensive preparation, including psychological readiness, technology maintenance, special financial policies, and (if possible) maintenance of foreign trade. Civil defense policies must be adaptive (contingent on the nature of the damage) and must strive for balance among sectors, rather than maximum survival. The simulation model itself consists of an interrelated set of mathematical equations, written in the computer language DYNAMO. Two appendices to the report are presented in this volume. Appendix C gives a brief introduction to the conventions and notations of the DYNAMO language. The equations, definitions, and variables of the model are listed in Appendix D. For the convenience of the reader, these two appendices are bound separately

Probabilistic accident consequence uncertainty analysis -- Uncertainty assessment for deposited material and external doses. Volume 2: Appendices

Energy Technology Data Exchange (ETDEWEB)

Goossens, L.H.J.; Kraan, B.C.P.; Cooke, R.M. [Delft Univ. of Technology (Netherlands); Boardman, J. [AEA Technology (United Kingdom); Jones, J.A. [National Radiological Protection Board (United Kingdom); Harper, F.T.; Young, M.L. [Sandia National Labs., Albuquerque, NM (United States); Hora, S.C. [Univ. of Hawaii, Hilo, HI (United States)

1997-12-01

The development of two new probabilistic accident consequence codes, MACCS and COSYMA, was completed in 1990. These codes estimate the consequence from the accidental releases of radiological material from hypothesized accidents at nuclear installations. In 1991, the US Nuclear Regulatory Commission and the Commission of the European Communities began cosponsoring a joint uncertainty analysis of the two codes. The ultimate objective of this joint effort was to systematically develop credible and traceable uncertainty distributions for the respective code input variables. A formal expert judgment elicitation and evaluation process was identified as the best technology available for developing a library of uncertainty distributions for these consequence parameters. This report focuses on the results of the study to develop distribution for variables related to the MACCS and COSYMA deposited material and external dose models. This volume contains appendices that include (1) a summary of the MACCS and COSYMA consequence codes, (2) the elicitation questionnaires and case structures, (3) the rationales and results for the panel on deposited material and external doses, (4) short biographies of the experts, and (5) the aggregated results of their responses.

Nuclear Dynamics Consequence Analysis (NDCA) for the Disposal of Spent Nuclear Fuel in an Underground Geologic Repository - Volume 3: Appendices

International Nuclear Information System (INIS)

Taylor, L.L.; Wilson, J.R.; Sanchez, L.C.; Aguilar, R.; Trellue, H.R.; Cochrane, K.; Rath, J.S.

1998-01-01

The United States Department of Energy Office of Environmental Management's (DOE/EM's) National Spent Nuclear Fuel Program (NSNFP), through a collaboration between Sandia National Laboratories (SNL) and Idaho National Engineering and Environmental Laboratory (INEEL), is conducting a systematic Nuclear Dynamics Consequence Analysis (NDCA) of the disposal of SNFs in an underground geologic repository sited in unsaturated tuff. This analysis is intended to provide interim guidance to the DOE for the management of the SNF while they prepare for final compliance evaluation. This report presents results from a Nuclear Dynamics Consequence Analysis (NDCA) that examined the potential consequences and risks of criticality during the long-term disposal of spent nuclear fuel owned by DOE-EM. This analysis investigated the potential of post-closure criticality, the consequences of a criticality excursion, and the probability frequency for post-closure criticality. The results of the NDCA are intended to provide the DOE-EM with a technical basis for measuring risk which can be used for screening arguments to eliminate post-closure criticality FEPs (features, events and processes) from consideration in the compliance assessment because of either low probability or low consequences. This report is composed of an executive summary (Volume 1), the methodology and results of the NDCA (Volume 2), and the applicable appendices (Volume 3)

Final environmental impact statement. Management of commercially generated radioactive waste. Volume 2. Appendices

Energy Technology Data Exchange (ETDEWEB)

1980-10-01

This EIS analyzes the significant environmental impacts that could occur if various technologies for management and disposal of high-level and transuranic wastes from commercial nuclear power reactors were to be developed and implemented. This EIS will serve as the environmental input for the decision on which technology, or technologies, will be emphasized in further research and development activities in the commercial waste management program. The action proposed in this EIS is to (1) adopt a national strategy to develop mined geologic repositories for disposal of commercially generated high-level and transuranic radioactive waste (while continuing to examine subseabed and very deep hole disposal as potential backup technologies) and (2) conduct a R and D program to develop such facilities and the necessary technology to ensure the safe long-term containment and isolation of these wastes. The Department has considered in this statement: development of conventionally mined deep geologic repositories for disposal of spent fuel from nuclear power reactors and/or radioactive fuel reprocessing wastes; balanced development of several alternative disposal methods; and no waste disposal action. This volume contains appendices of supplementary data on waste management systems, geologic disposal, radiological standards, radiation dose calculation models, related health effects, baseline ecology, socio-economic conditions, hazard indices, comparison of defense and commercial wastes, design considerations, and wastes from thorium-based fuel cycle alternatives. (DMC)

Final environmental impact statement. Management of commercially generated radioactive waste. Volume 2. Appendices

International Nuclear Information System (INIS)

1980-10-01

This EIS analyzes the significant environmental impacts that could occur if various technologies for management and disposal of high-level and transuranic wastes from commercial nuclear power reactors were to be developed and implemented. This EIS will serve as the environmental input for the decision on which technology, or technologies, will be emphasized in further research and development activities in the commercial waste management program. The action proposed in this EIS is to (1) adopt a national strategy to develop mined geologic repositories for disposal of commercially generated high-level and transuranic radioactive waste (while continuing to examine subseabed and very deep hole disposal as potential backup technologies) and (2) conduct a R and D program to develop such facilities and the necessary technology to ensure the safe long-term containment and isolation of these wastes. The Department has considered in this statement: development of conventionally mined deep geologic repositories for disposal of spent fuel from nuclear power reactors and/or radioactive fuel reprocessing wastes; balanced development of several alternative disposal methods; and no waste disposal action. This volume contains appendices of supplementary data on waste management systems, geologic disposal, radiological standards, radiation dose calculation models, related health effects, baseline ecology, socio-economic conditions, hazard indices, comparison of defense and commercial wastes, design considerations, and wastes from thorium-based fuel cycle alternatives

Songs for funerals and intercession. A collection of polyphony for the confraternity of St Barbara at the Corbie Abbey, Amiens, Bibliothèque Centrale Louis Aragon, MS 162 D. Edited by Peter Woetmann Christoffersen. Volume 2

DEFF Research Database (Denmark)

Christoffersen, Peter Woetmann

2015-01-01

artikel ‘Prayers for the dead, funeral music and simple polyphony in a French music manuscript of the early sixteenth century’. Dette labyrintiske materiale findes desuden organiseret i en lineær form som to PDF-bøger i A4-format: Volume 1 – Introduction and appendices (96 sider), volume 2 – Edition...

Large scale solar district heating. Evaluation, modelling and designing - Appendices

Energy Technology Data Exchange (ETDEWEB)

Heller, A.

2000-07-01

The appendices present the following: A) Cad-drawing of the Marstal CSHP design. B) Key values - large-scale solar heating in Denmark. C) Monitoring - a system description. D) WMO-classification of pyranometers (solarimeters). E) The computer simulation model in TRNSYS. F) Selected papers from the author. (EHS)

Waste Isolation Pilot Plant disposal phase final supplemental environmental impact statement. Volume 2: Appendices

International Nuclear Information System (INIS)

1997-09-01

The purpose of the Waste Isolation Pilot Plant Disposal Final Supplemental Environmental Impact Statement (SEIS-II) is to provide information on environmental impacts regarding the Department of Energy's (DOE) proposed disposal operations at WIPP. The Proposed Action describes the treatment and disposal of the Basic inventory of TRU waste over a 35-year period. The Action Alternatives proposed the treatment of the Basic Inventory and an Additional Inventory as well as the transportation of the treated waste to WIPP for disposal over a 150- to 190-year period. The three Action Alternatives include the treatment of TRU waste at consolidation sites to meet WIPP planning-basic Waste Acceptance Criteria, the thermal treatment of TRU waste to meet Land Disposal Restrictions, and the treatment of TRU waste by a shred and grout process. SEIS-II evaluates environmental impacts resulting from the various treatment options; the transportation of TRU waste to WIPP using truck, a combination of truck and regular rail service, and a combination of truck and dedicated rail service; and the disposal of this waste in the repository. Evaluated impacts include those to the general environment and to human health. Additional issues associated with the implementation of the alternatives are discussed to provide further understanding of the decisions to be reached and to provide the opportunity for public input on improving DOE's Environmental Management Program. This volume contains the following appendices: Waste inventory; Summary of the waste management programmatic environmental impact statement and its use in determining human health impacts at treatment sites; Air quality; Life-cycle costs and economic impacts; Transportation; Human health; Facility accidents; Long-term consequence analysis for proposed action and action alternatives; Long-term consequence analysis for no action alternative 2; and Updated estimates of the DOE's transuranic waste volumes

Resource Conservation and Recovery Act, Part B Permit Application [for the Waste Isolation Pilot Plant (WIPP)]. Volume 6, Chapter D, Appendices D4--D13: Revision 1.0

Energy Technology Data Exchange (ETDEWEB)

1991-12-31

This report (Vol. 6) for the WIPP facility contains appendices on the following information: Site characterization; general geology; ecological monitoring; and chemical compatibility of waste forms and container materials.

Technology, safety, and costs of decommissioning reference nuclear research and test reactors. Appendices

International Nuclear Information System (INIS)

Konzek, G.J.; Ludwick, J.D.; Kennedy, W.E. Jr.; Smith, R.I.

1982-03-01

Safety and Cost Information is developed for the conceptual decommissioning of two representative licensed nuclear research and test reactors. Three decommissioning alternatives are studied to obtain comparisons between costs (in 1981 dollars), occupational radiation doses, potential radiation dose to the public, and other safety impacts. The alternatives considered are: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and EMTOMB (entombment). The study results are presented in two volumes. Volume 2 (Appendices) contains the detailed data that support the results given in Volume 1, including unit-component data

Technology, safety, and costs of decommissioning reference nuclear research and test reactors. Appendices

Energy Technology Data Exchange (ETDEWEB)

Konzek, G.J.; Ludwick, J.D.; Kennedy, W.E. Jr.; Smith, R.I.

1982-03-01

Safety and Cost Information is developed for the conceptual decommissioning of two representative licensed nuclear research and test reactors. Three decommissioning alternatives are studied to obtain comparisons between costs (in 1981 dollars), occupational radiation doses, potential radiation dose to the public, and other safety impacts. The alternatives considered are: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and EMTOMB (entombment). The study results are presented in two volumes. Volume 2 (Appendices) contains the detailed data that support the results given in Volume 1, including unit-component data.

Joint Peru/United States report on Peru/United States cooperative energy assessment. Volume 1. Executive summary, main report and appendices

Energy Technology Data Exchange (ETDEWEB)

1979-08-01

In 1978, the US and Peru conducted a comprehensive assessment of Peru's energy resources, needs, and uses and developed several alternative energy strategies that utilize the available resources to meet their energy requirements. This Volume I reports the findings of the assessment and contains the executive summary, the main report, and five appendices of information that support the integrated energy supply and demand analysis. The following chapters are included: The Energy Situation in Peru (economic context and background, energy resources and production, energy consumption patterns); Reference Supply and Demand Projection (approach, procedures, and assumptions; economic projections; energy demand and supply projections; supply/demand integration; uncertainties); and The Development of Strategies and Options (the analysis of options; strategies; increased use of renewables, hydropower, coal; increased energy efficiency; and financial analysis of strategies).

Technology, safety and costs of decommissioning a reference boiling water reactor power station. Appendices. Volume 2

Energy Technology Data Exchange (ETDEWEB)

Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

1980-06-01

Appendices are presented concerning the evaluations of decommissioning financing alternatives; reference site description; reference BWR facility description; radiation dose rate and concrete surface contamination data; radionuclide inventories; public radiation dose models and calculated maximum annual doses; decommissioning methods; generic decommissioning information; immediate dismantlement details; passive safe storage, continuing care, and deferred dismantlement details; entombment details; demolition and site restoration details; cost estimating bases; public radiological safety assessment details; and details of alternate study bases.

Final programmatic environmental impact statement for alternative strategies for the long-term management and use of depleted uranium hexafluoride. Volume 2: Appendices

International Nuclear Information System (INIS)

1999-04-01

This PEIS assesses the potential impacts of alternative management strategies for depleted uranium hexafluoride (UF 6 ) currently stored at three DOE sites: Paducah site near Paducah, Kentucky, Portsmouth site near Portsmouth, Ohio; and K-25 site on the Oak Ridge Reservation, Oak Ridge, Tennessee. The alternatives analyzed in the PEIS include no action, long-term storage as UF 6 , long-term storage as uranium oxide, use as uranium oxide, use as uranium metal, and disposal. DOE's preferred alternative is to begin conversion of the depleted UF 6 inventory as soon as possible, either to uranium oxide, uranium metal, or a combination of both, while allowing for use of as much of this inventory as possible. This volume contains Appendices A--O

Energy conservation in existing office buildings. Appendices to report, Phase I, Volume 2

Energy Technology Data Exchange (ETDEWEB)

1977-06-01

A blank form of Questionnaire No. 1 is first presented, followed by data compiled from that questionnaire. Then data are presented on the analyses of the 436 buildings, statistical validation for selection of the 44 building sample, and some examples of the matching buildings for the 44 building sample. Questionnaire No. 2 is then given, followed by additional data collected from the study concerning energy consumption and building characteristics. To complete the appendices, a simulation of a typical building and a hypothetical building is included. (MCW)

Evaluation of Agency Non-Code Layered Pressure Vessels (LPVs) . Volume 2; Appendices

Science.gov (United States)

Prosser, William H.

2014-01-01

In coordination with the Office of Safety and Mission Assurance and the respective Center Pressure System Managers (PSMs), the NASA Engineering and Safety Center (NESC) was requested to formulate a consensus draft proposal for the development of additional testing and analysis methods to establish the technical validity, and any limitation thereof, for the continued safe operation of facility non-code layered pressure vessels. The PSMs from each NASA Center were asked to participate as part of the assessment team by providing, collecting, and reviewing data regarding current operations of these vessels. This document contains the appendices to the main report.

Review of technology for Arctic offshore oil and gas recovery. Appendices

Energy Technology Data Exchange (ETDEWEB)

Sackinger, W. M.

1980-06-06

This volume contains appendices of the following: US Geological Survey Arctic operating orders, 1979; Det Noske Vertas', rules for the design, construction and inspection of offshore technology, 1977; Alaska Oil and Gas Association, industry research projects, March 1980; Arctic Petroleum Operator's Association, industry research projects, January 1980; selected additional Arctic offshore bibliography on sea ice, icebreakers, Arctic seafloor conditions, ice-structures, frost heave and structure icing.

Transmission System Vegetation Management Program. Draft Environmental Impact Statement - Appendices

International Nuclear Information System (INIS)

1999-01-01

The appendices covered in this Draft Environmental Impact Statement are: Appendix A--Public involvement; Appendix B--Biological weed control agents; Appendix C--BPA herbicide licensing plan; Appendix D--Sample educational information; Appendix E--Clearance criteria; Appendix F--USFS mitigation measures and background; Appendix G--BLM mitigation measures and background and Appendix H--Pesticide fact sheets

Environmental assessment of remedial action at the Lakeview Uranium Mill Tailings Site, Lakeview, Oregon: Volume 2, Appendices

International Nuclear Information System (INIS)

1985-04-01

This document assesses and compares the environmental impacts of various alternatives for remedial action at the Lakeview uranium mill tailings site located one mile north of Lakeview, Oregon. The site covers 256 acres and contains 30 acres of tailings, 69 acres of evaporation ponds, and 25 acres of windblown materials. Remedial actions must be performed in accordance with standards and with the concurrence of the Nuclear Regulatory Commission. Three alternatives have been addressed in this document. The first alternative (the proposed action) is relocation of all contaminated materials to the Collins Ranch site. The contaminated materials would be consolidated into an embankment constructed partially below grade and covered with radon protection and erosion protection covers. A second alternative would relocate the tailings to the Flynn Ranch site and dispose of the contaminated materials in a slightly below grade embankment. A radon protection and erosion protection cover system would also be installed. The no-action alternative is also assessed. Stabilization in place is not considered due to potential seismic and geothermal hazards associated with the current tailings site, and the inability to meet EPA standards. Volume 2 contains 11 appendices

Methodologies for Verification and Validation of Space Launch System (SLS) Structural Dynamic Models: Appendices

Science.gov (United States)

Coppolino, Robert N.

2018-01-01

Verification and validation (V&V) is a highly challenging undertaking for SLS structural dynamics models due to the magnitude and complexity of SLS subassemblies and subassemblies. Responses to challenges associated with V&V of Space Launch System (SLS) structural dynamics models are presented in Volume I of this paper. Four methodologies addressing specific requirements for V&V are discussed. (1) Residual Mode Augmentation (RMA). (2) Modified Guyan Reduction (MGR) and Harmonic Reduction (HR, introduced in 1976). (3) Mode Consolidation (MC). Finally, (4) Experimental Mode Verification (EMV). This document contains the appendices to Volume I.

Hyperbilirubinemia as a predictor for appendiceal perforation

DEFF Research Database (Denmark)

Burcharth, J; Pommergaard, H C; Rosenberg, J

2013-01-01

Delayed or wrong diagnosis in patients with appendicitis can result in perforation and consequently increased morbidity and mortality. Serum bilirubin may be a useful marker for appendiceal perforation. The purpose of this systematic review was to evaluate studies investigating elevated serum...

Site characterization plan: Conceptual design report: Volume 4, Appendices F-O: Nevada Nuclear Waste Storage Investigations Project

Energy Technology Data Exchange (ETDEWEB)

MacDougall, H R; Scully, L W; Tillerson, J R [comps.

1987-09-01

The site for the prospective repository is located at Yucca Mountain in southwestern Nevada, and the waste emplacement area will be constructed in the underlying volcanic tuffs. The target horizon for waste emplacement is a sloping bed of densely welded tuff more than 650 ft below the surface and typically more than 600 ft above the water table. The conceptual design described in this report is unique among repository designs in that it uses ramps in addition to shafts to gain access to the underground facility, the emplacement horizon is located above the water table, and it is possible that 300- to 400-ft-long horizontal waste emplacement boreholes will be used. This report summarizes the design bases, design and performance criteria, and the design analyses performed. The current status of meeting the preclosure performance objectives for licensing and of resolving the repository design and preclosure issues is presented. The repository design presented in this report will be expanded and refined during the advanced conceptual design, the license application design, and the final procurement and construction design phases. Volume 4 contains Appendices F to O.

Site characterization plan: Conceptual design report: Volume 4, Appendices F-O: Nevada Nuclear Waste Storage Investigations Project

International Nuclear Information System (INIS)

MacDougall, H.R.; Scully, L.W.; Tillerson, J.R.

1987-09-01

The site for the prospective repository is located at Yucca Mountain in southwestern Nevada, and the waste emplacement area will be constructed in the underlying volcanic tuffs. The target horizon for waste emplacement is a sloping bed of densely welded tuff more than 650 ft below the surface and typically more than 600 ft above the water table. The conceptual design described in this report is unique among repository designs in that it uses ramps in addition to shafts to gain access to the underground facility, the emplacement horizon is located above the water table, and it is possible that 300- to 400-ft-long horizontal waste emplacement boreholes will be used. This report summarizes the design bases, design and performance criteria, and the design analyses performed. The current status of meeting the preclosure performance objectives for licensing and of resolving the repository design and preclosure issues is presented. The repository design presented in this report will be expanded and refined during the advanced conceptual design, the license application design, and the final procurement and construction design phases. Volume 4 contains Appendices F to O

Injection of radioactive waste by hydraulic fracturing at West Valley, New York. Volume 3. Appendices

International Nuclear Information System (INIS)

1978-05-01

Ten appendices are included: log data, elastic constants for transversely isotropic elastic media by ultrasonic velocity measurement, fracture toughness anisotropy of West Valley shale, in-situ stress measurement techniques, stress measurement data, hydraulic fracturing measurements, enhancement of horizontal crack initiation by jetting, finite element programs for analysis of crack propagation and for groundwater flow analysis, and well data

Radiological performance assessment for the E-Area Vaults Disposal Facility. Appendices A through M

Energy Technology Data Exchange (ETDEWEB)

Cook, J.R.

1994-04-15

These document contains appendices A-M for the performance assessment. They are A: details of models and assumptions, B: computer codes, C: data tabulation, D: geochemical interactions, E: hydrogeology of the Savannah River Site, F: software QA plans, G: completeness review guide, H: performance assessment peer review panel recommendations, I: suspect soil performance analysis, J: sensitivity/uncertainty analysis, K: vault degradation study, L: description of naval reactor waste disposal, M: porflow input file. (GHH)

Resource Conservation and Recovery Act: Part B permit application. Volume 9. Chapter E, Appendix E1-Chapter H, Appendix H3

International Nuclear Information System (INIS)

1995-01-01

Volume nine contains the following appendices: RCRA groundwater protection information; Examples of inspection sheets, logs and instructions for systems/equipment requiring inspection under 20 NMAC 4.1, Subpart V; Material safety data sheets; List of hazardous waste management job titles; and Waste Isolation Pilot Plant RCRA hazardous waste management job description

Final safety evaluation report related to the certification of the System 80+ design (Docket No. 52-002). Volume 2, Chapters 15--22 and appendices

International Nuclear Information System (INIS)

1994-08-01

This final safety evaluation report (FSER) documents the technical review of the System 80+ standard design by the US Nuclear Regulatory Commission (NRC) staff. The application for the system 80+ design was submitted by Combustion Engineering, Inc., now Asea Brown Boveri-Combustion Engineering (ABB-CE) as an application for design approval and subsequent design certification pursuant to 10 CFR section 52.45. System 80+ is a pressurized water reactor with a rated power of 3914 megawatts thermal (MWt) and a design power of 3992 MWt at which accidents are analyzed. Many features of the System 80+ are similar to those of ABB-CE's System 80 design from which it evolved. Unique features of the System 80+ design include: a large spherical, steel containment; an in-containment refueling water storage tank; a reactor cavity flooding system, hydrogen ignitors and a safety depressurization system for severe accident mitigation; a combustion gas turbine for an alternate ac source; and an advanced digitally based control room. On the basis of its evaluation and independent analyses, the NRC staff concludes that ABB-CE's application for design certification meets the requirements of Subpart B of 10 CFR Part 52 that are applicable and technically relevant to the System 80+ standard design. This document, Volume 2, contains Chapters 15 through 22 and Appendices A through E

Airborne gamma-ray spectrometer and magnetometer survey: Cameron A, Arizona, detail area. Volume II A. Final report

International Nuclear Information System (INIS)

1983-01-01

Volume II A contains appendices for: stacked profiles; geologic histograms; geochemical histograms; speed and altitude histograms; geologic statistical tables; geochemical statistical tables; magnetic and ancillary profiles; and test line data

Special Education Finance in California. Technical Appendices

Science.gov (United States)

Hill, Laura; Warren, Paul; Murphy, Patrick; Ugo, Iwunze; Pathak, Aditi

2016-01-01

This document presents the technical appendices that accompany the full report, "Special Education Finance in California." The appendices include: (1) Problems with AB 602 and Other State Funding Programs for Special Education; (2) Additional Figures for Analysis of Distribution of Students with Disabilities; (3) Using Supplemental and…

Appendiceal diameter: CT versus sonographic measurements

Energy Technology Data Exchange (ETDEWEB)

Orscheln, Emily S. [University of Cincinnati Medical Center, Department of Radiology, Cincinnati, OH (United States); Trout, Andrew T. [Cincinnati Children' s Hospital Medical Center, Department of Radiology, Cincinnati, OH (United States)

2016-03-15

Ultrasound and CT are the dominant imaging modalities for assessment of suspected pediatric appendicitis, and the most commonly applied diagnostic criterion for both modalities is appendiceal diameter. The classically described cut-off diameter for the diagnosis of appendicitis is 6 mm when using either imaging modality. To demonstrate the fallacy of using the same cut-off diameter for both CT and US in the diagnosis of appendicitis. We conducted a retrospective review of patients younger than 18 years who underwent both US and CT of the appendix within 24 h. The shortest transverse dimension of the appendix was measured at the level of the proximal, mid and distal appendix on US and CT images. We compared mean absolute difference in appendiceal diameter between US and CT, using the paired t-test. We reviewed exams of 155 children (58.7% female) with a mean age of 11.3 ± 4.2 years; 38 of the children (24.5%) were diagnosed with appendicitis. The average time interval between US and CT was 7.0 ± 5.4 h. Mean appendiceal diameter measured by CT was significantly larger than that measured by US in cases without appendicitis (5.3 ± 1.0 mm vs. 4.7 ± 1.1 mm, P < 0.0001) and in cases with appendicitis (8.3 ± 2.2 mm vs. 7.0 ± 2.0 mm, P < 0.0001). Mean absolute diameter difference at any location along the appendix was 1.3-1.4 mm in normal appendices and 2 mm in cases of appendicitis. Measured appendiceal diameter differs between US and CT by 1-2 mm, calling into question use of the same diameter cut-off (6 mm) for both modalities for the diagnosis of appendicitis. (orig.)

Appendiceal diameter: CT versus sonographic measurements

International Nuclear Information System (INIS)

Orscheln, Emily S.; Trout, Andrew T.

2016-01-01

Ultrasound and CT are the dominant imaging modalities for assessment of suspected pediatric appendicitis, and the most commonly applied diagnostic criterion for both modalities is appendiceal diameter. The classically described cut-off diameter for the diagnosis of appendicitis is 6 mm when using either imaging modality. To demonstrate the fallacy of using the same cut-off diameter for both CT and US in the diagnosis of appendicitis. We conducted a retrospective review of patients younger than 18 years who underwent both US and CT of the appendix within 24 h. The shortest transverse dimension of the appendix was measured at the level of the proximal, mid and distal appendix on US and CT images. We compared mean absolute difference in appendiceal diameter between US and CT, using the paired t-test. We reviewed exams of 155 children (58.7% female) with a mean age of 11.3 ± 4.2 years; 38 of the children (24.5%) were diagnosed with appendicitis. The average time interval between US and CT was 7.0 ± 5.4 h. Mean appendiceal diameter measured by CT was significantly larger than that measured by US in cases without appendicitis (5.3 ± 1.0 mm vs. 4.7 ± 1.1 mm, P < 0.0001) and in cases with appendicitis (8.3 ± 2.2 mm vs. 7.0 ± 2.0 mm, P < 0.0001). Mean absolute diameter difference at any location along the appendix was 1.3-1.4 mm in normal appendices and 2 mm in cases of appendicitis. Measured appendiceal diameter differs between US and CT by 1-2 mm, calling into question use of the same diameter cut-off (6 mm) for both modalities for the diagnosis of appendicitis. (orig.)

Analysis of the permitting processes associated with exploration of Federal OCS leases. Final report. Volume II. Appendices

Energy Technology Data Exchange (ETDEWEB)

1980-11-01

Under contract to the Office of Leasing Policy Development (LPDO), Jack Faucett Associates is currently undertaking the description and analysis of the Outer Continental Shelf (OCS) regulatory process to determine the nature of time delays that affect OCS production of oil and gas. This report represents the results of the first phase of research under this contract, the description and analysis of regulatory activity associated with exploration activities on the Federal OCS. Volume 1 contains the following three sections: (1) study results; (2) Federal regulatory activities during exploration of Federal OCS leases which involved the US Geological Survey, Environmental Protection Agency, US Coast Guard, Corps of Engineers, and National Ocean and Atmospheric Administration; and (3) state regulatory activities during exploration of Federal OCS leases of Alaska, California, Louisiana, Massachusetts, New Jersey, North Carolina and Texas. Volume II contains appendices of US Geological Survey, Environmental Protection Agency, Coast Guard, Corps of Engineers, the Coastal Zone Management Act, and Alaska. The major causes of delay in the regulatory process governing exploration was summarized in four broad categories: (1) the long and tedious process associated with the Environmental Protection Agency's implementation of the National Pollutant Discharge Elimination System Permit; (2) thelack of mandated time periods for the completion of individual activities in the permitting process; (3) the lack of overall coordination of OCS exploratory regulation; and (4) the inexperience of states, the Federal government and industry relating to the appropriate level of regulation for first-time lease sale areas.

1992 Columbia River Salmon Flow Measures Options Analysis/EIS : Appendices.

Energy Technology Data Exchange (ETDEWEB)

1992-01-01

This Options Analysis/Environmental Impact Statement (OA/EIS) identifies, presents effects of, and evaluates the potential options for changing instream flow levels in efforts to increase salmon populations in the lower Columbia and Snake rivers. The potential actions would be implemented during 1992 to benefit juvenile and adult salmon during migration through eight run-of-river reservoirs. The Corps of Engineers (Corps) prepared this document in cooperation with the Bonneville Power Administration and the Bureau of Reclamation. The US Fish and Wildlife Service (FWS) is a participating agency. The text and appendices of the document describe the characteristics of 10 Federal projects and one private water development project in the Columbia River drainage basin. Present and potential operation of these projects and their effects on the salmon that spawn and rear in the Columbia and Snake River System are presented. The life history, status, and response of Pacific salmon to current environmental conditions are described. The document concludes with an evaluation of the potential effects that could result from implementing proposed actions. The conclusions are based on evaluation of existing data, utilization of numerical models, and application of logical inference. This volume contains the appendices.

1992 Columbia River salmon flow measures Options Analysis/EIS: Appendices

International Nuclear Information System (INIS)

1992-01-01

This Options Analysis/Environmental Impact Statement (OA/EIS) identifies, presents effects of, and evaluates the potential options for changing instream flow levels in efforts to increase salmon populations in the lower Columbia and Snake rivers. The potential actions would be implemented during 1992 to benefit juvenile and adult salmon during migration through eight run-of-river reservoirs. The Corps of Engineers (Corps) prepared this document in cooperation with the Bonneville Power Administration and the Bureau of Reclamation. The US Fish and Wildlife Service (FWS) is a participating agency. The text and appendices of the document describe the characteristics of 10 Federal projects and one private water development project in the Columbia River drainage basin. Present and potential operation of these projects and their effects on the salmon that spawn and rear in the Columbia and Snake River System are presented. The life history, status, and response of Pacific salmon to current environmental conditions are described. The document concludes with an evaluation of the potential effects that could result from implementing proposed actions. The conclusions are based on evaluation of existing data, utilization of numerical models, and application of logical inference. This volume contains the appendices

Resource Conservation and Recovery Act: Part B Permit application. Volume 2, Chapter C, Appendix C1-Appendix C8

International Nuclear Information System (INIS)

1995-01-01

Volume 2 contains appendices for the following: chemical compatibility analysis of waste forms and container materials; data accumulated from headspace-gas analyses; totals analysis versus toxicity characteristic leaching procedure; waste characterization sampling methods; applicability of real-time radiography; quality assurance objectives for waste characterization sampling and analytical methods; quality assurance project plan requirements; and Waste Isolation Pilot Plant generator/storage site waste screening and acceptance audit program

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)

Refinery siting workbook: appendices A and B

Energy Technology Data Exchange (ETDEWEB)

1980-07-01

The objective of this effort is to develop and provide basic refinery-related information for use by state and local government officials as a basis for establishing responsible refinery siting requirements and policies consistent with the federal clean air and water standards and socio-economic concerns. The report will be organized into two volumes. The main text comprises the basic topics of physical concerns, regulatory requirements, and permitting activities, while the second volume includes the detailed appendix materials such as the applicable laws, and the necessary permits, as available and a glossary of pertinent terms. As a means to this objective, three refinery sizes, 200,000, 100,000 and 30,000 barrels per day crude charge will be discussed in technical terms. Process unit configuration will be presented which will maximize either gasoline or heating oil production with either sweet or sour crude oil feedstocks. The major issues affecting the socio-economic impact of siting the refinery in a given locale will be presented. These data will review the factors affecting the human environment and the issues that must be addressed to assess the impact that a refinery will have on a community. The key federal registrations which impact upon a refinery siting decision shall be reviewed. Summaries of these regulations and a simplified decision diagram for the air and water acts shall be presented to assist both government and refinery officials in understanding the scope of regulatory impact. All pertinent procedures required for refinery permitting shall be reviewed under the generalized headings of air, water, health and safety, land use, and miscellaneous permits. This categorization at the federal, state and local levels of government shall be used as a basis for establishing degrees of emphasis.

Final safety evaluation report related to the certification of the System 80{sup +} design (Docket No. 52-002). Volume 2, Chapters 15--22 and appendices

Energy Technology Data Exchange (ETDEWEB)

1994-08-01

This final safety evaluation report (FSER) documents the technical review of the System 80+ standard design by the US Nuclear Regulatory Commission (NRC) staff. The application for the system 80+ design was submitted by Combustion Engineering, Inc., now Asea Brown Boveri-Combustion Engineering (ABB-CE) as an application for design approval and subsequent design certification pursuant to 10 CFR {section} 52.45. System 80+ is a pressurized water reactor with a rated power of 3914 megawatts thermal (MWt) and a design power of 3992 MWt at which accidents are analyzed. Many features of the System 80+ are similar to those of ABB-CE`s System 80 design from which it evolved. Unique features of the System 80+ design include: a large spherical, steel containment; an in-containment refueling water storage tank; a reactor cavity flooding system, hydrogen ignitors and a safety depressurization system for severe accident mitigation; a combustion gas turbine for an alternate ac source; and an advanced digitally based control room. On the basis of its evaluation and independent analyses, the NRC staff concludes that ABB-CE`s application for design certification meets the requirements of Subpart B of 10 CFR Part 52 that are applicable and technically relevant to the System 80+ standard design. This document, Volume 2, contains Chapters 15 through 22 and Appendices A through E.

Conceptual design of advanced central receiver power systems sodium-cooled receiver concept. Volume 2, Book 2. Appendices. Final report

Energy Technology Data Exchange (ETDEWEB)

1979-03-01

The appendices include: (A) design data sheets and P and I drawing for 100-MWe commercial plant design, for all-sodium storage concept; (B) design data sheets and P and I drawing for 100-MWe commercial plant design, for air-rock bed storage concept; (C) electric power generating water-steam system P and I drawing and equipment list, 100-MWe commercial plant design; (D) design data sheets and P and I drawing for 281-MWe commercial plant design; (E) steam generator system conceptual design; (F) heat losses from solar receiver surface; (G) heat transfer and pressure drop for rock bed thermal storage; (H) a comparison of alternative ways of recovering the hydraulic head from the advanced solar receiver tower; (I) central receiver tower study; (J) a comparison of mechanical and electromagnetic sodium pumps; (K) pipe routing study of sodium downcomer; and (L) sodium-cooled advanced central receiver system simulation model. (WHK)

Appendiceal Endometriosis: A case Report and Literature Review ...

African Journals Online (AJOL)

Appendiceal endometriosis is a very rare and usually asymptomatic condiction, but can result in severe complications such as intestinal perforation, massive gastrointestinal bleeding or intussusception. We report a case of endometriosis of the appendix presenting as acute appendicitis. The patient was a 36 year old ...

Characterization of Class A low-level radioactive waste 1986--1990. Volume 3: Main report -- Part B

Energy Technology Data Exchange (ETDEWEB)

Dehmel, J.C.; Loomis, D.; Mauro, J. [S. Cohen & Associates, Inc., McLean, VA (United States); Kaplan, M. [Eastern Research Group, Inc., Lexington, MA (United States)

1994-01-01

Under contract to the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, the firms of S. Cohen & Associates, Inc. (SC&A) and Eastern Research Group (ERG) have compiled a report that describes the physical, chemical, and radiological properties of Class-A low-level radioactive waste. The report also presents information characterizing various methods and facilities used to treat and dispose non-radioactive waste. A database management program was developed for use in accessing, sorting, analyzing, and displaying the electronic data provided by EG&G. The program was used to present and aggregate data characterizing the radiological, physical, and chemical properties of the waste from descriptions contained in shipping manifests. The data thus retrieved are summarized in tables, histograms, and cumulative distribution curves presenting radionuclide concentration distributions in Class-A waste as a function of waste streams, by category of waste generators, and regions of the United States. The report also provides information characterizing methods and facilities used to treat and dispose non-radioactive waste, including industrial, municipal, and hazardous waste regulated under Subparts C and D of the Resource Conservation and Recovery Act (RCRA). The information includes a list of disposal options, the geographical locations of the processing and disposal facilities, and a description of the characteristics of such processing and disposal facilities. Volume 1 contains the Executive Summary, Volume 2 presents the Class-A waste database, Volume 3 presents the information characterizing non-radioactive waste management practices and facilities, and Volumes 4 to 7 contain Appendices A to P with supporting information.

Significance of appendiceal thickening in association with typhlitis in pediatric oncology patients

International Nuclear Information System (INIS)

McCarville, M.B.; Thompson, J.; Adelman, C.S.; Lee, M.O.; Li, C.; Alsammarae, D.; Rao, B.N.; May, M.V.; Jones, S.C.; Sandlund, J.T.

2004-01-01

Background: The management of pediatric oncology patients with imaging evidence of appendiceal thickening is complex because they are generally poor surgical candidates and often have confounding clinical findings. Objective: We sought to determine the significance of appendiceal thickening in pediatric oncology patients who also had typhlitis. Specifically, we evaluated the impact of this finding on the duration of typhlitis, its clinical management, and outcome. Materials and methods: From a previous review of the management of typhlitis in 90 children with cancer at our institution, we identified 4 with imaging evidence of appendiceal thickening. We compared colonic wall measurements, duration of typhlitis symptoms, management, and outcome of patients with appendiceal thickening and typhlitis to patients with typhlitis alone. Results: There was no significant difference in duration of typhlitis symptoms between patients with typhlitis only (15.6 ± 1.2 days) and those with typhlitis and appendiceal thickening (14.5 ± 5.8 days; P = 0.9). Two patients with appendiceal thickening required surgical treatment for ischemic bowel, and two were treated medically. Only one patient in the typhlitis without appendiceal thickening group required surgical intervention. There were no deaths in children with appendiceal thickening; two patients died of complications of typhlitis alone. (orig.)

Radiographic features of appendiceal colic in children

International Nuclear Information System (INIS)

Schisgall, R.M.

1986-01-01

The concept of appendiceal colic was introduced in 1980 to explain the common problem of recurrent crampy abdominal pain (RAP) in children. Children with appendiceal colic often have inspissated casts of stool as foreign bodies of the appendix. The radiographic findings of 115 children operated upon for appendiceal colic have been reviewed. The radiographic features of this syndrom have included: filling defects of the appendix (83% incidence of inspissated casts of stool within the appendix); partial filling of the appendix (44% incidence of fecal casts); retained barium behind 72 h (92% incidence of fecal casts blocking egress of barium); non-visualization of the appendix (42% incidence of fecal casts); and distention of the appendix (100% incidence of fecal casts). The correlation of radiographic and operative findings will be presented. A rational approach to the radiographic workup of a child with RAP will be presented. (orig.)

Computed tomography of appendiceal mucocele and peritoneal pseudomyxoma

International Nuclear Information System (INIS)

Lund, G.; Lien, H.H.

1982-01-01

Peritoneal pseudomyxoma is a colloidal growth, which develops on the peritoneum, often secondary to an ovarian tumor or mucocele of the appendix. The conventional radiographic findings of appendiceal mucocele were described by Akerlund, and the CT-pseudomyxoma have been reported by Seshul and Coulam. The present case illustrates the CT-findings of an appendiceal mucocele as well as the complicating peritoneal pseudomyxoma. (orig.)

A Case of Appendiceal Adenocarcinoma with Clinical Benefit from FOLFOX and Bevacizumab

Directory of Open Access Journals (Sweden)

Erin D. Powell

2009-07-01

Full Text Available A 44-year-old woman presented with lower abdominal pain and bilateral ovarian masses on ultrasound. Exploratory laparotomy revealed extensive peritoneal and intra-abdominal disease and an abnormal appendix. Bilateral salpingo-oophorectomy, infracolic omentectomy, ileocolic resection and primary anastomosis were performed. Final pathology revealed a primary appendiceal adenocarcinoma, poorly differentiated, of signet ring cell type. CT scan postoperatively revealed gross residual disease. The patient was treated with FOLFOX chemotherapy combined with bevacizumab. Repeat CT scan showed a decrease in residual disease and the patient clinically improved. After her treatment has been continued for 13 months, she remains clinically well and her CT scan shows sustained disease stability. Disseminated appendiceal carcinoma is generally considered to be refractory to 5-FU-based chemotherapy and, to our knowledge, this is the first reported case of a patient with appendiceal adenocarcinoma demonstrating clinical benefit and sustained stability of disease with combination chemotherapy plus bevacizumab.

Appendiceal immunoglobulin G4-related disease mimicking appendiceal tumor or appendicitis: A case report

International Nuclear Information System (INIS)

Kim, Hyun Soo; Kang, Won Kyung; Chung, Dong Jin

2016-01-01

Immunoglobulin G4 (IgG4)-related disease is an autoimmune disease that forms tumorous lesions. Several cases involving various organs are reported, however, IgG4-related disease involving appendix has not been reported yet. In this report, we presented a case of IgG4-related disease of appendix, which raised a suspicion of appendiceal tumor or usual appendicitis and, therefore, led to unnecessary surgical resection. IgG4-related disease should be considered in the differential diagnosis for a mass-like swelling of the appendix, in order to avoid unnecessary surgery

Appendiceal immunoglobulin G4-related disease mimicking appendiceal tumor or appendicitis: A case report

Energy Technology Data Exchange (ETDEWEB)

Kim, Hyun Soo; Kang, Won Kyung; Chung, Dong Jin [Yeouido St. Mary' s Hospital, The Catholic University of Korea, Seoul (Korea, Republic of)

2016-02-15

Immunoglobulin G4 (IgG4)-related disease is an autoimmune disease that forms tumorous lesions. Several cases involving various organs are reported, however, IgG4-related disease involving appendix has not been reported yet. In this report, we presented a case of IgG4-related disease of appendix, which raised a suspicion of appendiceal tumor or usual appendicitis and, therefore, led to unnecessary surgical resection. IgG4-related disease should be considered in the differential diagnosis for a mass-like swelling of the appendix, in order to avoid unnecessary surgery.

Market analysis of shale oil co-products. Appendices

Energy Technology Data Exchange (ETDEWEB)

1980-12-01

Data are presented in these appendices on the marketing and economic potential for soda ash, aluminia, and nahcolite as by-products of shale oil production. Appendices 1 and 2 contain data on the estimated capital and operating cost of an oil shales/mineral co-products recovery facility. Appendix 3 contains the marketing research data.

12 CFR Appendices F-I to Part 41 - [Reserved

Science.gov (United States)

2010-01-01

... 12 Banks and Banking 1 2010-01-01 2010-01-01 false [Reserved] F Appendices F-I to Part 41 Banks and Banking COMPTROLLER OF THE CURRENCY, DEPARTMENT OF THE TREASURY FAIR CREDIT REPORTING Appendices F-I to Part 41[Reserved] ...

Early Site Permit Demonstration Program: Guidelines for determining design basis ground motions. Volume 2, Appendices

Energy Technology Data Exchange (ETDEWEB)

1993-03-18

This report develops and applies a methodology for estimating strong earthquake ground motion. The motivation was to develop a much needed tool for use in developing the seismic requirements for structural designs. An earthquake`s ground motion is a function of the earthquake`s magnitude, and the physical properties of the earth through which the seismic waves travel from the earthquake fault to the site of interest. The emphasis of this study is on ground motion estimation in Eastern North America (east of the Rocky Mountains), with particular emphasis on the Eastern United States and southeastern Canada. Eastern North America is a stable continental region, having sparse earthquake activity with rare occurrences of large earthquakes. While large earthquakes are of interest for assessing seismic hazard, little data exists from the region to empirically quantify their effects. The focus of the report is on the attributes of ground motion in Eastern North America that are of interest for the design of facilities such as nuclear power plants. This document, Volume II, contains Appendices 2, 3, 5, 6, and 7 covering the following topics: Eastern North American Empirical Ground Motion Data; Examination of Variance of Seismographic Network Data; Soil Amplification and Vertical-to-Horizontal Ratios from Analysis of Strong Motion Data From Active Tectonic Regions; Revision and Calibration of Ou and Herrmann Method; Generalized Ray Procedure for Modeling Ground Motion Attenuation; Crustal Models for Velocity Regionalization; Depth Distribution Models; Development of Generic Site Effects Model; Validation and Comparison of One-Dimensional Site Response Methodologies; Plots of Amplification Factors; Assessment of Coupling Between Vertical & Horizontal Motions in Nonlinear Site Response Analysis; and Modeling of Dynamic Soil Properties.

Chronic appendicitis and complete appendiceal invagination: UC, CT and MRI findings

International Nuclear Information System (INIS)

Diaz, Gabriel; Seehaus, Alberto; Ocantos, Jorge; Diaz, Claudia; Coccaro, Nicolas; Piccioni, Hector

2003-01-01

The appendiceal intussusception is a rare entity. Usually there is a predisposing factor such as a tumor, mucocele, etc. We report the case of a 61 years old female patient, with recurrent abdominal pain, localized in the right lower quadrant. We performed different diagnostic imaging exams including: double-contrast barium enema, enteroclysis, ultrasonography, computed tomography and magnetic resonance. After endoscopy a surgical procedure removed the appendix. The pathological anatomy confirmed the diagnosis of an appendiceal intussusception, complicated with a chronic inflammatory process. Appendiceal intussusception and chronic appendicitis are infrequent; it is even more uncommon the association of both entities. In addition, it was not found a predisposing cause to intussusception. For the reasons described above, we conclude that this case is an unusual presentation of appendiceal intussusception, not previously reported. (author)

Acoustic measurements of a full-scale rotor with four tip shapes. Volume 1: Text, appendices A and B

Science.gov (United States)

Mosher, M.

1984-01-01

A full-scale helicopter with four different blade-tip geometries was tested in the 40- by 80-foot wind tunnel at Ames Research Center. Performance, loads, and noise were measured. The four tip shapes tested were rectangular, tapered, swept, and swept-tapered. Noise measurements from that test are presented in the form of tables and plots. The noise data include measurements of the sound pressure level in dB, dBA, and tone-corrected PNdB, for all of the conditions tested. Detailed measurements, 1/3-octave spectra and time-histories for some selected data are included as well as plots of dBA as function of test condition. Some performance measurements are given to aid interpretation of the noise data.

Normal patterns of 18F-FDG appendiceal uptake in children

Energy Technology Data Exchange (ETDEWEB)

Reavey, Hamilton E. [Emory University, Department of Radiology and Imaging Sciences, Division of Nuclear Medicine Molecular Imaging, Atlanta, GA (United States); Alazraki, Adina L.; Simoneaux, Stephen F. [Emory University, Department of Radiology and Imaging Sciences, Division of Pediatric Imaging, Children' s Healthcare of Atlanta at Egleston, Atlanta, GA (United States)

2014-04-15

Prior to interpreting PET/CT, it is crucial to understand the normal biodistribution of fluorodeoxyglucose (FDG). It is also important to realize that the normal biodistribution can vary between adults and children. Although many studies have defined normal patterns of pediatric FDG uptake in structures like the thymus, brown fat and bone marrow, patterns of normal pediatric bowel activity, specifically uptake within the appendix, have not been well described. Active lymphoid tissue has increased FDG uptake when compared with inactive tissue. Since children have more active lymphoid tissue than adults, and because the appendix contains aggregated lymphoid tissue, we postulated that appendiceal uptake may be increased in pediatric patients. To define the normal level of appendiceal FDG activity in children by evaluating a series of consecutive FDG PET/CT scans performed for other indications. After obtaining IRB approval, we retrospectively reviewed 128 consecutive whole-body pediatric FDG PET/CT examinations obtained for a variety of clinical indications. CT scans on which the appendix could not be visualized were excluded from analysis. CT scans on which the appendix could be visualized were evaluated for underlying appendiceal pathology. Studies with appendiceal or periappendiceal pathology by CT criteria were excluded. A region of interest (ROI) was placed over a portion of each appendix and appendiceal maximum standardized uptake value (SUVmax) was calculated. If an adjacent loop of bowel activity interfered with accurate measurements of the appendix SUVmax, the scan was excluded from the analysis. A chart review was performed on patients with elevated appendiceal SUVmax values to ensure that the patients did not have clinical symptomatology suggestive of acute appendicitis. When the appendix or a portion of the appendix could be visualized and accurately measured, the SUVmax was determined. SUVmax of the appendix was compared to the SUVmax of normal liver and

Appendiceal pathology at the time of oophorectomy for ovarian neoplasms.

Science.gov (United States)

Timofeev, Julia; Galgano, Mary T; Stoler, Mark H; Lachance, Jason A; Modesitt, Susan C; Jazaeri, Amir A

2010-12-01

To investigate the prevalence of appendiceal pathology in women undergoing surgery for a suspected ovarian neoplasm and the predictive value of intraoperative findings to determine the need for appendectomy at the time of surgery. Retrospective analysis of patients who underwent oophorectomy and appendectomy during the same surgical procedures at the University of Virginia Health System from 1992 to 2007. Observations were stratified based on the nature (benign, borderline, or malignant) and histology (serous compared with mucinous) of the ovarian neoplasm, frozen compared with final pathological diagnosis, and the gross appearance of the appendix. Among the 191 patients identified, frozen section was consistent with seven mucinous and 35 serous carcinomas, 16 serous and 33 mucinous borderline tumors, 71 mucinous and serous cystadenomas, and 29 cases of suspected metastatic tumor from a gastrointestinal primary. The highest rates of coexisting appendiceal pathology were associated with serous ovarian cancers (94.4% of grossly abnormal and 35.3% of normal appendices) and ovarian tumors suspected to be of primary gastrointestinal origin (83.3% grossly abnormal and 60.0% normal appendices harbored coexisting mucinous neoplasms). Linear regression analysis revealed that appearance of the appendix and frozen section diagnosis of the ovarian pathology were statistically significant predictors of coexisting appendiceal pathology, but the latter was more important. The prevalence of coexisting, clinically significant appendiceal pathology is low with a frozen section diagnosis of serous or mucinous cystadenoma. Appendectomy is recommended when frozen section diagnosis is mucinous or serous ovarian carcinoma, borderline tumor or metastatic carcinoma of suspected gastrointestinal origin.

The safety culture of the nuclear plants of Sydkraft. Appendices 5-7

International Nuclear Information System (INIS)

Edmondson, B.; Firing, J.A.; Nordland, O.S.; Ottne, E.

1994-01-01

This separate volume of appendices contains three contributions: ''Safety in Nuclear Electric'' by Bryan Edmondson, which reviews the legislation for nuclear safety in Britain, reproduces the Health and Policy Statement by Nuclear Electric, and describes the management of health and safety in the company. ''Safety in Norwegian off-shore industry'' by Joergen A. Firing, describing the safety practices of the Statoil Group and reproducing the relevant Norwegian law. ''The safety management in SAS Airline. The safety and quality in airline industries'' by O.S. Nordland and E. Ottne describing safety organization, internal control systems, and education and training in SAS

Research reactor core conversion guidebook. V. 3: Analytical verification (Appendices G and H)

International Nuclear Information System (INIS)

1992-04-01

Volume 3 consists of Appendix G which contains detailed results of a safety-related benchmark problem for an idealized reactor and Appendix H which contains detailed comparisons of calculated and measured data for actual cores with moderately enriched uranium and low enriched uranium fuels. The results of the benchmark calculations in Appendix G are summarized in Chapter 7 of Volume 1 and the results of the comparisons between calculations and measurements are summarized in Chapter 8 of Volume 1. Both the approaches described in these appendices are very useful in ensuring that the calculational methods employed in the preparation of a Safety Report are accurate. As a first step, it is recommended that reactor operators/physicists use their own methods and codes to first calculate the benchmark problem, and then compare the results of calculations with measurements in their own reactor or in one of the reactors for which measured data is available in Appendix H. (author). Refs, figs and tabs

Intra-appendiceal air at CT: Is it a seful or a onfusing sign for the diagnosis of acute appendicitis?

International Nuclear Information System (INIS)

Hong, Hye Suk; Cho, Hyun Suk; Woo, Ji Young; Lee, Yul; Yang, Ik; Hwang, Ji Young; Kim, Han Myun; Kim, Jeong Won

2016-01-01

To investigate the significance of intra-appendiceal air at CT for the evaluation of appendicitis. We retrospectively analyzed 458 patients (216 men, 242 women; age range, 18-91 years) who underwent CT for suspected appendicitis. Two independent readers reviewed the CT. Prevalence, amount, and appearance of intra-appendiceal air were assessed and compared between the patients with and without appendicitis. Performance of CT diagnosis was evaluated in two reading strategies: once ignoring appendiceal air (strategy 1), and the other time considering presence of appendiceal air as indicative of no appendicitis in otherwise indeterminate cases (strategy 2), using receiver operating characteristic (ROC) analysis. Of the 458 patients, 102 had confirmed appendicitis. The prevalence of intra-appendiceal air was significantly different between patients with (13.2%) and without (79.8%) appendicitis (p < 0.001). The amount of appendiceal air was significantly lesser in patients having appendicitis as compared with the normal group, for both reader 1 (p = 0.011) and reader 2 (p = 0.002). Stool-like appearance and air-fluid levels were more common in the appendicitis group than in the normal appendix for both readers (p < 0.05). Areas under the ROC curves were not significantly different between strategies 1 and 2 in reader 1 (0.971 vs. 0.985, respectively; p = 0.056), but showed a small difference in reader 2 (0.969 vs. 0.986, respectively; p = 0.042). Although significant differences were seen in the prevalence, amount, and appearance of intra-appendiceal air between patients with and without appendicitis, it has a limited incremental value for the diagnosis of acute appendicitis

Intra-appendiceal air at CT: Is it a seful or a onfusing sign for the diagnosis of acute appendicitis?

Energy Technology Data Exchange (ETDEWEB)

Hong, Hye Suk; Cho, Hyun Suk; Woo, Ji Young; Lee, Yul; Yang, Ik; Hwang, Ji Young; Kim, Han Myun; Kim, Jeong Won [Kangnam Sacred Heart Hospital, Hallym University College of Medicine, Seoul (Korea, Republic of)

2016-02-15

To investigate the significance of intra-appendiceal air at CT for the evaluation of appendicitis. We retrospectively analyzed 458 patients (216 men, 242 women; age range, 18-91 years) who underwent CT for suspected appendicitis. Two independent readers reviewed the CT. Prevalence, amount, and appearance of intra-appendiceal air were assessed and compared between the patients with and without appendicitis. Performance of CT diagnosis was evaluated in two reading strategies: once ignoring appendiceal air (strategy 1), and the other time considering presence of appendiceal air as indicative of no appendicitis in otherwise indeterminate cases (strategy 2), using receiver operating characteristic (ROC) analysis. Of the 458 patients, 102 had confirmed appendicitis. The prevalence of intra-appendiceal air was significantly different between patients with (13.2%) and without (79.8%) appendicitis (p < 0.001). The amount of appendiceal air was significantly lesser in patients having appendicitis as compared with the normal group, for both reader 1 (p = 0.011) and reader 2 (p = 0.002). Stool-like appearance and air-fluid levels were more common in the appendicitis group than in the normal appendix for both readers (p < 0.05). Areas under the ROC curves were not significantly different between strategies 1 and 2 in reader 1 (0.971 vs. 0.985, respectively; p = 0.056), but showed a small difference in reader 2 (0.969 vs. 0.986, respectively; p = 0.042). Although significant differences were seen in the prevalence, amount, and appearance of intra-appendiceal air between patients with and without appendicitis, it has a limited incremental value for the diagnosis of acute appendicitis.

Residential photovoltaic module and array requirement study. Low-Cost Solar Array Project engineering area. Final report appendices

Energy Technology Data Exchange (ETDEWEB)

1979-06-01

This volume contains the appendices to a study to identify design requirements for photovoltaic modules and arrays used in residential applications. Appendices include: (1) codes, standards, and manuals of accepted practice-definition and importance; (2) regional code variations-impact; (3) model and city codes-review; (4) National Electric Code (NEC)-review; (5) types of standards-definition and importance; (6) federal standards-review; (7) standards review method; (8) manuals of accepted practice; (9) codes and referenced standards-summary; (10) public safety testing laboratories; (11) insurance review; (12) studies approach; (13) mounting configurations; (14) module/panel size and shape cost analysis; (15) grounding, wiring, terminal and voltage studies; (16) array installation cost summary; (17) photovoltaic shingle/module comparison; (18) retrofit application; (19) residential photovoltaic module performance criteria; (20) critique of JPL's solar cell module design and test specifications for residential applications; and (21) CSI format specification. (WHK)

Airborne gamma-ray spectrometer and magnetometer survey, Durango A, Colorado. Final report Volume II A. Detail area

International Nuclear Information System (INIS)

1983-01-01

This volume contains geology of the Durango A detail area, radioactive mineral occurences in Colorado, and geophysical data interpretation. Eight appendices provide the following: stacked profiles, geologic histograms, geochemical histograms, speed and altitude histograms, geologic statistical tables, geochemical statistical tables, magnetic and ancillary profiles, and test line data

Intra-Appendiceal Air at CT: Is It a Useful or a Confusing Sign for the Diagnosis of Acute Appendicitis?

Science.gov (United States)

Cho, Hyun Suk; Woo, Ji Young; Lee, Yul; Yang, Ik; Hwang, Ji-Young; Kim, Han Myun; Kim, Jeong Won

2016-01-01

Objective To investigate the significance of intra-appendiceal air at CT for the evaluation of appendicitis. Materials and Methods We retrospectively analyzed 458 patients (216 men, 242 women; age range, 18-91 years) who underwent CT for suspected appendicitis. Two independent readers reviewed the CT. Prevalence, amount, and appearance of intra-appendiceal air were assessed and compared between the patients with and without appendicitis. Performance of CT diagnosis was evaluated in two reading strategies: once ignoring appendiceal air (strategy 1), and the other time considering presence of appendiceal air as indicative of no appendicitis in otherwise indeterminate cases (strategy 2), using receiver operating characteristic (ROC) analysis. Results Of the 458 patients, 102 had confirmed appendicitis. The prevalence of intra-appendiceal air was significantly different between patients with (13.2%) and without (79.8%) appendicitis (p appendicitis as compared with the normal group, for both reader 1 (p = 0.011) and reader 2 (p = 0.002). Stool-like appearance and air-fluid levels were more common in the appendicitis group than in the normal appendix for both readers (p appendicitis, it has a limited incremental value for the diagnosis of acute appendicitis. PMID:26798214

Data collection system. Volume 1, Overview and operators manual; Volume 2, Maintenance manual; Appendices

Energy Technology Data Exchange (ETDEWEB)

Caudell, R.B.; Bauder, M.E.; Boyer, W.B.; French, R.E.; Isidoro, R.J.; Kaestner, P.C.; Perkins, W.G.

1993-09-01

Sandia National Laboratories (SNL) Instrumentation Development Department was tasked by the Defense Nuclear Agency (DNA) to record data on Tektronix RTD720 Digitizers on the HUNTERS TROPHY field test conducted at the Nevada Test Site (NTS) on September 18, 1992. This report contains a overview and description of the computer hardware and software that was used to acquire, reduce, and display the data. The document is divided into two volumes: an overview and operators manual (Volume 1) and a maintenance manual (Volume 2).

Sierra Pacific Power Company Alturas Transmission Line Project, Final Environmental Impact Report/Environmental Impact Statement. Volume 3: Appendices

International Nuclear Information System (INIS)

1995-11-01

Sierra Pacific Power Company has proposed the construction and operation of a 345,000 volt overhead electric power transmission line from Alturas, California to Reno, Nevada. This Environmental Impact Report/Environmental Impact Statement will assess the potential environmental impacts of the proposed project and alternatives. This report contains Appendices A--I which contain the following: glossary/abbreviations; scoping report; structure coordinate summary; air quality; biological resources; geology; noise; visual contrast rating forms; and cultural resources

Appendiceal and ovarian Burkitt's lymphoma presenting as acute appendicitis

Directory of Open Access Journals (Sweden)

Donovan Hui

2018-05-01

Full Text Available Burkitt's lymphoma is an extremely aggressive B-cell non-Hodgkin lymphoma. Patients with the sporadic form of Burkitt's lymphoma typically present with a rapidly growing abdominal mass, pain and distension. Involvement of either the appendix and/or ovaries in females is a rare manifestation of the disease. We present an unusual case of a 13 year old girl with appendiceal and ovarian Burkitt's lymphoma presenting with signs of acute appendicitis. This case demonstrates the potential for secondary involvement of the appendix and/or ovaries from Burkitt's lymphoma as well as the importance of the histopathology. Keywords: Appendicitis, Appendix, Burkitt's lymphoma, Lymphoma, Ovarian tumor

Ocean Thermal Energy Conversion (OTEC) Programmatic Environmental Analysis--Appendices

Energy Technology Data Exchange (ETDEWEB)

Authors, Various

1980-01-01

The programmatic environmental analysis is an initial assessment of Ocean Thermal Energy Conversion (OTEC) technology considering development, demonstration and commercialization. It is concluded that the OTEC development program should continue because the development, demonstration, and commercialization on a single-plant deployment basis should not present significant environmental impacts. However, several areas within the OTEC program require further investigation in order to assess the potential for environmental impacts from OTEC operation, particularly in large-scale deployments and in defining alternatives to closed-cycle biofouling control: (1) Larger-scale deployments of OTEC clusters or parks require further investigations in order to assess optimal platform siting distances necessary to minimize adverse environmental impacts. (2) The deployment and operation of the preoperational platform (OTEC-1) and future demonstration platforms must be carefully monitored to refine environmental assessment predictions, and to provide design modifications which may mitigate or reduce environmental impacts for larger-scale operations. These platforms will provide a valuable opportunity to fully evaluate the intake and discharge configurations, biofouling control methods, and both short-term and long-term environmental effects associated with platform operations. (3) Successful development of OTEC technology to use the maximal resource capabilities and to minimize environmental effects will require a concerted environmental management program, encompassing many different disciplines and environmental specialties. This volume contains these appendices: Appendix A -- Deployment Scenario; Appendix B -- OTEC Regional Characterization; and Appendix C -- Impact and Related Calculations.

Draft Waste Management Programmatic Environmental Impact Statement for managing treatment, storage, and disposal of radioactive and hazardous waste. Volume 3, Appendix A: Public response to revised NOI, Appendix B: Environmental restoration, Appendix C, Environmental impact analysis methods, Appendix D, Risk

International Nuclear Information System (INIS)

1995-08-01

Volume three contains appendices for the following: Public comments do DOE's proposed revisions to the scope of the waste management programmatic environmental impact statement; Environmental restoration sensitivity analysis; Environmental impacts analysis methods; and Waste management facility human health risk estimates

Draft Waste Management Programmatic Environmental Impact Statement for managing treatment, storage, and disposal of radioactive and hazardous waste. Volume 3, Appendix A: Public response to revised NOI, Appendix B: Environmental restoration, Appendix C, Environmental impact analysis methods, Appendix D, Risk

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-08-01

Volume three contains appendices for the following: Public comments do DOE`s proposed revisions to the scope of the waste management programmatic environmental impact statement; Environmental restoration sensitivity analysis; Environmental impacts analysis methods; and Waste management facility human health risk estimates.

A Methodology for Selection of a Satellite Servicing Architecture. Volume 3. Appendices.

Science.gov (United States)

1985-12-01

model transfers between inclined circu- lar orbits. If OSV time of flight becomes more critical . then a choice between the other two techniques is...ABSTRACT iContinue on ,viverse if necesary and identify by block, number) Title: A METODO ~LOGY FOR SELECION~ OF A SATELLITE SERVICING ARCHITEIR VOLUME

A tale of two appendices – an unexpected finding | Heetun | South ...

African Journals Online (AJOL)

Abstract. Anomalies of the appendix are uncommon and are usually discovered incidentally during surgery for appendicitis. We present a rare case of appendiceal duplication, which can have serious consequences if overlooked during an operation.

The safety of Ontario's nuclear power reactors. A scientific and technical review. Vol. 2: Appendices

International Nuclear Information System (INIS)

Hare, F.K.

1988-01-01

These appendices contain seven detailed elaborations of matters covered more superficially in the Technical Report. They have been written by well-known authorities, or by the professional staff of the Review. They are essential supplements to the condensed material of the Technical Report. Several of the appendices contain detailed recommendations. Some of these have been incorporated into the Review's overall conclusions and recommendations. Others stand alone, as the opinions of the appendices' authors. I am in broad agreement with most of them, but have preferred to leave them within the authors' material. I hope that they will be given detailed study by appropriate bodies, especially Ontario Hydro and the Atomic Energy Control Board

Wien Automatic System Package (WASP). A computer code for power generating system expansion planning. Version WASP-III Plus. User's manual. Volume 2: Appendices

International Nuclear Information System (INIS)

1995-01-01

With several Member States, the IAEA has completed a new version of the WASP program, which has been called WASP-Ill Plus since it follows quite closely the methodology of the WASP-Ill model. The major enhancements in WASP-Ill Plus with respect to the WASP-Ill version are: increase in the number of thermal fuel types (from 5 to 10); verification of which configurations generated by CONGEN have already been simulated in previous iterations with MERSIM; direct calculation of combined Loading Order of FIXSYS and VARSYS plants; simulation of system operation includes consideration of physical constraints imposed on some fuel types (i.e., fuel availability for electricity generation); extended output of the resimulation of the optimal solution; generation of a file that can be used for graphical representation of the results of the resimulation of the optimal solution and cash flows of the investment costs; calculation of cash flows allows to include the capital costs of plants firmly committed or in construction (FIXSYS plants); user control of the distribution of capital cost expenditures during the construction period (if required to be different from the general 'S' curve distribution used as default). This second volume of the document to support use of the WASP-Ill Plus computer code consists of 5 appendices giving some additional information about the WASP-Ill Plus program. Appendix A is mainly addressed to the WASP-Ill Plus system analyst and supplies some information which could help in the implementation of the program on the user computer facilities. This appendix also includes some aspects about WASP-Ill Plus that could not be treated in detail in Chapters 1 to 11. Appendix B identifies all error and warning messages that may appear in the WASP printouts and advises the user how to overcome the problem. Appendix C presents the flow charts of the programs along with a brief description of the objectives and structure of each module. Appendix D describes the

Extra-appendiceal findings in pediatric abdominal CT for suspected appendicitis

Energy Technology Data Exchange (ETDEWEB)

Halverson, Mark; Delgado, Jorge; Mahboubi, Soroosh [The Children' s Hospital of Philadelphia, Department of Radiology, Philadelphia, PA (United States)

2014-07-15

Much has been written regarding the incidence, types, importance and management of abdominal CT incidental findings in adults, but there is a paucity of literature on incidental findings in children. We sought to determine the prevalence and characteristics of extra-appendiceal and incidental findings in pediatric abdominal CT performed for suspected appendicitis. A retrospective review was performed of abdominal CT for suspected appendicitis in a pediatric emergency department from July 2010 to June 2012. Extra-appendiceal findings were recorded. Any subsequent imaging was noted. Extra-appendiceal findings were divided into incidental findings of doubtful clinical significance, alternative diagnostic findings potentially providing a diagnosis other than appendicitis explaining the symptoms, and incidental findings that were abnormalities requiring clinical correlation and sometimes requiring further evaluation but not likely related to the patient symptoms. One hundred sixty-five children had abdominal CT for suspected appendicitis. Seventy-seven extra-appendiceal findings were found in 57 (34.5%) patients. Most findings (64 of 77) were discovered in children who did not have appendicitis. Forty-one of these findings (53%) could potentially help explain the patient's symptoms, while 30 of the findings (39%) were abnormalities that were unlikely to be related to the symptoms but required clinical correlation and sometimes further work-up. Six of the findings (8%) had doubtful or no clinical significance. Extra-appendiceal findings are common in children who undergo abdominal CT in the setting of suspected appendicitis. A significant percentage of these patients have findings that help explain their symptoms. Knowledge of the types and prevalence of these findings may help radiologists in the planning and interpretation of CT examinations in this patient population. (orig.)

C-reactive Protein may Predict the Recurrence of Appendicitis in Children Formerly with Appendiceal Mass after Successful Non-operative Treatment.

Science.gov (United States)

Chang, Yi-Jung; Chao, Hsun-Chin; Chen, Chyi-Liang; Chen, Shin-Yann; Yan, Dah-Chin; Tsai, Ming-Han

2017-08-01

This study identified factors associated with the recurrence of appendicitis in children with appendiceal masses after successful nonsurgical treatment. In this retrospective study, children who were diagnosed as having appendiceal masses after undergoing conservative treatment between 2000 and 2014 were enrolled and the medical records of those who did not undergo an interval appendectomy were reviewed. The clinical features and outcomes of patients with and those without recurrent appendicitis were compared. Regression analysis was used to identify risk factors of appendicitis recurrence. Seventy patients were included and successfully discharged after receiving nonsurgical treatment for appendiceal masses. Of the patients, 35 (50.0%) developed recurrent appendicitis and 85.7% (30/35) recurrences developed within 3 months. Multivariate analyses showed that patients with a higher serum C-reactive protein (CRP) level and peritonitis more frequently developed recurrence. The appendicitis recurrence rate was significantly higher in the patients with CRP levels of ≥103 mg/L with an odds ratio of 16.9 or in those with peritonitis with an odds ratio of 4.9. Children with appendiceal masses who develop peritonitis or have CRP levels of ≥103 mg/L have a higher recurrence rate of appendicitis and should undergo an interval appendectomy. Copyright © 2017. Published by Elsevier B.V.

Risk-informed appendices G and E for section XI of the ASME Boiler and Pressure Vessel Code

International Nuclear Information System (INIS)

Carter, B; Spanner, J.; Server, W.; Gamble, R.; Bishop, B.; Palm, N.; Heinecke, C.

2011-01-01

Full text of publication follows: The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, contains two appendices (G and E) related to reactor pressure boundary integrity. Appendix G provides procedures for defining Service Level A and B pressure temperature limits for ferritic components in the reactor coolant pressure boundary. Recently, an alternative risk informed methodology has been developed for ASME Section XI, Appendix G. The alternative methodology provides simple procedures to define risk informed pressure temperature limits for Service Level A and B events, including leak testing and reactor start up and shut down for both pressurized water reactors (PWRs) and boiling water reactors (BWRs). Risk informed pressure temperature limits provide more operational flexibility, particularly for reactor pressure vessels (RPV) with relatively high irradiation levels and radiation sensitive materials. Appendix E of Section XI provides a methodology for assessing conditions when the Appendix G limits are exceeded. A similar risk informed methodology is being considered for Appendix E. The probabilistic fracture mechanics evaluations used to develop the risk informed relationships included appropriate material properties for the range of RPV materials in operating plants in the United States and operating history and system operational constraints in both BWRs and PWRs. The analysis results were used to define pressure temperature relationships that provide an acceptable level of risk, consistent with safety goals defined by the U.S. Nuclear Regulatory Commission. The alternative methodologies for Appendices G and E will provide greater operational flexibility, especially for Service Level A and B events that may adversely affect efficient and safe plant operation, such as low temperature over pressurization for PWRs and BWR leak testing. Overall, application of the risk informed appendices can result in increased plant

Interim report on task 1.2: near equilibrium processing requirements part 2 of 2 appendices to Lawrence Livermore National Laboratory for contract b345772

International Nuclear Information System (INIS)

Stewart, M W A; Vance, E R; Day, R A; Brownscombe, A

1999-01-01

Ten appendices are included: Appendix A - Copies of fabrication work instructions, consisting mostly of micrographs; Appendix B - X-ray diffraction results of the samples from task 2, which contains a list of the raw data files; Appendix C - Scanning electron micrographs and energy dispersive x-ray spectrometry results for samples of composition B1-2 - Th/U-doped baseline ceramic; Appendix D - Scanning electron micrographs and energy dispersive x-ray spectrometry results for samples of composition B1-4 - TH/U-doped baseline + impurities ceramic; Appendix E - Scanning electron micrographs and energy dispersive x-ray spectrometry results for samples of composition B1-10 - Th/U-doped zirconolite-rich ceramic; Appendix F - Scanning electron micrographs and energy dispersive x-ray spectrometry results for samples of composition B1-12 - Th/U-doped brannerite-rich ceramic; Appendix G - Scanning electron micrographs and energy dispersive x-ray spectrometry results for samples of composition B1-14 - Th/U-doped, nominally ∼ 10 % perovskite ceramic; Appendix H - Scanning eleCtron micrographs and energy dispersive x-ray spectrometry results for samples of composition B1-16 - Th/U-doped, nominally ∼ 10 % phosphate ceramic; Appendix I - Scanning electron micrographs and energy dispersive x-ray spectrometry results for the plutonium-doped samples; and Appendix J - Scanning electron micrographs and energy dispersive x-ray spectrometry results of samples sintered in 3.7 % hydrogen in argon

Adaptive B-spline volume representation of measured BRDF data for photorealistic rendering

Directory of Open Access Journals (Sweden)

Hyungjun Park

2015-01-01

Full Text Available Measured bidirectional reflectance distribution function (BRDF data have been used to represent complex interaction between lights and surface materials for photorealistic rendering. However, their massive size makes it hard to adopt them in practical rendering applications. In this paper, we propose an adaptive method for B-spline volume representation of measured BRDF data. It basically performs approximate B-spline volume lofting, which decomposes the problem into three sub-problems of multiple B-spline curve fitting along u-, v-, and w-parametric directions. Especially, it makes the efficient use of knots in the multiple B-spline curve fitting and thereby accomplishes adaptive knot placement along each parametric direction of a resulting B-spline volume. The proposed method is quite useful to realize efficient data reduction while smoothing out the noises and keeping the overall features of BRDF data well. By applying the B-spline volume models of real materials for rendering, we show that the B-spline volume models are effective in preserving the features of material appearance and are suitable for representing BRDF data.

Sonographic study about differential diagnosis between acute appendicitis and non-appendicitis in appendices of borderline diameter

International Nuclear Information System (INIS)

Chung, Hwan Hoon; Kim, Yun Hwan; Kim, Hong Won; Park, Seung Cheol; Lee, Eun Jeong; Chung, Kyoo Byung; Suh, Won Hyuck

2000-01-01

To find out the sonographic criteria which can be effectively used to differentiate acute appendicitis from non-appendicitis in patients with appendices with borderline diameter(5-8 mm). Sixteen patients diagnosed as acute appendicitis, another 16 patients diagnosed as non-appendicitis were included in this study. They complained of RLQ pain and their appendices measured 5-8 mm in diameter on sonogram. Features such as appendiceal wall thickness, presence or absence of air in appendiceal lumen, movability of tip of the appendix, compressibility of the appendix were evaluated on gray-scale sonogram and thereafter, presence or absence of color flow in the wall of the appendix was evaluated on color Doppler sonogram. Thickness of appendiceal wall is 2.98 ± 0.77 mm in acute appendicitis group and 1.73 ± 0.44 mm in non-appendicitis group (p<0.05). When 2.5 mm thickness of appendiceal wall is applied for diagnosis of acute appendicitis, sensitivity is 81.3%, specificity is 87.5% and accuracy is 84.4%. With absence of air in appendiceal lumen, sensitivity is 93.8%, specificity is 68.8% and accuracy is 81.3%. With absence of movability of appendiceal tip, sensitivity is 87.5%, specificity is 50% and accuracy is 68.8%. With absence of compressibility of the appendix, sensitivity is 100%, specificity is 31.3% and accuracy is 65.6%. With color flow in appendiceal wall, sensitivity is 81.3%, specificity is 62.5% and accuracy is 71.9%. The above mentioned criteria show statistically significant difference between acute appendicitis and non-appendicitis groups (p<0.05). When the diameter of the appendix measures 5-8 mm on sonogram, evaluation of thickness of appendiceal wall, air in appendiceal lumen, movability of tip, compressibility and color flow in the wall will be helpful to diagnose the acute appendicitis with confidence.

Safety analysis report for the use of hazardous production materials in photovoltaic applications at the National Renewable Energy Laboratory. Volume 2, Appendices

Energy Technology Data Exchange (ETDEWEB)

Crandall, R.S.; Nelson, B.P.; Moskowitz, P.D.; Fthenakis, V.M.

1992-07-01

To ensure the continued safety of SERI`s employees, the community, and the environment, NREL commissioned an internal audit of its photovoltaic operations that used hazardous production materials (HPMS). As a result of this audit, NREL management voluntarily suspended all operations using toxic and/or pyrophoric gases. This suspension affected seven laboratories and ten individual deposition systems. These activities are located in Building 16, which has a permitted occupancy of Group B, Division 2 (B-2). NREL management decided to do the following. (1) Exclude from this SAR all operations which conformed, or could easily be made to conform, to B-2 Occupancy requirements. (2) Include in this SAR all operations that could be made to conform to B-2 Occupancy requirements with special administrative and engineering controls. (3) Move all operations that could not practically be made to conform to B-2 occupancy requirements to alternate locations. In addition to the layered set of administrative and engineering controls set forth in this SAR, a semiquantitative risk analysis was performed on 30 various accident scenarios. Twelve presented only routine risks, while 18 presented low risks. Considering the demonstrated safe operating history of NREL in general and these systems specifically, the nature of the risks identified, and the layered set of administrative and engineering controls, it is clear that this facility falls within the DOE Low Hazard Class. Each operation can restart only after it has passed an Operational Readiness Review, comparing it to the requirements of this SAR, while subsequent safety inspections will ensure future compliance. This document contains the appendices to the NREL safety analysis report.

Results of combustion and emissions testing when co-firing blends of binder-enhanced densified refuse-derived fuel (b-dRDF) pellets and coal in a 440 MW{sub e} cyclone fired combustor. Volume 3: Appendices

Energy Technology Data Exchange (ETDEWEB)

Ohlsson, O.

1994-07-01

This report contains the data resulting from the co-firing of b-dRDF pellets and coal in a 440-MW{sub e} cyclone-fired combustor. These tests were conducted under a Collaborative Research and Development Agreement (CRADA). The CRADA partners included the U.S. Department of Energy (DOE), National Renewable Energy Laboratory (NREL), Argonne National Laboratory (ANL), Otter Tail Power Company, Green Isle Environmental, Inc., XL Recycling Corporation, and Marblehead Lime Company. The report is made up of three volumes. This volume contains other supporting information, along with quality assurance documentation and safety and test plans. With this multi-volume approach, readers can find information at the desired level of detail, depending on individual interest or need.

Proceedings of the 2010 AFMS Medical Research Symposium. Volume 5. Nursing Track: Abstracts and Presentations

Science.gov (United States)

2011-03-15

Management Education at a Military Hospital .................................................................. 29  Proceedings of the 2010 AFMS... education information is in Appendix C of this volume. Appendices D-L are copies of presentation slides from the plenary sessions.  Volume 2. This volume...women who have menstruation as compared to deployed women who do not have menstruation ? This study is a descriptive co relational research design. The

Public Comments on the proposed 10 CFR Part 51 rule for renewal of nuclear power plant operating licenses and supporting documents: Review of concerns and NRC staff response. Appendices

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-05-01

This volume contains several appendices. Appendix A contains the list of individuals and organizations providing comments at various stages of the rulemaking process. The names of commenters at the public meetings are listed in the order that they spoke at the meeting; those who submitted written comments are listed by docket number. Appendix B contains the summaries of comments made. Each comment summary is identified by a unique comment number. Appendix C presents the concerns and NRC staff responses. Each concern embodies one or more comments on similar or related issues. The associated comment numbers are referenced for each concern. The concerns are organized by topic areas. A three-letter identifier for the topic, followed by a number, is assigned to each concern.

Public Comments on the proposed 10 CFR Part 51 rule for renewal of nuclear power plant operating licenses and supporting documents: Review of concerns and NRC staff response. Appendices

International Nuclear Information System (INIS)

1996-05-01

This volume contains several appendices. Appendix A contains the list of individuals and organizations providing comments at various stages of the rulemaking process. The names of commenters at the public meetings are listed in the order that they spoke at the meeting; those who submitted written comments are listed by docket number. Appendix B contains the summaries of comments made. Each comment summary is identified by a unique comment number. Appendix C presents the concerns and NRC staff responses. Each concern embodies one or more comments on similar or related issues. The associated comment numbers are referenced for each concern. The concerns are organized by topic areas. A three-letter identifier for the topic, followed by a number, is assigned to each concern

Draft environmental impact statement siting, construction, and operation of New Production Reactor capacity. Volume 4, Appendices D-R

Energy Technology Data Exchange (ETDEWEB)

None

1991-04-01

This Environmental Impact Statement (EIS) assesses the potential environmental impacts, both on a broad programmatic level and on a project-specific level, concerning a proposed action to provide new tritium production capacity to meet the nation`s nuclear defense requirements well into the 21st century. A capacity equivalent to that of about a 3,000-megawatt (thermal) heavy-water reactor was assumed as a reference basis for analysis in this EIS; this is the approximate capacity of the existing production reactors at DOE`s Savannah River Site near Aiken, South Carolina. The EIS programmatic alternatives address Departmental decisions to be made on whether to build new production facilities, whether to build one or more complexes, what size production capacity to provide, and when to provide this capacity. Project-specific impacts for siting, constructing, and operating new production reactor capacity are assessed for three alternative sites: the Hanford Site near Richland, Washington; the Idaho National Engineering Laboratory near Idaho Falls, Idaho; and the Savannah River Site. For each site, the impacts of three reactor technologies (and supporting facilities) are assessed: a heavy-water reactor, a light-water reactor, and a modular high-temperature gas-cooled reactor. Impacts of the no-action alternative also are assessed. The EIS evaluates impacts related to air quality; noise levels; surface water, groundwater, and wetlands; land use; recreation; visual environment; biotic resources; historical, archaeological, and cultural resources; socioeconomics; transportation; waste management; and human health and safety. The EIS describes in detail the potential radioactive releases from new production reactors and support facilities and assesses the potential doses to workers and the general public. This volume contains 15 appendices.

Appendiceal Mucocele in an Elderly Patient: How Much Surgery

Directory of Open Access Journals (Sweden)

C. Kim-Fuchs

2011-09-01

Full Text Available Appendiceal mucoceles are rare cystic lesions with an incidence of 0.3–0.7% of all appendectomies. They are divided into four subgroups according to their histology. Even though the symptoms may vary – depending on the level of complication – from right lower quadrant pain, signs of intussusception, gastrointestinal bleeding to an acute abdomen with sepsis, most mucoceles are asymptomatic and found incidentally. We present the case of a 70-year-old patient with an incidentally found appendiceal mucocele. He was seen at the hospital for backache. The CT scan showed a vertebral fracture and a 7-cm appendiceal mass. A preoperative colonoscopy displayed several synchronous adenomas in the transverse and left colon with high-grade dysplasia. In order to lower the cancer risk of this patient, we performed a subtotal colectomy. The appendiceal mass showed no histopathological evidence of malignancy and no sign of perforation. The follow-up was therefore limited to 2 months. In this case, appendectomy would have been sufficient to treat the mucocele alone. The synchronous high-grade dysplastic adenomas were detected in the preoperative colonoscopy and determined the therapeutic approach. Generally, in the presence of positive lymph nodes, a right colectomy is the treatment of choice. In the histological presence of mucinous peritoneal carcinomatosis, cytoreductive surgery with hyperthermic intraperitoneal chemotherapy is indicated. In conclusion, mucoceles of the appendix are detected with high sensitivity by CT scan. If there is no evidence of synchronous tumor preoperatively and no peritoneal spillage, invasion or positive sentinel lymph nodes during surgery, a mucocele is adequately treated by appendectomy.

Low-grade appendiceal mucinous neoplasm mimicking an adnexal mass.

Science.gov (United States)

Cristian, Daniel Alin; Grama, Florin Andrei; Becheanu, Gabriel; Pop, Anamaria; Popa, Ileana; Şurlin, Valeriu; Stănilescu, Sorin; Bratu, Ana Magdalena; Burcoş, Traean

2015-01-01

We present a rare case of malignant epithelial neoplasm of the appendix, an uncommon disorder encountered in clinical practice, which poses a variety of diagnostic and therapeutic challenges. We report a particular case in which the appendix was abnormally located in the pelvis, mimicking an adnexal mass. Therefore, it was difficult to make the preoperative diagnosis on clinical examination, imaging studies and laboratory tests and we discovered the lesion during the diagnostic laparoscopy. No lymphadenopathy or mucinous ascites were found. The case was completely handled via the laparoscopic approach keeping the appendix intact during the operation. The frozen section, the detailed histopathology overview as well as multiple immunostaining with a complex panel of markers report diagnosed a low-grade appendiceal mucinous neoplasm (LAMN) with no invasion of the wall. No adjuvant therapy was considered needed. At a one-year follow-up oncological assessment, the patient was free of disease. In women with cystic mass in the right iliac fossa an appendiceal mucocele should be considered in the differential diagnosis. Laparoscopic appendectomy can represent an adequate operation for the appendiceal mucinous neoplasm if the histological report is clear and surgical precautionary measures are taken.

Resource Conservation and Recovery Act, Part B Permit Application

International Nuclear Information System (INIS)

1991-02-01

The Waste Isolation Pilot Plant (WIPP) project was authorized by the Department of Energy National Security and Military Applications of Nuclear Energy Authorization Act of 1980 (Public Law 96-164) as a research and development facility to demonstrate the safe, environmentally sound disposal of transuranic (TRU) radioactive wastes derived from the defense activities of the United States. The WIPP facility is owned and operated by the US Department of Energy (DOE). The TRU waste to be received at WIPP consists largely of such items as laboratory glassware and utensils, tools, scrap metal, shielding, personnel protection equipment, and solidified sludges from the treatment of waste water. Approximately 60 percent of this waste is ''mixed,'' that is, it is also contaminated with hazardous waste or hazardous waste constituents as defined by the Resource Conservation and Recovery Act (RCRA) and by the New Mexico Hazardous Waste Management Regulations (HWMR-5). Therefore, emplacement of TRU mixed waste in the WIPP repository is subject to regulation under HWMR-5 and RCRA. The permit application under the Resource Conservation and Recovery Act for WIPP is divided into five volumes. This document, Volume 2, contains Appendices B1, C1, and C2. These appendices describe the surface hydrology of the area, provide a description of the physical and chemical characteristics of wastes to be placed in WIPP, and outline a waste analysis plan which gives an overview of the total waste inventory planned for WIPP. 34 refs., 107 figs., 27 tabs

Single-incision laparoscopic cecectomy for low-grade appendiceal mucinous neoplasm after laparoscopic rectectomy

Science.gov (United States)

Fujino, Shiki; Miyoshi, Norikatsu; Noura, Shingo; Shingai, Tatsushi; Tomita, Yasuhiko; Ohue, Masayuki; Yano, Masahiko

2014-01-01

In this case report, we discuss single-incision laparoscopic cecectomy for low-grade appendiceal neoplasm after laparoscopic anterior resection for rectal cancer. The optimal surgical therapy for low-grade appendiceal neoplasm is controversial; currently, the options include appendectomy, cecectomy, right hemicolectomy, and open or laparoscopic surgery. Due to the risk of pseudomyxoma peritonei, complete resection without rupture is necessary. We have encountered 5 cases of low-grade appendiceal neoplasm and all 5 patients had no lymph node metastasis. We chose the appendectomy or cecectomy without lymph node dissection if preoperative imaging studies did not suspect malignancy. In the present case, we performed cecectomy without lymph node dissection by single-incision laparoscopic surgery (SILS), which is reported to be a reduced port surgery associated with decreased invasiveness and patient stress compared with conventional laparoscopic surgery. We are confident that SILS is a feasible alternative to traditional surgical procedures for borderline tumors, such as low-grade appendiceal neoplasms. PMID:24868331

The Energy Information Administration`s assessment of reformulated gasoline. Volume 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-09-28

This report is divided into two volumes. The first volume contains EIA`s findings and analyses on reformulated gasoline as it affects the petroleum industry. The data contained herein should assist members of the Congress, Federal, State and local governments, analysts, researchers, the media and academia to understand the RFG program and the current status of implementation. This second volume contains 10 appendices that include letter from Congressman Dingell, survey results, survey forms, and historical summary data. A glossary and a list of acronyms and abbreviations are printed in Volumes 1 and 2.

Inventory of clayey and marly formations in France and update of knowledge on the Albian in Aube. Final report. Volume 1: Report. Volume 2: Appendices

International Nuclear Information System (INIS)

2008-01-01

In the context of searching a site for a storage centre for low level and long life radioactive wastes, this voluminous document reports geological studies on soils presenting the most favourable geological and hydro-geological criteria to retain radionuclides. The locations, characteristics, variability, geology, hydro-geology, and environmental constraints of various and precisely identified clayey or marly formations of the Paris basin and of the Aquitaine basin are analysed and reported in detail. Some additional results of investigations of the Albian site in the Aube district are also reported. The appendices contain information, data and analysis concerning the different French regions

Southeast Regional Wastewater Treatment Plant Facilities Improvements Project and Geysers Effluent Pipeline Project. Draft EIR/EIS, Volume 2 of 2: Appendices

International Nuclear Information System (INIS)

1994-01-01

The Southeast Regional Wastewater Treatment Plant (SERWTP) Facilities Improvement Plan and Geysers Effluent Pipeline and Effluent Injection Project are proposed as a plan to provide expanded wastewater treatment capabilities and to dispose of the effluent by injection in The Geysers geothermal field for purposes of power production. The project is located predominantly in the County of Lake, California, and also in part of Sonoma County. The plan includes various conventional facilities improvements in wastewater treatment to a secondary level of treatment at the SWERWTP. The plan includes facilities to convey the treated effluent in a 26-mile, 24-inch inside diameter pipeline to the Southeast Geysers. The wastewater from the SERWTP would be supplemented by raw lake water diverted from nearby Clear Lake. At The Geysers, the effluent would be directed into a system of distribution lines to wells. In the geothermal reservoir, the water will be converted to steam and collected in production wells that will direct the steam to six existing power plants. This document is a summary of a combined full Environmental Impact Report (EIR) and Environmental Impact Statement (EIS). The EIR/EIS describes the environmental impacts of the various components of the project. Mitigation measures are suggested for reducing impacts to a less than significant level. This report contains appendices A and B. Appendix A contains notices of preparation/notices of intent and EIR/EIS scoping comments. Appendix B contains GeothermEx, Inc., analysis of Geothermal Reservoir Effects and Induced Seismicity

Airborne gamma-ray spectrometer and magnetometer survey, Durango D, Colorado. Final report Volume II A. Detail area

International Nuclear Information System (INIS)

1983-01-01

This volume contains geology of the Durango D detail area, radioactive mineral occurrences in Colorado, and geophysical data interpretation. Eight appendices provide: stacked profiles, geologic histograms, geochemical histograms, speed and altitude histograms, geologic statistical tables, geochemical statistical tables, magnetic and ancillary profiles, and test line data

GPU v. B and W lawsuit review and its effect on TMI-1 (Docket 50-289)

International Nuclear Information System (INIS)

1983-09-01

This report documents a review by the Nuclear Regulatory Commission (NRC) staff of the General Public Utilities Corporation, et al. v. the Babcock and Wilcox Company, et al. (GPU v. B and W) lawsuit record to assess whether any of the staff's previous conclusions or their principal bases presented at the Three Mile Island Unit 1 (TMI-1) restart hearing, supporting restart of TMI-1, should be amended in light of the information contained in the lawsuit record. Details of the lawsuit record are provided in the appendices contained in Volume II of this report

GPU v. B and W lawsuit review and its effect on TMI-1 (Docket 50-289)

Energy Technology Data Exchange (ETDEWEB)

1983-09-01

This report documents a review by the Nuclear Regulatory Commission (NRC) staff of the General Public Utilities Corporation, et al. v. the Babcock and Wilcox Company, et al. (GPU v. B and W) lawsuit record to assess whether any of the staff's previous conclusions or their principal bases presented at the Three Mile Island Unit 1 (TMI-1) restart hearing, supporting restart of TMI-1, should be amended in light of the information contained in the lawsuit record. Details of the lawsuit record are provided in the appendices contained in Volume II of this report.

Technical support document: Energy efficiency standards for consumer products: Room air conditioners, water heaters, direct heating equipment, mobile home furnaces, kitchen ranges and ovens, pool heaters, fluorescent lamp ballasts and television sets. Volume 2, Fluorescent lamp ballasts, television sets, room air conditioners, and kitchen ranges and ovens

Energy Technology Data Exchange (ETDEWEB)

1993-11-01

This document is divided into ``volumes`` B through E, dealing with individual classes of consumer products. Chapters in each present engineering analysis, base case forecasts, projected national impacts of standards, life-cycle costs and payback periods, impacts on manufacturers, impacts of standards on electric utilities, and environmental effects. Supporting appendices are included.

B Plant Complex pollution prevention plan. Revision 1

International Nuclear Information System (INIS)

Beam, T.G.

1994-01-01

The US Department of Energy (DOE) has directed Westinghouse Hanford Company (WHC) to develop an effective strategy to minimize the generation of hazardous, radioactive, and mixed wastes at Hanford in compliance with state and federal regulations. WHC has formalized a pollution prevention program composed of management policies, management requirements and procedures. This plan addresses pollution prevention for B Plant Complex. A pollution prevention team is in place and has been assigned responsibility for implementing the plan. This plan includes actions and goals for reducing volume and toxicity of waste generated, as well as a basis for evaluation of progress. Descriptions of waste streams, current specific goals, general pollution prevention methods, and specific accomplishments are in the appendices of this plan

Plan for studies of subsurface radionuclide migration at the Radioactive Waste Management Complex of the Idaho National Engineering Laboratory. Volume 1 of 2

International Nuclear Information System (INIS)

1983-11-01

This document describes planned studies of subsurface radionuclide migration at the Radioactive Waste Management Complex of the Idaho National Engineering Laboratory. A plan is provided for each proposed study. The rational for arriving at the list of proposed studies is also presented. This document consists of two volumes. In the first volume, Sections 1 through 5 contain the introduction, the objectives of the proposed studies, and background information. The discussion is not comprehensive in detail; documents are referenced that discuss the background material in greater detail. Sections 6 through 9 identify and select the group of studies to be performed and discuss the peer review process. The second volume contains Appendices A and B, which present the assignment of responsibilities and the detailed plans, schedules, and costs for the proposed program

The development of coal-based technologies for Department of Defense facilities. Volume 2, Appendices. Semiannual technical progress report, September 28, 1994--March 27, 1995

International Nuclear Information System (INIS)

Miller, B.G.; Bartley, D.A.; Hatcher, P.

1996-01-01

This semiannual progress report contains the following appendices: description of the 1,000 lb steam/h watertube research boiler; the Pennsylvania CGE model; Phase II, subtask 3.9 coal market analysis; the CGE model; and sector definition

Low-Grade Appendiceal Mucinous Neoplasm Involving the Endometrium and Presenting with Mucinous Vaginal Discharge.

Science.gov (United States)

Vavinskaya, Vera; Baumgartner, Joel M; Ko, Albert; Saenz, Cheryl C; Valasek, Mark A

2016-01-01

Primary appendiceal mucinous lesions are uncommon and represent a spectrum from nonneoplastic mucous retention cysts to invasive adenocarcinoma. Low-grade appendiceal mucinous neoplasms (LAMNs) represent an intermediate category on this spectrum and can be classified according to whether or not they are confined to the appendix. Although LAMNs are frequently confined to the appendix, they can also spread to the peritoneum and clinically progress as pseudomyxoma peritonei (i.e., mucinous ascites). Thus, the appropriate classification of appendiceal primary neoplasia is essential for prognosis and influences clinical management. In addition, the precise classification, management, and clinical outcome of patients with disseminated peritoneal disease remain controversial. Here, we report an unusual case of LAMN with pseudomyxoma peritonei that initially presented with mucinous and bloody vaginal discharge. Pathological evaluation revealed low-grade appendiceal mucinous neoplasm with secondary involvement of the peritoneum, ovaries, and endometrial surface. Therefore, LAMN should be considered in the differential diagnosis of mucinous vaginal discharge.

Low-Grade Appendiceal Mucinous Neoplasm Involving the Endometrium and Presenting with Mucinous Vaginal Discharge

Directory of Open Access Journals (Sweden)

Vera Vavinskaya

2016-01-01

Full Text Available Primary appendiceal mucinous lesions are uncommon and represent a spectrum from nonneoplastic mucous retention cysts to invasive adenocarcinoma. Low-grade appendiceal mucinous neoplasms (LAMNs represent an intermediate category on this spectrum and can be classified according to whether or not they are confined to the appendix. Although LAMNs are frequently confined to the appendix, they can also spread to the peritoneum and clinically progress as pseudomyxoma peritonei (i.e., mucinous ascites. Thus, the appropriate classification of appendiceal primary neoplasia is essential for prognosis and influences clinical management. In addition, the precise classification, management, and clinical outcome of patients with disseminated peritoneal disease remain controversial. Here, we report an unusual case of LAMN with pseudomyxoma peritonei that initially presented with mucinous and bloody vaginal discharge. Pathological evaluation revealed low-grade appendiceal mucinous neoplasm with secondary involvement of the peritoneum, ovaries, and endometrial surface. Therefore, LAMN should be considered in the differential diagnosis of mucinous vaginal discharge.

Robust, accurate, and non-contacting vibration measurement systems: Supplemental appendices presenting comparison measurements of the robust laser interferometer and typical accelerometer systems. Volume 2

International Nuclear Information System (INIS)

Goodenow, T.C.; Shipman, R.L.; Holland, H.M.

1995-06-01

Epoch Engineering, Incorporated (EEI) has completed a series of vibration measurements comparing their newly-developed Robust Laser Interferometer (RLI) with accelerometer-based instrumentation systems. EEI has successfully demonstrated, on several pieces of commonplace machinery, that non-contact, line-of-sight measurements are practical and yield results equal to or, in some cases, better than customary field implementations of accelerometers. The demonstration included analysis and comparison of such phenomena as nonlinearity, transverse sensitivity, harmonics, and signal-to-noise ratio. Fast Fourier Transformations were performed on the accelerometer and the laser system outputs to provide a comparison basis. The RLI was demonstrated, within the limits o the task, to be a viable, line-of-sight, non-contact alternative to accelerometer systems. Several different kinds of machinery were instrumented and. compared, including a small pump, a gear-driven cement mixer, a rotor kit, and two small fans. Known machinery vibration sources were verified and RLI system output file formats were verified to be compatible with commercial computer programs used for vibration monitoring and trend analysis. The RLI was also observed to be less subject to electromagnetic interference (EMI) and more capable at very low frequencies. This document, Volume 2, provides the appendices to this report

Airborne gamma-ray spectrometer and magnetometer survey: Indian Wells, Texas. Final report. Detail area, Volume IIB

International Nuclear Information System (INIS)

Volume IIB contains appendices for: flight line maps; geology maps; explanation of geologic legend; flight line/geology maps; radiometric contour maps; magnetic contour maps; geochemical factor analysis maps

Systems for Arctic Spill Response. Volume II. Appendices.

Science.gov (United States)

1978-03-01

Microbial Degradation of Oil Pollutants, Center for Wetland Resources. Pub. No. LSU-SG-73-O1 , 1973, p. 153. 6. Atlas , R. and E. Schofield , •U petroleum... Atlas , R. and R. Bartha , “Degradation and Mineralization of Petroleum in in Sea Water: Limitation by Nitrogen and Phosphorus ,” Biotechnology, B...iNFORMATION SOURCES USED IN THE PREPARATION OF MAPS OF ECOLOGICAL SENSITIVITY A- i APPENDIX B - APPLICATION OF EXISTING AND PLANNED OIL SPILL

Draft environmental impact statement for the siting, construction, and operation of New Production Reactor capacity. Volume 3, Sections 7-12, Appendices A-C

Energy Technology Data Exchange (ETDEWEB)

1991-04-01

This Environmental Impact Statement (EIS) assesses the potential environmental impacts, both on a broad programmatic level and on a project-specific level, concerning a proposed action to provide new tritium production capacity to meet the nation`s nuclear defense requirements well into the 21st century. A capacity equivalent to that of about a 3,000-megawatt (thermal) heavy-water reactor was assumed as a reference basis for analysis in this EIS; this is the approximate capacity of the existing production reactors at DOE`s Savannah River Site near Aiken, South Carolina. The EIS programmatic alternatives address Departmental decisions to be made on whether to build new production facilities, whether to build one or more complexes, what size production capacity to provide, and when to provide this capacity. Project-specific impacts for siting, constructing, and operating new production reactor capacity are assessed for three alternative sites: the Hanford Site near Richland, Washington; the Idaho National Engineering Laboratory near Idaho Falls, Idaho; and the Savannah River Site. For each site, the impacts of three reactor technologies (and supporting facilities) are assessed: a heavy-water reactor, a light-water reactor, and a modular high-temperature gas-cooled reactor. Impacts of the no-action alternative also are assessed. The EIS evaluates impacts related to air quality; noise levels; surface water, groundwater, and wetlands; land use; recreation; visual environment; biotic resources; historical, archaeological, and cultural resources; socioeconomics; transportation; waste management; and human health and safety. The EIS describes in detail the potential radioactive releases from new production reactors and support facilities and assesses the potential doses to workers and the general public. This volume contains references; a list of preparers and recipients; acronyms, abbreviations, and units of measure; a glossary; an index and three appendices.

Blanket comparison and selection study. Volume II

International Nuclear Information System (INIS)

1983-10-01

This volume contains extensive data for the following chapters: (1) solid breeder tritium recovery, (2) solid breeder blanket designs, (3) alternate blanket concept screening, and (4) safety analysis. The following appendices are also included: (1) blanket design guidelines, (2) power conversion systems, (3) helium-cooled, vanadium alloy structure blanket design, (4) high wall loading study, and (5) molten salt safety studies

Tokamak experimental power reactor conceptual design. Volume II

International Nuclear Information System (INIS)

1976-08-01

Volume II contains the following appendices: (1) summary of EPR design parameters, (2) impurity control, (3) plasma computational models, (4) structural support system, (5) materials considerations for the primary energy conversion system, (6) magnetics, (7) neutronics penetration analysis, (8) first wall stress analysis, (9) enrichment of isotopes of hydrogen by cryogenic distillation, and (10) noncircular plasma considerations

Appendiceal-sigmoid fistula presenting in a man with ulcerative colitis: a case report

Directory of Open Access Journals (Sweden)

Minutolo Vincenzo

2010-07-01

Full Text Available Abstract Introduction Ulcerative colitis is a chronic disease characterized by diffuse mucosal inflammation limited to the colon. It mostly affects young adults, yet a large number of middle-aged and older patients with ulcerative colitis have also been reported. Case presentation A 58-year-old Caucasian man presented to our hospital in August 2006 with continuous and diffuse abdominal pain, meteorism, fever and bloody diarrhea. He had a two-year history of ulcerative colitis. Our patient was treated with intravenous medical therapy. As his condition worsened, he underwent surgery. An explorative laparotomy revealed that the entire colon was distended and pus was found around an appendiceal-sigmoid fistula. Conclusions Therapy for ulcerative colitis is a rapidly evolving field, with many new biological agents under investigation that are likely to change therapeutic strategies radically in the next decade. Indications for surgery are intractability (49%, stricture, dysplasia, toxic colitis, hemorrhage and perforation. To the best of our knowledge, this is the first case of an appendiceal-sigmoid fistula in a patient affected by ulcerative colitis reported in the literature. Fistulae between the appendix and the sigmoid tract are rarely reported in cases of diverticular disease and appendicitis.

Sizewell 'B' power station public enquiry: CEGB statement of case. 2 vols and appendices A-G, H, J, L, M

International Nuclear Information System (INIS)

1982-04-01

This statement of case summarises the case which the CEGB intends to put to the public enquiry into building a PWR reactor at Sizewell. The two volumes are divided into chapters covering an introduction, the Electricity Supply Industry and the CEGB, nuclear development on the CEGB system, new generating plant, the need for Sizewell B and various aspects of safety and design. (U.K.)

Hanford spent nuclear fuel project recommended path forward, volume III: Alternatives and path forward evaluation supporting documentation

International Nuclear Information System (INIS)

Fulton, J.C.

1994-10-01

Volume I of the Hanford Spent Nuclear Fuel Project - Recommended Path Forward constitutes an aggressive series of projects to construct and operate systems and facilities to safely retrieve, package, transport, process, and store K Basins fuel and sludge. Volume II provided a comparative evaluation of four Alternatives for the Path Forward and an evaluation for the Recommended Path Forward. Although Volume II contained extensive appendices, six supporting documents have been compiled in Volume III to provide additional background for Volume II

Multiple caeco-appendiceal fistulas and diverticulosis: a newly defined congenital anomaly of the appendix-report of the first case.

Science.gov (United States)

Yucel, Ahmet Fikret; Pergel, Ahmet; Kocakusak, Ahmet; Aydin, Ibrahim; Bagci, Pelin; Sahin, Dursun Ali

2011-11-01

Congenital anomalies of the appendix are extremely rare. They are usually found incidentally during operations other than appendectomies. Congenital appendix diverticula are even less frequent. Congenital caeco-appendiceal fistulae have not been reported until today. Herein, we present real diverticula of the appendix with multiple caeco-appendiceal fistulae which, to our knowledge, is the first in the literature.

Barnwell Nuclear Fuels Plant applicability study. Volume III. Appendices

International Nuclear Information System (INIS)

1978-03-01

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

Canton hydroelectric project: feasibility study. Final report, appendices

Energy Technology Data Exchange (ETDEWEB)

1979-05-01

These appendices contain legal, environmental, regulatory, technical and economic information used in evaluating the feasibility of redeveloping the hydroelectric power generating facilities at the Upper and Lower Dams of the Farmington River at Collinsville, CT. (LCL)

Immobilization of defense high-level waste: an assessment of technological strategies and potential regulatory goals. Volume II

International Nuclear Information System (INIS)

1979-06-01

This volume contains the following appendices: selected immobilization processes, directory of selected European organizations involved in HLW management, U.S. high-level waste inventories, and selected European HLW program

Systems study of the feasibility of high-level nuclear waste fractionation for thermal stress control in a geologic repository: appendices

International Nuclear Information System (INIS)

McKee, R.W.; Elder, H.K.; McCallum, R.F.; Silviera, D.J.; Swanson, J.L.; Wiles, L.E.

1983-06-01

This study assesses the benefits and costs of fractionating the cesium and strontium (Cs/Sr) components in commercial high-level waste (HLW) to a separate waste stream for the purpose of reducing geologic-repository thermal stresses in the region of the HLW. The major conclusion is that the Cs/Sr fractionation concept offers the prospect of a substantial total system cost advantage for HLW disposal if reduced HLW package temperatures in a basalt repository are desired. However there is no cost advantage if currently designated maximum design temperatures are acceptable. Aging the HLW for 50 to 100 years can accomplish similar results at equivalent or lower costs. Volume II contains appendices for: (1) thermal analysis supplement; (2) fractionation process experimental results supplement; (3) cost analysis supplement; and (4) radiological risk analysis supplement

NASAwide electronic publishing system-prototype STI electronic document distribution: Stage-4 evaluation report. Part 2; Appendices

Science.gov (United States)

Tuey, Richard C.; Collins, Mary; Caswell, Pamela; Haynes, Bob; Nelson, Michael L.; Holm, Jeanne; Buquo, Lynn; Tingle, Annette; Cooper, Bill; Stiltner, Roy

1996-01-01

This evaluation report contains an introduction, seven chapters, and five appendices. The Introduction describes the purpose, conceptual framework, functional description, and technical report server of the Scientific and Technical Information (STI) Electronic Document Distribution (EDD) project. Chapter 1 documents the results of the prototype STI EDD in actual operation. Chapter 2 documents each NASA center's post processing publication processes. Chapter 3 documents each center's STI software, hardware. and communications configurations. Chapter 7 documents STI EDD policy, practices, and procedures. The appendices consist of (A) the STI EDD Project Plan, (B) Team members, (C) Phasing Schedules, (D) Accessing On-line Reports, and (E) Creating an HTML File and Setting Up an xTRS. In summary, Stage 4 of the NASAwide Electronic Publishing System is the final phase of its implementation through the prototyping and gradual integration of each NASA center's electronic printing systems, desk top publishing systems, and technical report servers, to be able to provide to NASA's engineers, researchers, scientists, and external users, the widest practicable and appropriate dissemination of information concerning its activities and the result thereof to their work stations.

Preliminary feasibility study on storage of radioactive wastes in Columbia River basalts. Volume II

Energy Technology Data Exchange (ETDEWEB)

,

1976-11-01

Volume II comprises four appendices: analytical data and sample locations for basalt flow type localities; Analytical data and sample locations for measured field sections in Yakima basalts; core hole lithology and analytical data; and geophysical logs. (LK)

The relationship of VOI threshold, volume and B/S on DISA images

International Nuclear Information System (INIS)

Song Liejing; Wang Mingming; Si Hongwei; Li Fei

2011-01-01

Objective: To explore the relationship of VOI threshold, Volume and B/S on DISA phantom images. Methods: Ten hollow spheres were placed in cylinder phantom. According to the B/S of 1 : 7, 1 : 5 and 1 : 4, 99m TcO 4- and 18 F-FDG was filled into the container and spheres simultaneously and separately. Images were acquired by DISA and SIDA protocol. Volume of interest (VOI) for each sphere was analyzed by threshold method and to fit expression individually for validating of the relationship. Results: The equation for the estimation of optimal threshold was as following Tm = d + c × Bm/(e + f × Vm) + b/Vm. In majority of data, the calculated threshold was in the 1% interval that optimal thresholds were really in. Those who were not in were at the lower or upper intervals. Conclusions: Both DISA and SIDA images, based o the relationship of VOI thresh- old. Volume and B/S and real volume, this method could accurately calculate optimal threshold with an error less than 1% for spheres whose volumes ranged from 3.3 to 30.8 ml. (authors)

Immunohistochemistry - Microarray Analysis of Patients with Peritoneal Metastases of Appendiceal or Colorectal Origin

Directory of Open Access Journals (Sweden)

Danielle E Green

2015-01-01

Full Text Available BackgroundThe value of immunohistochemistry (IHC-microarray analysis of pathological specimens in the management of patients is controversial although preliminary data suggests potential benefit. We describe the characteristics of patients undergoing a commercially available IHC-microarray method in patients with peritoneal metastases (PM and the feasibility of this technique in this population.MethodsWe retrospectively analyzed consecutive patients with pathologically confirmed PM from appendiceal or colorectal primary who underwent Caris Molecular IntelligenceTM testing. IHC, microarray, FISH and mutational analysis were included and stratified by PCI score, histology and treatment characteristics. Statistical analysis was performed using non-parametric tests.ResultsOur study included 5 patients with appendiceal and 11 with colorectal PM. The median age of patients was 51 (IQR 39-65 years, with 11(68% female. The median PCI score of the patients was 17(IQR 10-25. Hyperthermic intra-peritoneal chemoperfusion (HIPEC was performed in 4 (80% patients with appendiceal primary tumors and 4 (36% with colorectal primary. KRAS mutations were encountered in 40% of appendiceal vs. 30% colorectal tumors, while BRAF mutations were seen in 40% of colorectal PM and none of the patients with appendiceal PM (p=0.06. IHC biomarker expression was not significantly different between the two primaries. Sufficient tumor for microarray analysis was found in 44% (n=7 patients, which was not associated with previous use of chemotherapy (p>0.20 for 5-FU/LV, Irinotecan and Oxaliplatin.ConclusionsIn a small sample of patients with peritoneal metastases, the feasibility and results of IHC-microarray staining based on a commercially available test is reported. The apparent high incidence of the BRAF mutation in patients with PM may potentially offer opportunities for novel therapeutics and suggest that IHC-microarray is a method that can be used in this population.

Draft Hanford Remedial Action Environmental Impact Statement and Comprehensive Land Use Plan. Volume 3 of 4

International Nuclear Information System (INIS)

1996-08-01

This volume of the Environmental Impact Statement contains ten appendices. These appendices contain the following: the ecological risk assessment methodology and calculations; the strategy for remediation of contaminated ground water; a description of the reference barrier and potential quarry sites that could be used to supply materials for barriers; the methodology for estimating socio-economic impacts; the methodology for evaluation of air quality impacts; an assessment of costs and physical impacts; the calculation of estimated industrial health and safety occupational losses; a floodplains and wetlands impact assessment; information about Hanford waste sites, and US EPA guidance on using land-use decisions in remediation

Low-Grade Appendiceal Mucinous Neoplasm Involving the Endometrium and Presenting with Mucinous Vaginal Discharge

OpenAIRE

Vavinskaya, Vera; Baumgartner, Joel M.; Ko, Albert; Saenz, Cheryl C.; Valasek, Mark A.

2016-01-01

Primary appendiceal mucinous lesions are uncommon and represent a spectrum from nonneoplastic mucous retention cysts to invasive adenocarcinoma. Low-grade appendiceal mucinous neoplasms (LAMNs) represent an intermediate category on this spectrum and can be classified according to whether or not they are confined to the appendix. Although LAMNs are frequently confined to the appendix, they can also spread to the peritoneum and clinically progress as pseudomyxoma peritonei (i.e., mucinous ascit...

Appendiceal diverticulum associated with chronic appendicitis

OpenAIRE

Zubieta-O’Farrill, Gregorio; Guerra-Mora, José Raúl; Gudiño-Chávez, Andrés; Gonzalez-Alvarado, Carlos; Cornejo-López, Gilberto Bernabe; Villanueva-Sáenz, Eduardo

2014-01-01

INTRODUCTION: Appendiceal diverticulosis is a rare entity, with a global incidence between 0.004% and 2.1% of all appendectomies. It has been related with an elevated risk of perforation in comparison to acute appendicitis, as well as an increased risk for synchronic appendicular cancer in 48% of the cases, and colonic cancer in 43%. The incidence of chronic appendicitis has been reported in 1.5% of all appendicitis cases. PRESENTATION OF CASE: We present a 73-year-old female, with no rele...

Guidance and Control Software Project Data - Volume 2: Development Documents

Science.gov (United States)

Hayhurst, Kelly J. (Editor)

2008-01-01

The Guidance and Control Software (GCS) project was the last in a series of software reliability studies conducted at Langley Research Center between 1977 and 1994. The technical results of the GCS project were recorded after the experiment was completed. Some of the support documentation produced as part of the experiment, however, is serving an unexpected role far beyond its original project context. Some of the software used as part of the GCS project was developed to conform to the RTCA/DO-178B software standard, "Software Considerations in Airborne Systems and Equipment Certification," used in the civil aviation industry. That standard requires extensive documentation throughout the software development life cycle, including plans, software requirements, design and source code, verification cases and results, and configuration management and quality control data. The project documentation that includes this information is open for public scrutiny without the legal or safety implications associated with comparable data from an avionics manufacturer. This public availability has afforded an opportunity to use the GCS project documents for DO-178B training. This report provides a brief overview of the GCS project, describes the 4-volume set of documents and the role they are playing in training, and includes the development documents from the GCS project. Volume 2 contains three appendices: A. Guidance and Control Software Development Specification; B. Design Description for the Pluto Implementation of the Guidance and Control Software; and C. Source Code for the Pluto Implementation of the Guidance and Control Software

US Department of Energy interim mixed waste inventory report: Waste streams, treatment capacities and technologies: Volume 6, Appendices

International Nuclear Information System (INIS)

1993-04-01

This volume contains Appendix A--Federal Facility Compliance Act of 1992, Appendix B--Technology Development, and Appendix C--Other Materials. Appendix B supplies details concerning the technology development activities supported by DOE in the area of mixed waste management. Two parts of this appendix are important. The more important of the two is the collection of technology development summaries. There are 267 summaries collected from several sources, which are described. The second important part consists of tables which group technologies by one several attributes such as target site and cross-complex applicability as well as relationship to Resource Conservation Recovery Act Best Demonstrated Available Technologies (RCRA BDATs)

Gulf of Mexico Sales 139 and 141: Central and western planning areas. Final environmental impact statement. Volume 2: Sections 4.D. through 9. Final report

International Nuclear Information System (INIS)

1991-10-01

The report is Volume II of two volumes. The EIS is a description of the environmental aspects and impacts of oil and gas activities resulting from these lease sales or the States bordering the Gulf of Mexico. The volume continues with Environmental Consequences; Consultation and Coordination; Bibliography and Special References; Preparers; Glossary; and the Appendices

An evaluation of known remaining oil resources in the United States: Appendix. Volume 10

Energy Technology Data Exchange (ETDEWEB)

NONE

1993-11-01

Volume ten contains the following appendices: overview of improved oil recovery methods which covers enhanced oil recovery methods and advanced secondary recovery methods; the benefits of improved oil recovery, selected data for the analyzed states; and list of TORIS fields and reservoirs.

Resolution of the Task A-11 reactor-vessel materials-toughness safety issue. Appendices C-K

International Nuclear Information System (INIS)

1982-10-01

The central problem in the unresolved safety issue A-11, Reactor Vessel Materials Toughness, was to provide guidance in performing analyses required by 10 CFR Part 50, Appendix G, Section V.C. for reactor pressure vessels (RPVs) which fail to meet the toughness requirement during service life as a result of neutron radiation embrittlement. Although the methods of linear-elastic fracture mechanics (LEFM) were adequate for low-temperature RPV problems, they were inapplicable under operating conditions because vessel steels, even those which exhibit less than 50 ft-lb of C/sub v/ energy, were relatively tough at temperatures where the impact energy reached its upper shelf values. A technical team of recognized experts was organized to assist the NRC staff in addressing the problem. Using the foundation of the tearing modulus concept, which had been developed under earlier NRC sponsorship, relationships were obtained which provided approximate solutions to the problem of RPV fracture with assumed beltline region flaws. The first paper of this report is a summary of the problem, the solutions, and the results of verification analyses. The details are provided in a series of appendices in Volumes I and II

9433 Design Pointing Anomaly. Volume II. Appendices

Science.gov (United States)

1976-01-30

A X/A4 r42/ jC Pa4 ,oo/ £’dr/O N/ IV /pal B-87 ONb 1JP4C& PA64K W ’CIO4JL;O UEC- CA6 .rOSIN-A ~ ~VO 45 F ORT NO. PAGE CHECKED MODEL 7-&,td1V Z-/aZo or...BPS 13.12 Lubritation Treatment (Proprietary) BPS 16.1S Stainless Steel Passivation BPS 16.32 Primer Zinc-Chromate BPS 19.01 Packaging and Sealing...e at-orfr7ed mixork. 7--7-V-5O64ai �-SI-30?O, R~~MRGMLRCR COPY 0- /Z𔄁,r REWORK TREATMENT TRW BEARINGS P/N 32708-1 & -3 inse all bearing

Industrial Sector Technology Use Model (ISTUM): industrial energy use in the United States, 1974-2000. Volume 3. Appendix on service and fuel demands. Final report

Energy Technology Data Exchange (ETDEWEB)

1979-10-01

This book is the third volume of the ISTUM report. The first volume of the report describes the primary model logic and the model's data inputs. The second volume lists and evaluates the results of one model run. This and the fourth volume give supplementary information in two sets of model data - the energy consumption base and technology descriptions. Chapter III of Vol. I, Book 1 describes the ISTUM demand base and explains how that demand base was developed. This volume serves as a set of appendices to that chapter. The chapter on demands in Vol. I describes the assumptions and methodology used in constructing the ISTUM demand base; this volume simply lists tables of data from that demand base. This book divides the demand tables into two appendices. Appendix III-1 contains detailed tables on ISTUM fuel-consumption estimates, service-demand forecasts, and size and load-factor distributions. Appendix III-2 contains tables detailing ISTUM allocations of each industry's fuel consumption to service sectors. The tables show how the ECDB was used to develop the ISTUM demand base.

Usefulness of measurement of the outer appendiceal diameter on abdominal computer tomography in the diagnosis of acute appendicitis

International Nuclear Information System (INIS)

Chisuwa, Hisanao; Tauchi, Katsunori; Mori, Shusuke; Kishimoto, Hirofumi; Koike, Hideo; Higuchi, Kayoko; Ohmori, Toshihiro; Miyazawa, Masahisa

2008-01-01

The purpose of this study was to evaluate the accuracy of our computer tomography (CT)-based protocol and the usefulness of measurement of the outer appendiceal diameter on CT in the diagnosis of acute appendicitis. Two-hundred thirty-nine consecutive patients with clinical diagnoses of acute appendicitis during the period from January 2002 to Jun 2004 were evaluated. The CT criterion of acute appendicitis was the outer appendiceal diameter of 6 mm or more, and/or other associated inflammatory changes. The histological criterion of acute appendicitis was the presentation of polymorphic granulocytes throughout the appendiceal wall. Of 239 patients, 235 underwent CT examination. Among 222 patients with appendectomy, 205 had histologically proven acute appendicitis. Of 200 patients who had the outer appendiceal diameter of 6 mm or more on CT, 193 had histologically proven acute appendicitis. The positive predictive value for diagnosing acute appendicitis was 92.3% in the surgery group, and 96.5% in the group that the outer appendiceal diameter was 6 mm or more on CT. The recurrence rate of acute appendicitis diagnosed by CT following conservative therapy was 35.3%, and was high (50%) in the group with the appendiceal diameter of at least 10 mm. CT is useful in the diagnosis for acute appendicitis. (author)

SMACS - a system of computer programs for probabilistic seismic analysis of structures and subsystems. Volume II. Example problem

International Nuclear Information System (INIS)

Maslenikov, O.R.; Johnson, J.J.; Tiong, L.W.; Mraz, M.J.; Bumpus, S.; Gerhard, M.A.

1985-03-01

In this volume of the SMACS User's Manual an example problem is presented to demonstrate the type of problem that SMACS is capable of solving and to familiarize the user with format of the various data files involved. This volume is organized into thirteen appendices which follow a short description of the problem. Each appendix contains listings of the input and output files associated with each computer run that was necessary to solve the problem. In cases where one SMACS program uses data generated by another SMACS program, the data file is shown in the appendix for the programs which generated it

Hanford Site background: Part 1, Soil background for nonradioactive analytes. Revision 1, Volume 2

Energy Technology Data Exchange (ETDEWEB)

1993-04-01

Volume two contains the following appendices: Description of soil sampling sites; sampling narrative; raw data soil background; background data analysis; sitewide background soil sampling plan; and use of soil background data for the detection of contamination at waste management unit on the Hanford Site.

Jabiluka project - Draft Environmental Impact Statement. Appendices

International Nuclear Information System (INIS)

1996-01-01

The Appendices provide various technical data in support of studies presented in the Main Report, including the guidelines for an EIS at Jabiluka, environmental requirements, waste management plan, water management system criteria, water quality data, transport licensing and security procedures, rehabilitation plus specialist studies into ore characteristics, noise issues and haulage risk assessment. Copyright (1996) Energy Resources of Australia Limited

Influence of 5% dextrose volume on amphotericin B deoxycholate preparation.

Science.gov (United States)

Sun, Pingping; Chen, Jie; Zhang, Zhihao; Gao, Xiang; Chen, Pan; Li, Shuxia

2016-04-01

Preparation of amphotericin B deoxycholate (AmB-d) in different volumes of 5% dextrose (D5W) was studied to investigate a interesting phenomenon that AmB-d was easy to bring pipe blockage when diluted in 500 ml but not in 50 ml. AmB-d (25 mg/vial) in 50 ml, 250 ml or 500 ml D5W was prepared. Fluids were collected before and after infusion, then were assayed by validated high-performance liquid chromatography (HPLC) method. Light obscuration assay was used to detect the particles in transfusions. pH values of different volumes of D5W were all about 3.7, which was lower than the requirement of AmB-d package insert (pH > 4.2). The number of insoluble particles >10 μm/25 μm in 25 mg/500 ml infusions exceeded China Pharmacopoeia limit. Filters in 25 mg/500 ml infusion set were full of AmB-d after dripping slowly for 6 h, and 331.3 ml solution was left in the bottles and only 11.3% of AmB-d could flow out. Whereas the AmB-d infusion consists of 25 mg/50 ml, 25 mg/250 ml and 50 mg/500 ml could meet with China Pharmacopoeia standards, and they flowed out easily and completely. In practice, 25 mg/250 ml and 50 mg/500 ml would be more suitable for clinical use, rather than 25 mg/500 ml. We provided a convenient method for AmB-d preparation. © 2016 Royal Pharmaceutical Society, Journal of Pharmacy and Pharmacology.

Waste-Management Education and Research Consortium (WERC) annual progress report, 1992--1993. Appendices

Energy Technology Data Exchange (ETDEWEB)

1993-02-15

This report contains the following appendices: Appendix A - Requirements for Undergraduate Level; Appendix B - Requirements for Graduate Level; Appendix C - Graduate Degree In Environmental Engineeringat New Mexico State University; Appendix D - Non-degree Certificate program; Appendix E - Curriculum for Associate Degree Program in Radioactive & Hazardous Waste Materials; Appendix F - Curriculum for NCC Program in Earth & Environmental Sciences; Appendix G - Brochure of 1992 Teleconference Series; Appendix H - Sites for Hazardous/Radioactive Waste Management Series; Appendix I - WERC Interactive Television Courses; Appendix J - WERC Research Seminar Series Brochures; Appendix K - Summary of Technology Development of the Third Year; Appendix L - List of Major Publications Resulting From WERC; Appendix M - Types of Equipment at WERC Laboratories; and Appendix N - WERC Newsletter Examples.

Evaluation, engineering and development of advanced cyclone processes. Final separating media evaluation and test report (FSMER). Appendices

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-05-01

This report consists of appendices pertaining to the separating media evaluation (calcium nitrate solution) and testing for an advanced cyclone process. Appendices include: materials safety data, aqueous medium regeneration, pH control strategy, and other notes and data.

Resource Conservation and Recovery Act, Part B Permit Application [for the Waste Isolation Pilot Plant (WIPP)]. Volume 2, Chapter C, Appendix C1--Chapter C, Appendix C3 (beginning), Revision 3

Energy Technology Data Exchange (ETDEWEB)

1993-03-01

This volume contains appendices for the following: Rocky Flats Plant and Idaho National Engineering Laboratory waste process information; TRUPACT-II content codes (TRUCON); TRUPACT-II chemical list; chemical compatibility analysis for Rocky Flats Plant waste forms; chemical compatibility analysis for waste forms across all sites; TRU mixed waste characterization database; hazardous constituents of Rocky Flats Transuranic waste; summary of waste components in TRU waste sampling program at INEL; TRU waste sampling program; and waste analysis data.

Life sciences payload definition and integration study. Volume 3: Appendices

Science.gov (United States)

1972-01-01

Detail design information concerning payloads for biomedical research projects conducted during space missions is presented. Subjects discussed are: (1) equipment modules and equipment item lists, (2) weight and volume breakdown by payload and equipment units, (3) longitudinal floor arrangement configuration, and (4) nonbaseline second generation layouts.

Life prediction methodology for ceramic components of advanced vehicular heat engines: Volume 3, Appendices 3, 4, 5, 6, and 7. Final report

Energy Technology Data Exchange (ETDEWEB)

Khandelwal, P.K.; Provenzano, N.J.; Schneider, W.E. [Allison Engine Co., Indianapolis, IN (United States)

1996-02-01

The appendices contain: dynamic fatigue testing of MOR specimens in air at Allison from 1000 to 1400 C; dynamic fatigue testing of MOR specimens in air and Ar at ORNL from 1000-1400 C; dynamic fatigue testing of button-head tensile specimens in air at Southern Research Institute; tensile creep curves for dogbone specimens tested at the National Institute of Science and Technology; and oxidation behavior of PY-6 Si nitride between 1000-1400 C in air.

Impacts of Outer Continental Shelf (OCS) development on recreation and tourism. Volume 4. User's manual

Energy Technology Data Exchange (ETDEWEB)

1987-04-01

The final report for the project is presented in five volumes. The project sought to determine the impact of Outer Continental Shelf development on recreation and tourism in California. This volume is the User's Guide. It includes the following topics: Introduction and Summary Guide; Input Data Files; Gravity Model Programs; Economic Effects Model Programs; Consumer Surplus Model Programs; References; and Appendices.

Appendices for: Improper Signaling in Two-Path Relay Channels

KAUST Repository

Gaafar, Mohamed

2016-12-01

This document contains the appendices for the work in “Improper Signaling in Two-Path Relay Channels,” which is submitted to 2017 IEEE International Conference on Communications (ICC) Workshop on Full-Duplex Communications for Future Wireless Networks, Paris, France.

Appendices for: Improper Signaling in Two-Path Relay Channels

KAUST Repository

Gaafar, Mohamed; Amin, Osama; Schaefer, Rafael F.; Alouini, Mohamed-Slim

2016-01-01

This document contains the appendices for the work in “Improper Signaling in Two-Path Relay Channels,” which is submitted to 2017 IEEE International Conference on Communications (ICC) Workshop on Full-Duplex Communications for Future Wireless Networks, Paris, France.

ACARP Project C10059. ACARP manual of modern coal testing methods. Volume 2: Appendices

Energy Technology Data Exchange (ETDEWEB)

Sakurovs, R.; Creelman, R.; Pohl, J.; Juniper, L. [CSIRO Energy Technology, Sydney, NSW (Australia)

2002-07-01

The Manual summarises the purpose, applicability, and limitations of a range of standard and modern coal testing methods that have potential to assist the coal company technologist to better evaluate coal performance. It is presented in two volumes. This second volume provides more detailed information regarding the methods discussed in Volume 1.

Preliminary evaluation of alternative waste form solidification processes. Volume II. Evaluation of the processes

International Nuclear Information System (INIS)

1980-08-01

This Volume II presents engineering feasibility evaluations of the eleven processes for solidification of nuclear high-level liquid wastes (HHLW) described in Volume I of this report. Each evaluation was based in a systematic assessment of the process in respect to six principal evaluation criteria: complexity of process; state of development; safety; process requirements; development work required; and facility requirements. The principal criteria were further subdivided into a total of 22 subcriteria, each of which was assigned a weight. Each process was then assigned a figure of merit, on a scale of 1 to 10, for each of the subcriteria. A total rating was obtained for each process by summing the products of the subcriteria ratings and the subcriteria weights. The evaluations were based on the process descriptions presented in Volume I of this report, supplemented by information obtained from the literature, including publications by the originators of the various processes. Waste form properties were, in general, not evaluated. This document describes the approach which was taken, the developent and application of the rating criteria and subcriteria, and the evaluation results. A series of appendices set forth summary descriptions of the processes and the ratings, together with the complete numerical ratings assigned; two appendices present further technical details on the rating process

Assessing indoor air quality options: Final environmental impact statement on new energy-efficient home programs: Volume 2

International Nuclear Information System (INIS)

1988-03-01

This report discusses the impact of energy conservation measures on indoor air quality in various size residential buildings. This volume includes appendices on ventilation rates, indoor pollutant levels, health effects, human risk assessment, radon, fiberglass hazards, tobacco smoke, mitigation

Study of the Utah uranium-milling industry. Volume I. A policy analysis

International Nuclear Information System (INIS)

Turley, R.E.

1980-05-01

This is the first volume of a two volume study of the Utah Uranium Milling Industry. The study was precipitated by a 1977 report issued by the Western Interstate Nuclear Board entitled Policy Recommendations on Financing Stabilization. Perpetual Surveillance and Maintenance of Uranium Mill Tailings. Volume I of this study is a policy analysis or technology assessment of the uranium milling industry in the state of Utah; specifically, the study addresses issues that deal with the perpetual surveillance, monitoring, and maintenance of uranium tailings piles at the end of uranium milling operations, i.e., following shutdown and decommissioning. Volume II of this report serves somewhat as an appendix. It represents a full description of the uranium industry in the state of Utah, including its history and statements regarding its future. The topics covered in volume I are as follows: today's uranium industry in Utah; management of the industry's characteristic nuclear radiation; uranium mill licensing and regulation; state licensing and regulation of uranium mills; forecast of future milling operations; policy needs relative to perpetual surveillance, monitoring, and maintenance of tailings; policy needs relative to perpetual oversight; economic aspects; state revenue from uranium; and summary with conclusions and recommendations. Appendices, figures and tables are also presented

The environmental energy sector programme. Poland: Appendices to feasibility study

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-07-01

The appendices contain Energy Law, Act of 10 April 1997 and also more specific details from the feasibility study for the procurement of a financial solution to the modernisation of the combined heat and power plant in the city of Zielona Gora, Poland. (EHS)

Interim report task 3: immobilization process/equipment testing - task 3.4: non-destructive evaluation appendices part 2 of 2 to Lawrence Livermore National Laboratory under contract b345772

International Nuclear Information System (INIS)

Stewart, M W A; Vance, E R; Day, R A; Lumpkin, G R

2000-01-01

Nine appendices are included: Appendix A - Scanning electron micrographs, energy dispersive x-ray spectrometry image analysis and x-ray diffraction results for samples of composition B1-2 - Th/U-doped baseline ceramic; Appendix B - Scanning electron micrographs, energy dispersive x-ray spectrometry image analysis and x-ray diffraction results for samples of composition B1-4 - Th/U-doped baseline + impurities ceramic; Appendix C - Scanning electron micrographs, energy dispersive x-ray spectrometry image analysis and x-ray diffraction results for samples of composition B1-10 - Th/U-doped zirconolite-rich ceramic; Appendix D - Scanning electron micrographs, energy dispersive x-ray spectrometry image analysis and x-ray diffraction results for samples of composition B1-12 - Th/U-doped brannerite-rich ceramic; Appendix E - Scanning electron micrographs, energy dispersive x-ray spectrometry image analysis and x-ray diffraction results for samples of composition B1-14 - Th/U-doped nominally 10 % perovskite ceramic; Appendix F - Scanning electron micrographs, energy dispersive x-ray spectrometry image analysis and x-ray diffraction results for samples of composition B1-16 - Th/U-doped ∼ 10 % phosphate-doped ceramic;Appendix G - Scanning electron micrographs, energy dispersive x-ray spectrometry image analysis and x-ray diffraction results for samples of composition B1-1 - Pu/U-doped baseline ceramic ;Appendix H - Scanning electron micrographs, energy dispersive x-ray spectrometry image analysis and x-ray diffraction results for samples of composition A-7 and B3-13 - Pu/U-doped baseline + impurities ceramics; and, Appendix I - Scanning electron micrographs, energy dispersive x-ray spectrometry image analysis and x-ray diffraction results for samples of composition B1-13 - Pu/U-doped nominally 10% perovskite ceramic

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

Funding California Schools: The Revenue Limit System. Technical Appendices

Science.gov (United States)

Weston, Margaret

2010-01-01

This document presents the technical appendices accompanying the report, "Funding California Schools: The Revenue Limit System." Included are: (1) Revenue Limit Calculation and Decomposition; (2) Data and Methods; and (3) Base Funding Alternative Simulation Results. (Contains 5 tables and 26 footnotes.) [For the main report,…

Technology, safety, and costs of decommissioning a reference pressurized water reactor power station. Appendices

International Nuclear Information System (INIS)

Smith, R.I.; Konzek, G.J.; Kennedy, W.E. Jr.

1978-05-01

Detailed appendices are presented under the following headings: reference PWR facility description, reference PWR site description, estimates of residual radioactivity, alternative methods for financing decommissioning, radiation dose methodology, generic decommissioning activities, intermediate dismantlement activities, safe storage and deferred dismantlement activities, compilation of unit cost factors, and safety assessment details

No-migration variance petition: Draft. Volume 4, Appendices DIF, GAS, GCR (Volume 1)

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-05-31

The Department of Energy is responsible for the disposition of transuranic (TRU) waste generated by national defense-related activities. Approximately 2.6 million cubic feet of the se waste have been generated and are stored at various facilities across the country. The Waste Isolation Pilot Plant (WIPP), was sited and constructed to meet stringent disposal requirements. In order to permanently dispose of TRU waste, the DOE has elected to petition the US EPA for a variance from the Land Disposal Restrictions of RCRA. This document fulfills the reporting requirements for the petition. This report is volume 4 of the petition which presents details about the transport characteristics across drum filter vents and polymer bags; gas generation reactions and rates during long-term WIPP operation; and geological characterization of the WIPP site.

No-migration variance petition: Draft. Volume 4, Appendices DIF, GAS, GCR (Volume 1)

International Nuclear Information System (INIS)

1995-01-01

The Department of Energy is responsible for the disposition of transuranic (TRU) waste generated by national defense-related activities. Approximately 2.6 million cubic feet of the se waste have been generated and are stored at various facilities across the country. The Waste Isolation Pilot Plant (WIPP), was sited and constructed to meet stringent disposal requirements. In order to permanently dispose of TRU waste, the DOE has elected to petition the US EPA for a variance from the Land Disposal Restrictions of RCRA. This document fulfills the reporting requirements for the petition. This report is volume 4 of the petition which presents details about the transport characteristics across drum filter vents and polymer bags; gas generation reactions and rates during long-term WIPP operation; and geological characterization of the WIPP site

Uranium milling, project M-25. Volume I. summary and text. Final generic environmental impact statement

International Nuclear Information System (INIS)

1980-09-01

The Final Generic Environmental Impact Statement (GEIS) on Uranium Milling focuses primarily upon the matter of mill tailings disposal. It evaluates both the costs and benefits of alternative tailings disposal modes and draws conclusions about criteria which should be incorporated into regulations. Both institutional and technical controls are evaluated. Health impacts considered were both short and long term. Restatement and resolution of all public comments received on the draft (GEIS) are presented. There are three volumes: Volume I is the main text and Volumes II and III are supporting appendices

Trends in laboratory test volumes for Medicare Part B reimbursements, 2000-2010.

Science.gov (United States)

Shahangian, Shahram; Alspach, Todd D; Astles, J Rex; Yesupriya, Ajay; Dettwyler, William K

2014-02-01

Changes in reimbursements for clinical laboratory testing may help us assess the effect of various variables, such as testing recommendations, market forces, changes in testing technology, and changes in clinical or laboratory practices, and provide information that can influence health care and public health policy decisions. To date, however, there has been no report, to our knowledge, of longitudinal trends in national laboratory test use. To evaluate Medicare Part B-reimbursed volumes of selected laboratory tests per 10,000 enrollees from 2000 through 2010. Laboratory test reimbursement volumes per 10,000 enrollees in Medicare Part B were obtained from the Centers for Medicare & Medicaid Services (Baltimore, Maryland). The ratio of the most recent (2010) reimbursed test volume per 10,000 Medicare enrollees, divided by the oldest data (usually 2000) during this decade, called the volume ratio, was used to measure trends in test reimbursement. Laboratory tests with a reimbursement claim frequency of at least 10 per 10,000 Medicare enrollees in 2010 were selected, provided there was more than a 50% change in test reimbursement volume during the 2000-2010 decade. We combined the reimbursed test volumes for the few tests that were listed under more than one code in the Current Procedural Terminology (American Medical Association, Chicago, Illinois). A 2-sided Poisson regression, adjusted for potential overdispersion, was used to determine P values for the trend; trends were considered significant at P reimbursement volumes were electrolytes, digoxin, carbamazepine, phenytoin, and lithium, with volume ratios ranging from 0.27 to 0.64 (P reimbursement volumes were meprobamate, opiates, methadone, phencyclidine, amphetamines, cocaine, and vitamin D, with volume ratios ranging from 83 to 1510 (P reimbursement volumes increased for most of the selected tests, other tests exhibited statistically significant downward trends in annual reimbursement volumes. The observed

Resource Conservation and Recovery Act, Part B permit application [of the Waste Isolation Pilot Plant (WIPP)]. Volume 11, Chapter D, Appendix D4--Chapter D, Appendix D17: Revision 3

Energy Technology Data Exchange (ETDEWEB)

1993-03-01

This volume contains appendices D4 through D17 which cover the following: Waste Isolation Pilot Plant site environmental report; ecological monitoring program at the Waste Isolation Pilot Plant; site characterization; regional and site geology and hydrology; general geology; dissolution features; ground water hydrology; typical carbon sorption bed efficiency; VOC monitoring plan for bin-room tests; chemical compatibility analysis of waste forms and container materials; probable maximum precipitation; WHIP supplementary roof support system room 1, panel 1; and corrosion risk assessment of the Waste Isolation Pilot Plant ``humid`` test bins.

Effect of Glu-B3 Allelic Variation on Sodium Dodecyl Sulfate Sedimentation Volume in Common Wheat (Triticum aestivum L.

Directory of Open Access Journals (Sweden)

Hongqi Si

2013-01-01

Full Text Available Sodium dodecyl sulfate (SDS sedimentation volume has long been used to characterize wheat flours and meals with the aim of predicting processing and end-product qualities. In order to survey the influence of low-molecular-weight glutenin subunits (LMW-GSs at Glu-B3 locus on wheat SDS sedimentation volume, a total of 283 wheat (Triticum aestivum L. varieties including landraces and improved and introduced cultivars were analyzed using 10 allele-specific PCR markers at the Glu-B3 locus. The highest allele frequency observed in the tested varieties was Glu-B3i with 21.9% in all varieties, 21.1% in landraces, 25.5% in improved cultivars, and 12% in introduced cultivars. Glu-B3 locus represented 8.6% of the variance in wheat SDS sedimentation volume, and Glu-B3b, Glu-B3g, and Glu-B3h significantly heightened the SDS sedimentation volume, but Glu-B3a, Glu-B3c, and Glu-B3j significantly lowered the SDS sedimentation volume. For the bread-making quality, the most desirable alleles Glu-B3b and Glu-B3g become more and more popular and the least desirable alleles Glu-B3a and Glu-B3c got less and less in modern improved cultivars, suggesting that wheat grain quality in China has been significantly improved through breeding effort.

Focus on Mentee-Mentor Relationships: The 10th Grade Implementation of iMentor's College Ready Program. Technical Appendices

Science.gov (United States)

Merrill, Lisa; Kang, David; Siman, Nina; Soltani, Jasmine

2016-01-01

This document presents the technical appendices that accompany the full report entitled:"Focus on Mentee-Mentor Relationships: The 10th Grade Implementation of iMentor's College Ready Program." The appendices include: (1) Mentor Survey Construct Items; (2) Qualative Data Collection and Analysis Methods; and (3) Methods for Estimating the…

[Expression of receptors of estrogens and androgens in the testicular appendices].

Science.gov (United States)

Paredes Esteban, R M; Luque Barona, R J; Velasco Sánchez, B; Rodríguez Vargas, J; Lorite, A; García Ruiz, M

2008-07-01

The appendices or hidátides of the testicle are structures that are considered an embryonic rest. In testicular hidátide estrogen receivers have been demonstrated but in the epididimys the results vary. Has been theorized that the elevation of the estrogen levels in the puberty can produce an inflammation and torsion of hidátide, nevertheless, in the epididimys in which the estrogen expression is not clear (and also they are twisted) the theory is put in doubt. This controversy takes us to the accomplishment of this work. A prospective study is made in 20 testicular appendices, of which 7 from the epididimys are extirpated of patients to whom an escrotal exploration is made in the development of surgery of processes of the inguino-escrotal channel (hidroceles, hernias). Optical microscopy and inmunohistoquímical study are analyzed by means of using prediluted monoclonales antibodies, for receivers of estrogens, androgens and proliferative index. The results were proceed and analyzed by means of SPSS statistical program. All hidátides, testicular and from the epididimarys expressed receivers for estrogens without significant difference among them, not existing differences as far as the location of receiving sayings within the three compartments of hidátide. The number of estrogen receivers was in relation to the age of the patient. Only hidátides from the epididimys fundamentally expressed receivers of located androgens and at level of ductus. We have not found significant relation between the proliferative index and the expression of estrogen receivers. The proliferative index was more elevated at level of ductus. 1) As much the testicular appendices as those from the epididimays expressed receivers of estrogens at level of the three compartments. It makes think about a same embryonic origin, although only the epididimal ones expressed androgen receivers. 2) the observation of estrogen receivers in both types of hidátides, as well as the relation of the

Guidance and Control Software Project Data - Volume 1: Planning Documents

Science.gov (United States)

Hayhurst, Kelly J. (Editor)

2008-01-01

The Guidance and Control Software (GCS) project was the last in a series of software reliability studies conducted at Langley Research Center between 1977 and 1994. The technical results of the GCS project were recorded after the experiment was completed. Some of the support documentation produced as part of the experiment, however, is serving an unexpected role far beyond its original project context. Some of the software used as part of the GCS project was developed to conform to the RTCA/DO-178B software standard, "Software Considerations in Airborne Systems and Equipment Certification," used in the civil aviation industry. That standard requires extensive documentation throughout the software development life cycle, including plans, software requirements, design and source code, verification cases and results, and configuration management and quality control data. The project documentation that includes this information is open for public scrutiny without the legal or safety implications associated with comparable data from an avionics manufacturer. This public availability has afforded an opportunity to use the GCS project documents for DO-178B training. This report provides a brief overview of the GCS project, describes the 4-volume set of documents and the role they are playing in training, and includes the planning documents from the GCS project. Volume 1 contains five appendices: A. Plan for Software Aspects of Certification for the Guidance and Control Software Project; B. Software Development Standards for the Guidance and Control Software Project; C. Software Verification Plan for the Guidance and Control Software Project; D. Software Configuration Management Plan for the Guidance and Control Software Project; and E. Software Quality Assurance Activities.

Guidance and Control Software Project Data - Volume 3: Verification Documents

Science.gov (United States)

Hayhurst, Kelly J. (Editor)

2008-01-01

The Guidance and Control Software (GCS) project was the last in a series of software reliability studies conducted at Langley Research Center between 1977 and 1994. The technical results of the GCS project were recorded after the experiment was completed. Some of the support documentation produced as part of the experiment, however, is serving an unexpected role far beyond its original project context. Some of the software used as part of the GCS project was developed to conform to the RTCA/DO-178B software standard, "Software Considerations in Airborne Systems and Equipment Certification," used in the civil aviation industry. That standard requires extensive documentation throughout the software development life cycle, including plans, software requirements, design and source code, verification cases and results, and configuration management and quality control data. The project documentation that includes this information is open for public scrutiny without the legal or safety implications associated with comparable data from an avionics manufacturer. This public availability has afforded an opportunity to use the GCS project documents for DO-178B training. This report provides a brief overview of the GCS project, describes the 4-volume set of documents and the role they are playing in training, and includes the verification documents from the GCS project. Volume 3 contains four appendices: A. Software Verification Cases and Procedures for the Guidance and Control Software Project; B. Software Verification Results for the Pluto Implementation of the Guidance and Control Software; C. Review Records for the Pluto Implementation of the Guidance and Control Software; and D. Test Results Logs for the Pluto Implementation of the Guidance and Control Software.

Physics Letters B, Volume 716, Issue 1- Cover Page

CERN Multimedia

CERN

2012-01-01

The cover page of the Physics Letters B Journal, Volume 716, Issue 1, dedicated to the observation of a new particle in the search for the Standard Model Higgs boson. To celebrate this historical discovery, Elsevier reprinted the ATLAS and the CMS articles together with a foreword by Peter Higgs and the other scientists that predicted the existence of the so-called Higgs boson and published this in a separate booklet.

Mixed waste focus area integrated technical baseline report. Phase I, Volume 2: Revision 0

International Nuclear Information System (INIS)

1996-01-01

This document (Volume 2) contains the Appendices A through J for the Mixed Waste Focus Area Integrated Technical Baseline Report Phase I for the Idaho National Engineering Laboratory. Included are: Waste Type Managers' Resumes, detailed information on wastewater, combustible organics, debris, unique waste, and inorganic homogeneous solids and soils, and waste data information. A detailed list of technology deficiencies and site needs identification is also provided

[Acute abdomen secondary to appendiceal intussusception].

Science.gov (United States)

Betancourth-Alvarenga, J E; Vázquez-Rueda, F; Murcia-Pascual, F J; Ayala-Montoro, J

2015-01-01

Appendiceal intussusception is a rare condition that can occur at any age. Only a few cases have been reported, and most are found during surgery. The therapeutic approach is usually surgical, ranging from an appendectomy to a hemicolectomy, primarily for biopsy and to rule out possible malignancy. Three cases of children under 14 years who underwent surgery for acute abdominal pain located in the right iliac fossa are presented; one with preoperative diagnosis by ultrasound, and the other two with positive intraoperative findings of intussusception of the cecal appendix, with acute appendicitis being histologically confirmed. Copyright © 2013 Asociación Española de Pediatría. Published by Elsevier Espana. All rights reserved.

Appendicitis complicated by appendiceal metastasis via peritoneal dissemination from lung cancer.

Science.gov (United States)

Shiota, Naoki; Furonaka, Makoto; Kikutani, Kazuya; Haji, Keiko; Fujisaki, Seiji; Nishida, Toshihiro

2016-07-01

Peritoneal disseminations from lung cancer are difficult to detect during the patient's clinical course. Therefore, complications of this condition are unclear. We report a case in which peritoneal dissemination from lung cancer complicated appendicitis. A 74-year-old man with lung cancer who was receiving maintenance therapy presented at our hospital because of abdominal pain. It was the seventh day after the 14th cycle of maintenance therapy with bevacizumab. He was diagnosed with acute appendicitis. The resected appendix showed acute appendicitis complicated by appendiceal metastasis from lung cancer. Adenocarcinoma was observed predominantly in the serous membrane from the neck to the tail of the appendix. The distribution of the adenocarcinoma was diffuse. Peritoneal dissemination was considered the route of metastasis. He was admitted to the palliative care unit 10 months after appendectomy. Appendiceal metastasis via peritoneal dissemination from lung cancer complicated appendicitis in our patient who had been receiving bevacizumab.

Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1. Analysis of core damage frequency from internal events for plant operational state 5 during a refueling outage. Internal events appendices K to M

International Nuclear Information System (INIS)

Forester, J.; Yakle, J.; Walsh, B.; Darby, J.; Whitehead, D.; Staple, B.; Brown, T.

1994-07-01

This report provides supporting documentation for various tasks associated with the performance of the probabilistic risk assessment for Plant Operational State 5 (approximately Cold Shutdown as defined by Grand Gulf Technical Specifications) during a refueling outage at Grand Gulf, Unit 1 as documented in Volume 2, Part 1 of NUREG/CR-6143. The report contains the following appendices: K - HEP Locator Files; L - Supporting Information for the Plant Damage State Analysis; M - Summary of Results from the Coarse Screening Analysis - Phase 1A

Acute appendiceal abscess and atraumatic splenic rupture: A case of dual pathology.

Science.gov (United States)

Ananthavarathan, Piriyankan; Patel, Kamlesh; Doran, Catherine; Suggett, Nigel

2016-01-01

Atraumatic splenic rupture is a rare surgical emergency that is often attributed to neoplastic or infectious causes. Rarely, it has been identified to also occur in the setting of an acute severe sepsis and in cases of pelvic or splenic abscess formation post-appendicectomy. However, to our knowledge, the co-presentation of acute appendiceal abscess and splenic rupture has not been previously described. We present the case of a 67-year old male with decompensating haemorrhagic shock secondary to atraumatic splenic rupture on a background of an inadequately treated complicated appendicitis originally managed as diverticulitis with antibiotics in the community. Intra-operatively, in addition to a de-gloved, ruptured spleen; an acutely inflamed appendiceal abscess was also identified. A concomitant splenectomy, washout and appendicectomy and was therefore performed. Histopathological examination revealed a normal spleen with a stripped capsular layer. Mucosal ulceration, transmural inflammation and serositis of the appendix appeared to be consistent with acute appendicitis. Our case demonstrates how inadequately treated sepsis may predispose to an acute presentation of splenic rupture with associated haemorrhagic shock; which may initially be interpreted as septic shock. However, we demonstrate how insults such as sepsis and haemorrhagic shock may co-exist warranting careful consideration of possible dual pathologies in complex presentations which may be life-threatening. While the causal relationship between acute appendicitis and atraumatic spontaneous splenic rupture remains unclear, our case considers and highlights the importance of considering dual pathology in patients presenting in the acute setting. Copyright © 2016. Published by Elsevier Ltd.

Proceedings of the Advanced Turbine Systems Annual Program Review meeting. Volume 2

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-10-01

Goal of the 8-year program are to develop cleaner, more efficient, and less expensive gas turbine systems for utility and industrial electric power generation, cogeneration, and mechanical drive units. The conference is held annually for energy executives, engineers, scientists, and other interested parties in industry, academia, and Government. This volume contains 28 poster presentations and appendices; the poster papers are processed separately for the data base.

RSE-M: In-Service Inspection Rules for Mechanical Components of PWR Nuclear Islands

International Nuclear Information System (INIS)

2016-01-01

The RSE-M code defines in-service inspection operations. It applies to pressure equipment used in PWR plants, as well as spare parts for such equipment. The RSE-M code does not apply to equipment made from materials other than metal. It is based on the RCC-M code for requirements relating to the design and fabrication of mechanical components. Use: The inspection rules specified in the RSE-M code describe the standard requirements of best practice within the French nuclear industry, based on its own feedback from operating several nuclear units and partly supplemented with requirements stipulated by French regulations. To date, the 58 units in France's nuclear infrastructure enforce the in-service inspection rules of the RSE-M code. Operation of 30 commissioned units in China's nuclear infrastructure, corresponding to the M310, CPR-1000 and CPR-600 reactors, is based on the RSE-M code (since 2007, use of AFCEN codes has been required by NNSA for Generation II+ reactors). Contents of the 2016 Edition: Volume I - Rules: Section A - General rules, Section B - Specific rules for class 1 components, Section C - Specific rules for class 2 or 3 components, Section D - Specific rules for components not assigned to any particular RSE-M class; Volume II - Appendices 1 to 8: Appendices 1.0 to 1.9: supporting appendices for the general requirements, Appendix 2.1: appendix associated with chap. 2000 Requalifications, Hydraulic Proof Tests and Hydraulic Tests, Appendices 4.1 to 4.4: appendices associated with chap. 4000 Examination techniques, Appendices 5.1 to 5.8 and RPP2: appendices associated with chap. 5000 Mechanical and Materials, Appendices 8.1 to 8.2: appendices associated with chap. 8000 Maintenance Operations; Volume III: Appendix 3.1 - Visit tables: main primary and secondary systems, EPR pre-service inspection program, Class 2 or 3 vessels; Appendix 3.2 - Inspection Plans For Non-Nuclear Pressure Equipment

NEW CLASSIFICATION AND DIAGNOSIS OF APPENDICEAL CARCINOID TUMORS

Directory of Open Access Journals (Sweden)

Vuka Katić

2012-03-01

Full Text Available Carcinoid tumours are rare lesions that belong to the APUDoma category having the capacity of Amine Precursor Uptake and Decarboxylase. Gastrointestinal system comprises 90% of all carcinoids in the body and they are the most common type of primary malignant lesions of the appendix. New WHO classification of gastrointestinal carcinoids, diagnostic dilemmas of some carcinoid variants and, sometimes unpredictable prognosis are the reasons for the following study: clinical, macro- and microscopical as well as cytochemical and immunocytochemical examination of the vermiform appendix carcinoids, surgically removed from 16 patients. The appendectomy was induced by acute appendicitis or tumorous mass, without carcinoid syndrome. After two-day fixation in 10% formaldehyde, routinelly processed and embedded in paraffin, laboratory sections were stained with H&E, Fontana-Masson’s, Grimelius’, FIF and ABPAS methods. ABC method has been used for immunohistochemical examination. The antibodies for Chromogranin A, NSE, Synaptophysin, Cytokeratin 7, S-100 protein, Ki67 and CEA (primary antibodies and ABC (secondary antibody (Dako Kopenhagen were tested. The patients had no carcinoid syndrome. The most frequent was classic appendiceal carcinoid, well differentiated - NETG1 (8 cases, without metastases; goblet cell carcinoids were rare (3 cases, one case with liver metastases. The second case of goblet cell carcinoid was associated with cystadenoma papillare mucinosum, complicated by pseudomixoma peritonei and the third case was limited only to appendiceal wall. The patient with liver metastases died five months after appendectomy. The patient with goblet cell carcinoid associated with papillary mucinous cystadenoma and complicated by pseudomixoma peritonei had re-operation with both partial cecal and right ovarial resection, associated with washing the peritoneal cavity. The patient was feeling well during six years from the second operation. Based on our

Plasma diagnostics package. Volume 2: Spacelab 2 section. Part B: Thesis projects

Science.gov (United States)

Pickett, Jolene S. (Compiler); Frank, L. A. (Compiler); Kurth, W. S. (Compiler)

1988-01-01

This volume (2), which consists of two parts (A and B), of the Plasma Diagnostics Package (PDP) Final Science Report contains a summary of all of the data reduction and scientific analyses which were performed using PDP data obtained on STS-51F as a part of the Spacelab 2 (SL-2) payload. This work was performed during the period of launch, July 29, 1985, through June 30, 1988. During this period the primary data reduction effort consisted of processing summary plots of the data received by 12 of the 14 instruments located on the PDP and submitting these data to the National Space Science Data Center (NSSDC). Three Master's and three Ph.D. theses were written using PDP instrumentation data. These theses are listed in Volume 2, Part B.

A Caulobacter MreB mutant with irregular cell shape exhibits compensatory widening to maintain a preferred surface area to volume ratio

Science.gov (United States)

Harris, Leigh K.; Dye, Natalie A.; Theriot, Julie A.

2014-01-01

Summary Rod-shaped bacteria typically elongate at a uniform width. To investigate the genetic and physiological determinants involved in this process, we studied a mutation in the morphogenetic protein MreB in Caulobacter crescentus that gives rise to cells with a variable-width phenotype, where cells have regions that are both thinner and wider than wild-type. During growth, individual cells develop a balance of wide and thin regions, and mutant MreB dynamically localizes to poles and thin regions. Surprisingly, the surface area to volume ratio of these irregularly-shaped cells is, on average, very similar to wild-type. We propose that, while mutant MreB localizes to thin regions and promotes rod-like growth there, wide regions develop as a compensatory mechanism, allowing cells to maintain a wild-type-like surface area to volume ratio. To support this model, we have shown that cell widening is abrogated in growth conditions that promote higher surface area to volume ratios, and we have observed individual cells with high ratios return to wild-type levels over several hours by developing wide regions, suggesting that compensation can take place at the level of individual cells. PMID:25266768

Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit 1: Analysis of core damage frequency from internal events during mid-loop operations, Appendices A--D. Volume 2, Part 2

International Nuclear Information System (INIS)

Chu, T.L.; Musicki, Z.; Kohut, P.

1994-06-01

During 1989, the Nuclear Regulatory Commission (NRC) initiated an extensive program to carefully examine the Potential risks during low Power and shutdown operations. The program includes two parallel projects being performed by Brookhaven National Laboratory (BNL) and Sandia National Laboratories (SNL). Two plants, Surry (pressurized water reactor) and Grand Gulf (boiling water reactor), were selected as the Plants to be studied. The objectives of the program are to assess the risks of severe accidents initiated during plant operational states other than full power operation and to compare the estimated core damage frequencies, important accident sequences and other qualitative and quantitative results with those accidents initiated during full power operation as assessed in NUREG-1150. The objective of this report is to document the approach utilized in the Surry plant and discuss the results obtained. A parallel report for the Grand Gulf plant is prepared by SNL. This study shows that the core-damage frequency during mid-loop operation at the Surry plant is comparable to that of power operation. We recognize that there is very large uncertainty in the human error probabilities in this study. This study identified that only a few procedures are available for mitigating accidents that may occur during shutdown. Procedures written specifically for shutdown accidents would be useful. This document, Volume 2, Pt. 2 provides appendices A through D of this report

Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit 1: Analysis of core damage frequency from internal events during mid-loop operations, Appendices A--D. Volume 2, Part 2

Energy Technology Data Exchange (ETDEWEB)

Chu, T.L.; Musicki, Z.; Kohut, P. [Brookhaven National Lab., Upton, NY (United States)] [and others

1994-06-01

During 1989, the Nuclear Regulatory Commission (NRC) initiated an extensive program to carefully examine the Potential risks during low Power and shutdown operations. The program includes two parallel projects being performed by Brookhaven National Laboratory (BNL) and Sandia National Laboratories (SNL). Two plants, Surry (pressurized water reactor) and Grand Gulf (boiling water reactor), were selected as the Plants to be studied. The objectives of the program are to assess the risks of severe accidents initiated during plant operational states other than full power operation and to compare the estimated core damage frequencies, important accident sequences and other qualitative and quantitative results with those accidents initiated during full power operation as assessed in NUREG-1150. The objective of this report is to document the approach utilized in the Surry plant and discuss the results obtained. A parallel report for the Grand Gulf plant is prepared by SNL. This study shows that the core-damage frequency during mid-loop operation at the Surry plant is comparable to that of power operation. We recognize that there is very large uncertainty in the human error probabilities in this study. This study identified that only a few procedures are available for mitigating accidents that may occur during shutdown. Procedures written specifically for shutdown accidents would be useful. This document, Volume 2, Pt. 2 provides appendices A through D of this report.

Mixed strategies for energy conservation and alternative energy utilization (solar) in buildings. Final report. Volume III. Appendixes. [10 appendices

Energy Technology Data Exchange (ETDEWEB)

None

1977-06-01

This appendix summarizes building characteristics used to determine heating and cooling loads for each of the five building types in each of the four regions. For the selected five buildings, the following data are attached: new and existing construction characteristics; new and existing construction thermal resistance; floor plan and elevation; people load schedule; lighting load schedule; appliance load schedule; ventilation schedule; and hot water use schedule. For the five building types (single family, apartment buildings, commercial buildings, office buildings, and schools), data are compiled in 10 appendices. These are Building Characteristics; Alternate Energy Sources and Energy Conservation Techniques Description, Costs, Fuel Price Scenarios; Life Cycle Cost Model; Simulation Models; Solar Heating/Cooling System; Condensed Weather; Single and Multi-Family Dwelling Characteristics and Energy Conservation Techniques; Mixed Strategies for Energy Conservation and Alternative Energy Utilization in Buildings. An extensive bibliography is given in the final appendix. (MCW)

Local Agenda 21 in Apeldoorn, Netherlands. Appendices

International Nuclear Information System (INIS)

Dullens, M.; Schouw, J.C.; Straatman, T.G.

1999-08-01

The (im)possibilities of concrete projects to start Local Agenda 21 activities in Apeldoorn, Netherlands, are discussed. Attention is paid to options with respect to transportation, energy conservation, water use, soil pollution, waste management, and nature. Local Agenda 21 is a program by means of which local governments can contribute to sustainable targets as formulated during the 1992 conference Agenda 21 of the United Nations (UN). The appendices contain background information (reports of meetings, elaboration of ecological subjects in relation with socio-economic subjects, and a table with all the recommendations) and are published in this report. The main report is a separate publication

Membranous appendices of spherosomes (oleosomes) : Possible role in fat utilization in germinating oil seeds.

Science.gov (United States)

Wanner, G; Theimer, R R

1978-01-01

Spherosomes (oleosomes) of cotyledons of rape (Brassica napus L.), sunflower (Helianthus annuus L.), and watermelon (Citrullus vulgaris, Schrad.) seedlings are delimited by a "half unit membrane" that appears to be continuous with each of the osmiophilic layers of a tripartite unit membrane forming a handlelike appendix of the spherosomes. Prior to any noticeable utilization of the spherosomal storage fat, ribosomes were found to be attached to these "handles". At later stages appendices of the spherosomes are smooth, showing a diameter of about 22 nm that greatly exceeds the thickness of any other unit membrane profiles identical in structure and diameter osomes appears to be continuous with the thick lipid layer of the handles. In intermediate stages of fat depletion the spherosomal bodies become invaginated with cytoplasmic material. Finally vesicles with cytoplasmic contents surrounded by a membrane with a typically thick lipid layer are left in the cells. Membrane profiles indentical in structure and diameter to the spherosomal appendices were also present in electron micrographs of the lipolytic membrane fraction recovered from sucrose density gradients after centrifugation of a microsomal cell fraction. The ultrastructural observations are taken for evidence that the spherosomal appendices represent the lipase-carrying membranes isolated previously (Theimer and Rosnitschek, 1978). A novel hypothesis for development and utilization of fat-storing spherosomes is also proposed.

Primary appendiceal lymphoma presenting as suspected perforated acute appendicitis: clinical, sonography and CT findings with pathologic correlation.

Science.gov (United States)

Guo, Jingjing; Wu, Gang; Chen, Xiaojun; Li, Xiaodong

2014-01-01

The gastrointestinal tract is the most common site for extranodal involvement by non-Hodgkin's lymphoma. However, primary appendiceal lymphomas presenting as perforated acute appendicitis are very rare: they occur in only 0.015% of all gastrointestinal lymphoma cases. The management of this condition is still controversial, and a multimodality approach (e.g., surgery, radiation therapy, and chemotherapy) is the optimal treatment. In these cases, appendiceal non-Hodgkin's lymphomas typically manifest with acute symptoms in patients with no prior lymphoma history. Additionally, we treated our patient with a right hemicolectomy and postoperative multiagent chemotherapy.

Picosecond studies of excitation transport in a finite volume: The clustered transport system octadecyl rhodamine B in triton X-100 micelles

International Nuclear Information System (INIS)

Ediger, M.D.; Domingue, R.P.; Fayer, M.D.

1984-01-01

A detailed experimental and theoretical examination of electronic excited state transport in the finite volume system, octadecyl rhodamine B molecules in triton X-100 micelles, is presented. Picosecond fluorescence mixing and transient grating techniques were used to examine systems in which the average number of chromophores per micelle ranged from 0.1 to 11. Because of the clustering of chromophores in the small micelles, the energy transport observed is extremely efficient. A statistical mechanical theory, based on a density expansion with a Pade approximant, is developed for donor--donor transport on a spherical surface. This theory accurately accounts for the experimental data with only the micelle radius as an adjustable parameter. The radius obtained from this procedure is in good agreement with determinations by other methods. This demonstrates that quantitative information about the spatial extent of chromophore distributions in small volumes can be obtained when appropriate finite volume energy transport theories are employed. It is shown that theories developed for infinite volumes are not applicable to systems such as the ones considered here. Finally the partitioning of rhodamine B and octadecyl rhodamine B between aqueous and micellar phases is measured, and lifetimes and rotation times are reported

Geothermal resource assessment for the state of Texas: status of progress, November 1980. Final report. Appendices A through D

Energy Technology Data Exchange (ETDEWEB)

Woodruff, C.M. Jr.; Caran, S.C.; Gever, C.; Henry, C.D.; Macpherson, G.L.; McBride, M.W.

1982-03-01

These appendices include: a folio of county maps showing locations of well data across the state; a computerized tabulation of the wells depicted; an explanation of the computer coding procedures; and a selected bibliography on heat flow and geothermics. (MHR)

Characteristics of potential repository wastes: Volume 4, Appendix 4A, Nuclear reactors at educational institutions of the United States; Appendix 4B, Data sheets for nuclear reactors at educational institutions; Appendix 4C, Supplemental data for Fort St. Vrain spent fuel; Appendix 4D, Supplemental data for Peach Bottom 1 spent fuel; Appendix 4E, Supplemental data for Fast Flux Test Facility

International Nuclear Information System (INIS)

1992-07-01

Volume 4 contains the following appendices: nuclear reactors at educational institutions in the United States; data sheets for nuclear reactors at educational institutions in the United States(operational reactors and shut-down reactors); supplemental data for Fort St. Vrain spent fuel; supplemental data for Peach Bottom 1 spent fuel; and supplemental data for Fast Flux Test Facility

Report on corrections and future considerations for Appendices II–VIII of the International Code of Nomenclature for Algae, Fungi, and Plants

Science.gov (United States)

For the first time, the main text and Appendices II–VIII of the International Code of Nomenclature were separately published following decisions of the Melbourne Nomenclature Section, which contributed to subsequent development of an online resource capable of producing the Appendices in real time. ...

Inflammatory markers in blood and serum tumor markers predict survival in patients with epithelial appendiceal neoplasms undergoing surgical cytoreduction and intraperitoneal chemotherapy.

Science.gov (United States)

Chua, Terence C; Chong, Chanel H; Liauw, Winston; Zhao, Jing; Morris, David L

2012-08-01

The study examines the role inflammatory and tumor markers as biomarkers to preoperatively predict outcome in patients with epithelial appendiceal neoplasm undergoing cytoreduction and intraperitoneal chemotherapy. Associations between baseline variables, tumor markers [CEA (carcinoembyronic antigen], CA125, CA199), inflammatory markers including neutrophils-lymphocyte ratio (NLR), platelet-lymphocyte ratio (PLR), and C-reactive protein (CRP) with progression-free survival (PFS) and overall survival (OS) were examined in patients undergoing surgical cytoreduction and intraperitoneal chemotherapy for epithelial appendiceal neoplasm. A total of 174 patients with epithelial appendiceal neoplasm (low-grade pseudomyxoma, n = 117; appendiceal cancer, n = 57) underwent cytoreduction. On univariate analysis, all 3 inflammatory and tumor markers predicted for both PFS and OS, respectively; NLR ≤ 2.6 (P = 0.01, P = 0.002), PLR ≤ 166 (P = 0.006, P = 0.016), CRP ≤ 12.5 (P = 0.001, P = 0.008), CEA (P 37 (P = 0.003), and a CRP > 12.5 (P = 0.013). A higher peritoneal cancer index (PCI > 24) was associated with elevation in CEA > 12, CA125 > 39, CA199 > 37, PLR > 166 and CRP > 12. The tumor histologic subtype was associated with CA 199 levels. The results from this investigation suggest that preoperative inflammatory markers in blood and serologic tumor markers may predict outcomes and are associated with tumor biology in patients with epithelial appendiceal neoplasm undergoing cytoreduction and intraperitoneal chemotherapy treatment.

The ADVANCE project: Formal evaluation of the targeted deployment. Volume 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-01-01

The Advanced Driver and Vehicle Advisory Navigation ConcEpt (ADVANCE) was an invehicle advanced traveler information system (ATIS) that operated in the northwest suburbs of Chicago, Illinois. It was designed to provide origin-destination shortest-time route guidance to a vehicle based on (a) an on-board static (fixed) data base of average network link travel times by time of day, combined as available and appropriate with (b) dynamic (real-time) information on traffic conditions provided by radio frequency (RF) communications to and from a traffic information center (TIC). Originally conceived in 1990 as a major project that would have installed 3,000 to 5,000 route guidance units in privately owned vehicles throughout the test area, ADVANCE was restructured in 1995 as a {open_quotes}targeted deployment,{close_quotes} in which approximately 80 vehicles were to be equipped with the guidance units - Mobile Navigation Assistants (MNAs) - to be in full communication with the TIC while driving the ADVANCE test area road system. Volume one consists of the evaluation managers overview report, and several appendices containing test results.

Comment Hobbes tente de rendre son matérialisme acceptable dans les appendices du Léviathan

Directory of Open Access Journals (Sweden)

Anne Staquet

2011-11-01

Full Text Available Le Léviathan de Hobbes [1651] a subi de nombreuses attaques, au point qu’il est jugé responsable de la grande peste de 1665 et de l’incendie de Londres l’année suivante et que le parlement ouvre une procédure contre l’ouvrage. Aussi, lorsqu’en 1666, Thomas Hobbes veut publier la traduction latine de ce livre, il y adjoint trois appendices. La version latine de l’œuvre est généralement jugée plus acceptable que le texte originaire anglais. En étudiant la manière dont Hobbes traite de son matérialisme dans ces appendices, je tente de montrer que les addenda latins ne constituent en aucune manière un retour en arrière du texte, mais que le philosophe enrobe simplement davantage des propos que, par ailleurs, il rend plus radicaux.Hobbes’s Leviathan [1651] has been critiqued so much that it was held responsible for the Great Plague of 1665 and the Fire of London during the following year, resulting in the Parliament instituting proceedings against the book. Therefore, when in 1666 Thomas Hobbes wanted to publish a Latin translation of this book, he added three appendices. Generally, the Latin version of the work is considered more acceptable than the English original text. By studying how Hobbes deals with his materialism in these appendices, I try to show that the Latin additions are in no way a reversal of the text, but that the philosopher simply veiled more propositions, while at the same time making them more radical.

Emissions of greenhouse gases from the use of transportation fuels and electricity. Volume 2: Appendixes A--S

Energy Technology Data Exchange (ETDEWEB)

DeLuchi, M.A. [Argonne National Lab., IL (United States)]|[Univ. of California, Davis, CA (United States). Inst. of Transportation Studies

1993-11-01

This volume contains the appendices to the report on Emission of Greenhouse Gases from the Use of Transportation Fuels and Electricity. Emissions of methane, nitrous oxide, carbon monoxide, and other greenhouse gases are discussed. Sources of emission including vehicles, natural gas operations, oil production, coal mines, and power plants are covered. The various energy industries are examined in terms of greenhouse gas production and emissions. Those industries include electricity generation, transport of goods via trains, trucks, ships and pipelines, coal, natural gas and natural gas liquids, petroleum, nuclear energy, and biofuels.

Data and methods for the assessment of the risks associated with the maritime transport of radioactive materials. Results of the SeaRAM program studies. Volume 2: Appendices

International Nuclear Information System (INIS)

Sprung, J.L.; Bespalko, S.J.; Kanipe, F.L.

1998-05-01

This report describes ship accident event trees, ship collision and ship fire frequencies, representative ships and shipping practices, a model of ship penetration depths during ship collisions, a ship fire spread model, cask to environment release fractions during ship collisions and fires, and illustrative consequence calculations. This report contains the following appendices: Appendix 1 -- Representative Ships and Shipping Practices; Appendix 2 -- Input Data for Minorsky Calculations; Appendix 3 -- Port Ship Speed Distribution; and Appendix 4 -- Cask-to-Environment Release Fractions

Data and methods for the assessment of the risks associated with the maritime transport of radioactive materials: Results of the SeaRAM program studies. Volume 2 -- Appendices

Energy Technology Data Exchange (ETDEWEB)

Sprung, J.L.; Bespalko, S.J.; Kanipe, F.L. [and others

1998-05-01

This report describes ship accident event trees, ship collision and ship fire frequencies, representative ships and shipping practices, a model of ship penetration depths during ship collisions, a ship fire spread model, cask to environment release fractions during ship collisions and fires, and illustrative consequence calculations. This report contains the following appendices: Appendix 1 -- Representative Ships and Shipping Practices; Appendix 2 -- Input Data for Minorsky Calculations; Appendix 3 -- Port Ship Speed Distribution; and Appendix 4 -- Cask-to-Environment Release Fractions.

Risk of appendiceal endometriosis among women with deep-infiltrating endometriosis.

Science.gov (United States)

Moulder, Janelle K; Siedhoff, Matthew T; Melvin, Kathryn L; Jarvis, Elizabeth G; Hobbs, Kumari A; Garrett, Joanne

2017-11-01

To determine whether deep-infiltrating endometriosis (DE) carries an increased risk of appendiceal endometriosis (AppE) as compared with superficial endometriosis or no endometriosis. In a retrospective study, data were obtained by chart review of an internal database for women who underwent coincidental appendectomy during benign gynecologic surgery between July 2009 and February 2014 at a tertiary referral center in the USA. Univariate, bivariate, and regression analyses were performed. The primary exposure was surgically documented endometriosis (DE, superficial, or no endometriosis). The primary outcome was AppE. Endometriosis was diagnosed for 151 (38.2%) of 395 women; 82 (54.3%) had DE. The prevalence of AppE was 13.2% (52/395) overall; 8 (11.6%) of 69 women with superficial endometriosis and 32 (39.0%) of 82 with DE were affected. Frequency of AppE was increased among women with DE, abnormal appendix appearance, and surgical indication (all Pendometriosis, controlling for appendiceal appearance and surgical indication, and a 2.7-fold (95% CI 1.2-6.2) higher risk of AppE compared with those with superficial endometriosis. Women with DE have increased risk of AppE. Coincidental appendectomy should form part of complete endometriosis excision for these patients. © 2017 International Federation of Gynecology and Obstetrics.

International Nuclear Model. Volume 3. Program description. Appendix A-H (Part 1)

International Nuclear Information System (INIS)

Andress, D.

1985-01-01

The International Nuclear Model (INM) is a comprehensive model of the commercial nuclear power industry. It simulates economic decisions for reactor deployment and fuel management decisions based on an input set of technical, economic and scenario parameters. The technical parameters include reactor operating characteristics, fuel cycle timing and mass loss factors, and enrichment tails assays. Economic parameters include fuel cycle costs, financial data, and tax alternatives. INM has a broad range of scenario options covering, for example, process constraints, interregional activities, reprocessing, and fuel management selection. INM reports reactor deployment schedules, electricity generation, and fuel cycle requirements and costs. It also has specialized reports for extended burnup and permanent disposal. This volume contains appendices A through H including a description of subroutines and the Fortran listing of the program

Demonstration, testing, and evaluation of in situ heating of soil. Volume 1, Final report

International Nuclear Information System (INIS)

Dev, H.; Enk, J.; Jones, D.; Sabato, W.

1996-01-01

This document is a final reports in two volumes. Volume I contains the technical report and Volume II contains appendices with background information and data. In this project approximately 300 cubic yards of clayey soil containing a low concentration plume of volatile organic chemicals was heated in situ by the application of electrical energy. It was shown that as a result of heating the effective permeability of soil to air flow was increased such that in situ soil vapor extraction could be performed. The initial permeability of soil was so low that the soil gas flow rate was immeasurably small even at high vacuum levels. It was demonstrated that the mass flow rate of the volatile organic chemicals was enhanced in the recovered soil gas as a result of heating

Demonstration, testing, and evaluation of in situ heating of soil. Volume 1, Final report

Energy Technology Data Exchange (ETDEWEB)

Dev, H.; Enk, J.; Jones, D.; Sabato, W.

1996-04-05

This document is a final reports in two volumes. Volume I contains the technical report and Volume II contains appendices with background information and data. In this project approximately 300 cubic yards of clayey soil containing a low concentration plume of volatile organic chemicals was heated in situ by the application of electrical energy. It was shown that as a result of heating the effective permeability of soil to air flow was increased such that in situ soil vapor extraction could be performed. The initial permeability of soil was so low that the soil gas flow rate was immeasurably small even at high vacuum levels. It was demonstrated that the mass flow rate of the volatile organic chemicals was enhanced in the recovered soil gas as a result of heating.

Resource Conservation and Recovery Act, Part B Permit Application

International Nuclear Information System (INIS)

1991-02-01

The Waste Isolation Pilot Plant (WIPP) project was authorized by the Department of Energy National Security and Military Applications of Nuclear Energy Authorization Act of 1980 (Public Law 96-164) as a research and development facility to demonstrate the safe, environmentally sound disposal of transuranic (TRU) radioactive wastes derived from the defense activities of the United States. The WIPP facility is owned and operated by the US Department of Energy (DOE). The TRU waste to be received at WIPP consists largely of such items as laboratory glassware and utensils, tools, scrap metal, shielding, personnel protection equipment, and solidified sludges from the treatment of waste water. Approximately 60 percent of this waste is ''mixed,'' that is, it is also contaminated with hazardous waste or hazardous waste constituents as defined by the Resource Conservation and Recovery Act (RCRA) and by the New Mexico Hazardous Waste Management Regulations (HWMR-5). Therefore, emplacement of TRU mixed waste in the WIPP repository is subject to regulation under HWMR-5 and RCRA. The permit application under the Resource Conservation and Recovery Act for WIPP is divided into five volumes. This document, Volume 4, contains Appendices C3, C4, and D1--D10. These appendices cover information on environmental impacts, site characterization, geology and hydrology of the area, monitoring of the environment, compatibility of waste forms and containers, and removal of volatile organic compounds (VOC)

Analysis and evaluation of GAVE chains. Part 3 of 3. Appendices; Analyse en evaluatie van GAVE-ketens. Deel 3 van 3. Appendices

Energy Technology Data Exchange (ETDEWEB)

Bosma, W.J.P. [Arthur D. Little International, Rotterdam (Netherlands)

1999-12-01

The final report (part 2) contains the detailed findings of the analysis, evaluation, and integration of Novem GAVE options and aims at the reader who is interested in the detailed findings, as well as an overview of the results. For readers who are mainly interested in the high-level results, and are comfortable with Dutch, there is a short text summary of our results, entitled 'Analyse en evaluatie van GAVE-ketens, management summary' (part 1). These appendices is for readers who are interested in the underlying data and detailed assumptions. 70 refs.

Resource Conservation and Recovery Act, Part B Permit Application

International Nuclear Information System (INIS)

1993-01-01

This volume contains appendices for the following: Rocky Flats Plant and Idaho National Engineering Laboratory waste process information; TRUPACT-II content codes (TRUCON); TRUPACT-II chemical list; chemical compatibility analysis for Rocky Flats Plant waste forms; chemical compatibility analysis for waste forms across all sites; TRU mixed waste characterization database; hazardous constituents of Rocky Flats Transuranic waste; summary of waste components in TRU waste sampling program at INEL; TRU waste sampling program; and waste analysis data

Generating human reliability estimates using expert judgment. Volume 2. Appendices

International Nuclear Information System (INIS)

Comer, M.K.; Seaver, D.A.; Stillwell, W.G.; Gaddy, C.D.

1984-11-01

The US Nuclear Regulatory Commission is conducting a research program to determine the practicality, acceptability, and usefulness of several different methods for obtaining human reliability data and estimates that can be used in nuclear power plant probabilistic risk assessments (PRA). One method, investigated as part of this overall research program, uses expert judgment to generate human error probability (HEP) estimates and associated uncertainty bounds. The project described in this document evaluated two techniques for using expert judgment: paired comparisons and direct numerical estimation. Volume 2 provides detailed procedures for using the techniques, detailed descriptions of the analyses performed to evaluate the techniques, and HEP estimates generated as part of this project. The results of the evaluation indicate that techniques using expert judgment should be given strong consideration for use in developing HEP estimates. Judgments were shown to be consistent and to provide HEP estimates with a good degree of convergent validity. Of the two techniques tested, direct numerical estimation appears to be preferable in terms of ease of application and quality of results

Analysis of potential combustion source impacts on acid deposition using an independently derived inventory. Volume II, appendices

Energy Technology Data Exchange (ETDEWEB)

1983-12-01

This document contains 2 appendices. The first documents the methodologies used to calculate production, unit energy consumption, fuel type and emission estimates for 16 industries and 35 types of facilities utilizing direct-fired industrial combustion processes, located in 26 states (and the District of Columbia) east of the Mississippi River. As discussed in the text of this report, a U.S. total of 16 industries and 45 types of facilities utilizing direct-fired combustion processes were identified by an elimination type method that was developed based on evaluation of fuel use in industrial SIC codes 20-39 to identify pollutant sources contributing to acid rain. The final population included only plants that have direct-fired fuel consumption greater than or equal to 100 x 10/sup 9/ Btu/yr of equivalent energy consumption. The goal for this analysis was to provide at least a 1980 base year for the data. This was achieved for all of the industries and in fact, 1981 data were used for a number of the industries evaluated. The second contains an analysis of all consumption of major fossil fuels to: (1) identify all fuel usage categories, and (2) identify the kinds of combustion equipment used within each category. This analysis provides a frame of reference for the balance of the study and permits using an energy accounting methodology to quantify the degree to which the inventoried sources in individual consuming sectors are complete and representative of the total population for the sector.

Interim reliability-evaluation program: analysis of the Millstone Point Unit 1 nuclear power plant. Volume IV. Appendix B.9 through B.19 and C

International Nuclear Information System (INIS)

Curry, J.J.; Gallagher, D.W.; Modarres, M.; Radder, J.A.

1983-05-01

Appendices are presented concerning isolation condenser makeup; vapor suppression system; station air system; reactor building closed cooling water system; turbine building secondary closed water system; service water system; emergency service water system; fire protection system; emergency ac power; dc power system; event probability estimation; methodology of accident sequence quantification; and assignment of dominant sequences to release categories

Mississippi River: Study of Alternatives for Rehabilitation of Lock and Dam Number 1. Minneapolis, Minnesota. Volume 3. Appendices B-F.

Science.gov (United States)

1976-04-01

ADA34 023 MSSISSIPPI RVER: STUDOFALERNATVESOR 1/4 REHABILIATION OF LOCK AND D..U) CORPS OF ENGINEERS ST A SR P UNCLASSIFED PALM STPU DITIT AR7 / 132...AFACIFA4 Slh9qFAC,- 6 I0. "A e 6250 , 3 VW~- 41Mj,4, 4 04X, 4950 , 5 SCp * 295" , 6, 496Vs, .3502 S 00-, 55oolo,, ,e-. o’so b, Swl~.-/~o~ 41 N //Z-V...the concrete specimen. Selected portions wurc examined in immersion oils under the petrographic microscope. CONC LUSIONS River Wall, Drill Hole No. 74

Shemya AFB, Alaska 1992 IRP field investigation report. Volume 3, Appendixes B, C, and D: Final report

Energy Technology Data Exchange (ETDEWEB)

1993-02-01

The US Air Force is currently investigating 22 sites on Shemya Air Force Base (AFB) to determine if past spill and disposal activities have caused environmental damage. These investigations are being carried out under the Air Force`s Installation Restoration Program (IRP). Field investigations were performed in 1992 to obtain the information needed to assess what future actions will need to be carried out at each site. The island`s drinking water supply was also investigated. Activities completed at 10 selected sites included surface sampling to determine the lateral extent of contamination, subsurface sampling to determine the vertical extent of contamination, and the installation of well points and monitoring wells to determine the direction of groundwater flow and if the groundwater has been affected by a site. Geophysical surveys were performed at most sites to identify site boundaries and check for the presence of buried metal to be avoided during drilling activities. This report, appendices B, C, and D contains information on the following: geophysical contour maps and profile plots; human health risk assessment; and ecological risk assessment.

Historical sketches of Sandia National Laboratories nuclear field testing. Volume 1: Full discussion except for sensitive references

International Nuclear Information System (INIS)

Banister, J.R.

1994-10-01

This report contains historical sketches that cover the major activities of Sandia nuclear field testing, from early atmospheric shots until 1990. It includes a chronological overview followed by more complete discussions of atmospheric, high-altitude, underwater, cratering, and underground nuclear testing. Other activities related to nuclear testing and high-explosive tests are also described. A large number of references are cited for readers who wish to learn more about technical details. Appendices, written by several authors, provide more insight for a variety of special aspects of nuclear testing and related work. Two versions of this history were published: volume 1 has an unlimited distribution, and volume 2 has a limited distribution

Regulatory Oversight Program, July 1, 1993--March 3, 1997. Volume 2: Appendices

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-12-31

On July, 1993, a Regulatory Oversight (RO) organization was established within the US DOE, Oak Ridge Operations to provide regulatory oversight of the DOE uranium enrichment facilities leased to the United States Enrichment Corporation (USEC). The purpose of the OR program was to ensure continued plant safety, safeguards and security while the plants were transitioned to regulatory oversight by the Nuclear Regulatory Commission (NRC). Volume 2 contains copies of the documents which established the relationship between NRC, DOE, USEC, and DOL (Dept of Labor) required to facilitate regulatory oversight transition.

Regulatory Oversight Program, July 1, 1993 - March 3, 1997. Volume 2: Appendices

International Nuclear Information System (INIS)

1997-01-01

On July, 1993, a Regulatory Oversight (RO) organization was established within the US DOE, Oak Ridge Operations to provide regulatory oversight of the DOE uranium enrichment facilities leased to the United States Enrichment Corporation (USEC). The purpose of the OR program was to ensure continued plant safety, safeguards and security while the plants were transitioned to regulatory oversight by the Nuclear Regulatory Commission (NRC). Volume 2 contains copies of the documents which established the relationship between NRC, DOE, USEC, and DOL (Dept of Labor) required to facilitate regulatory oversight transition

Appendiceal hemorrhage – An uncommon cause of lower gastrointestinal bleeding

Directory of Open Access Journals (Sweden)

Ching-Chung Chiang

2011-06-01

Full Text Available Lower gastrointestinal bleeding is a common disease among elderly patients. The common sources of lower gastrointestinal bleeding include vascular disease, Crohn’s disease, neoplasms, inflammatory bowel disease, hemorrhoids, and ischemic colitis. Lower gastrointestinal bleeding arising from the appendix is an extremely rare condition. We report a case of appendiceal hemorrhage in a young male. Diagnosis was made by multidetector computerized tomography during survey for hematochezia. The patient recovered well after appendectomy. The histological finding revealed focal erosion of appendix mucosa with bleeding.

Technology, safety and costs of decommissioning a reference small mixed oxide fuel fabrication plant. Volume 2. Appendices

Energy Technology Data Exchange (ETDEWEB)

Jenkins, C. E.; Murphy, E. S.; Schneider, K. J.

1979-01-01

Volume 2 contains appendixes on small MOX fuel fabrication facility description, site description, residual radionuclide inventory estimates, decommissioning, financing, radiation dose methodology, general considerations, packaging and shipping of radioactive materials, cost assessment, and safety (JRD)

The System 80+ Standard Plant design control document. Volume 15

International Nuclear Information System (INIS)

1997-01-01

This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains all five parts of section 12 (Radiation Protection) of the ADM Design and Analysis. Topics covered are: ALARA exposures; radiation sources; radiation protection; dose assessment; and health physics program. All six parts and appendices A and B for section 13 (Conduct of Operations) of the ADM Design and Analysis are also contained in this volume. Topics covered are: organizational structure; training program; emergency planning; review and audit; plant procedures; industrial security; sabotage protection (App 13A); and vital equipment list (App 13B)

Developing maintainability for tokamak fusion power systems. Phase II report. Volume III: appendices

International Nuclear Information System (INIS)

Fuller, G.M.; Zahn, H.S.; Mantz, H.C.; Kaletta, G.R.; Waganer, L.M.; Carosella, L.A.; Conlee, J.L.

1978-11-01

This volume contains time estimate summaries to the second level of detail for scheduled or unscheduled maintenance of the first wall/blanket, some selected subsystem components and maintenance equipment. Elaboration of selected maintenance equipment functions and performance as well as conceptual designs is also included

Finite volume for three-flavour Partially Quenched Chiral Perturbation Theory through NNLO in the meson sector

International Nuclear Information System (INIS)

Bijnens, Johan; Rössler, Thomas

2015-01-01

We present a calculation of the finite volume corrections to meson masses and decay constants in three flavour Partially Quenched Chiral Perturbation Theory (PQChPT) through two-loop order in the chiral expansion for the flavour-charged (or off-diagonal) pseudoscalar mesons. The analytical results are obtained for three sea quark flavours with one, two or three different masses. We reproduce the known infinite volume results and the finite volume results in the unquenched case. The calculation has been performed using the supersymmetric formulation of PQChPT as well as with a quark flow technique. Partial analytical results can be found in the appendices. Some examples of cases relevant to lattice QCD are studied numerically. Numerical programs for all results are available as part of the CHIRON package.

Finite volume for three-flavour Partially Quenched Chiral Perturbation Theory through NNLO in the meson sector

Energy Technology Data Exchange (ETDEWEB)

Bijnens, Johan; Rössler, Thomas [Department of Astronomy and Theoretical Physics, Lund University,Sölvegatan 14A, SE 223-62 Lund (Sweden)

2015-11-16

We present a calculation of the finite volume corrections to meson masses and decay constants in three flavour Partially Quenched Chiral Perturbation Theory (PQChPT) through two-loop order in the chiral expansion for the flavour-charged (or off-diagonal) pseudoscalar mesons. The analytical results are obtained for three sea quark flavours with one, two or three different masses. We reproduce the known infinite volume results and the finite volume results in the unquenched case. The calculation has been performed using the supersymmetric formulation of PQChPT as well as with a quark flow technique. Partial analytical results can be found in the appendices. Some examples of cases relevant to lattice QCD are studied numerically. Numerical programs for all results are available as part of the CHIRON package.

Tank Vapor Characterization Project: Headspace vapor characterization of Hanford Tank 241-B-105: Results from samples collected on 07/30/96

International Nuclear Information System (INIS)

Pool, K.H.; Evans, J.C.; Thomas, B.L.

1997-01-01

This report describes the analytical results of vapor samples taken from the headspace of the waste storage tank 241-B-105 (Tank B-105) at the Hanford Site in Washington State. The results described in this report were obtained to characterize the vapors present in the tank headspace and to support safety evaluations and tank farm operations. The results include air concentrations of selected inorganic and organic analytes and grouped compounds from samples obtained by Westinghouse Hanford Company (WHC) and provided for analysis to Pacific Northwest National Laboratory (PNNL). Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Analyte concentrations were based on analytical results and, where appropriate, sample volumes provided by WHC. A summary of the inorganic analytes, permanent gases, and total non-methane organic compounds is listed in Table S.1. The three highest concentration analytes detected in SUMMA trademark canister and triple sorbent trap samples are also listed in Table S.1. Detailed descriptions of the analytical results appear in the appendices

Analysis of core damage frequency, Surry, Unit 1 internal events appendices

International Nuclear Information System (INIS)

Bertucio, R.C.; Julius, J.A.; Cramond, W.R.

1990-04-01

This document contains the appendices for the accident sequence analyses of internally initiated events for the Surry Nuclear Station, Unit 1. This is one of the five plant analyses conducted as part of the NUREG-1150 effort by the Nuclear Regulatory Commission. NUREG-1150 documents the risk of a selected group of nuclear power plants. The work performed is an extensive reanalysis of that published in November 1986 as NUREG/CR-4450, Volume 3. It addresses comments from numerous reviewers and significant changes to the plant systems and procedures made since the first report. The uncertainty analysis and presentation of results are also much improved. The context and detail of this report are directed toward PRA practitioners who need to know how the work was performed and the details for use in further studies. The mean core damage frequency at Surry was calculated to be 4.0E-5 per year, with a 95% upper bound of 1.3E-4 and 5% lower bound of 6.8E-6 per year. Station blackout type accidents (loss of all AC power) were the largest contributors to the core damage frequency, accounting for approximately 68% of the total. The next type of dominant contributors were Loss of Coolant Accidents (LOCAs). These sequences account for 15% of core damage frequency. No other type of sequence accounts for more than 10% of core damage frequency

Resource Conservation and Recovery Act Part B permit application [for the Waste Isolation Pilot Plant (WIPP)]. Volume 7: Revision 1.0

Energy Technology Data Exchange (ETDEWEB)

1992-07-01

This permit application (Vol. 7) for the WIPP facility contains appendices related to the following information: Ground water protection; personnel; solid waste management; and memorandums concerning environmental protection standards.

Transformations of inorganic coal constituents in combustion systems. Volume 3, Appendices: Final report

Energy Technology Data Exchange (ETDEWEB)

Helble, J.J. [ed.; Srinivasachar, S.; Wilemski, G.; Boni, A.A. [PSI Technology Co., Andover, MA (United States); Kang, Shim-Gyoo; Sarofim, A.F.; Graham, K.A.; Beer, J.M. [Massachusetts Inst. of Tech., Cambridge, MA (United States); Peterson, T.W.; Wendt, O.L.; Gallagher, N.B.; Bool, L. [Arizona Univ., Tucson, AZ (United States); Huggins, F.E.; Huffman, G.P.; Shah, N.; Shah, A. [Kentucky Univ., Lexington, KY (United States)

1992-11-01

This report contains the computer codes developed for the coal combustion project. In Subsection B.1 the FORTRAN code developed for the percolative fragmentation model (or the discrete model, since a char is expressed as a collection of discrete elements in a discrete space) is presented. In Subsection B.2 the code for the continuum model (thus named because mineral inclusions are distributed in a continuum space) is presented. A stereological model code developed to obtain the pore size distribution from a two-dimensional data is presented in Subsection B.3.

Construction and operation of the Spallation Neutron Source: Draft environmental impact statement. Volume 2

International Nuclear Information System (INIS)

1998-12-01

DOE proposes to construct and operate a state-of-the-art, short-pulsed spallation neutron source comprised of an ion source, a linear accelerator, a proton accumulator ring, and an experiment building containing a liquid mercury target and a suite of neutron scattering instrumentation. The proposed Spallation Neutron Source would be designed to operate at a proton beam power of 1 megawatt. The design would accommodate future upgrades to a peak operating power of 4 megawatts. These upgrades may include construction of a second proton accumulation ring and a second target. Volume 1 of this document analyzes the potential environmental impacts from the proposed action and the alternatives. The analysis assumes a facility operating at a power of 1 MW and 4 MW over the life of the facility. The two primary alternatives analyzed in this EIS are: the proposed action (to proceed with building the Spallation Neutron Source) and the No-Action Alternative. This volume contains the following appendices: (A) SNS accident source terms for EIS input; (B) Reports on the selection of alternative sites for the SNS; (C) Letters of consultation on protected species and cultural resources; (D) Ecological resource survey reports and summaries; (E) Descriptions of ORNL research projects in the Walker Branch Watershed; (F) Atmospheric dispersion and dose calculations for normal and accident conditions; (G) Projected air quality modeling effects at NOAA's Walker Branch Monitoring Tower

Verification and validation guidelines for high integrity systems. Volume 1

Energy Technology Data Exchange (ETDEWEB)

Hecht, H.; Hecht, M.; Dinsmore, G.; Hecht, S.; Tang, D. [SoHaR, Inc., Beverly Hills, CA (United States)

1995-03-01

High integrity systems include all protective (safety and mitigation) systems for nuclear power plants, and also systems for which comparable reliability requirements exist in other fields, such as in the process industries, in air traffic control, and in patient monitoring and other medical systems. Verification aims at determining that each stage in the software development completely and correctly implements requirements that were established in a preceding phase, while validation determines that the overall performance of a computer system completely and correctly meets system requirements. Volume I of the report reviews existing classifications for high integrity systems and for the types of errors that may be encountered, and makes recommendations for verification and validation procedures, based on assumptions about the environment in which these procedures will be conducted. The final chapter of Volume I deals with a framework for standards in this field. Volume II contains appendices dealing with specific methodologies for system classification, for dependability evaluation, and for two software tools that can automate otherwise very labor intensive verification and validation activities.

Verification and validation guidelines for high integrity systems. Volume 1

International Nuclear Information System (INIS)

Hecht, H.; Hecht, M.; Dinsmore, G.; Hecht, S.; Tang, D.

1995-03-01

High integrity systems include all protective (safety and mitigation) systems for nuclear power plants, and also systems for which comparable reliability requirements exist in other fields, such as in the process industries, in air traffic control, and in patient monitoring and other medical systems. Verification aims at determining that each stage in the software development completely and correctly implements requirements that were established in a preceding phase, while validation determines that the overall performance of a computer system completely and correctly meets system requirements. Volume I of the report reviews existing classifications for high integrity systems and for the types of errors that may be encountered, and makes recommendations for verification and validation procedures, based on assumptions about the environment in which these procedures will be conducted. The final chapter of Volume I deals with a framework for standards in this field. Volume II contains appendices dealing with specific methodologies for system classification, for dependability evaluation, and for two software tools that can automate otherwise very labor intensive verification and validation activities

Ductile fracture toughness of modified A 302 grade B plate materials. Volume 2

International Nuclear Information System (INIS)

McCabe, D.E.; Manneschmidt, E.T.; Swain, R.L.

1997-02-01

The objective of this work was to develop ductile fracture toughness data in the form of J-R curves for modified A 302 grade B plate materials typical of those used in fabricating reactor pressure vessels. A previous experimental study at Materials Engineering Associates (MEA) on one particular heat of A 302 grade B plate showed decreasing J-R curves with increased specimen thickness. This characteristic has not been observed in numerous tests made on the more recent production materials of A 533 grade B and A 508 class 2 pressure vessel steels. It was unknown if the departure from norm for the MEA material was a generic characteristic for all heats of A 302 grade B steels or just unique to that one particular plate. Seven heats of modified A 302 grade B steel and one heat of vintage A 533 grade B steel were provided to this project by the General Electric Company of San Jose, California. All plates were tested for chemical content, tensile properties, Charpy transition temperature curves, drop-weight nil-ductility transition (NDT) temperature, and J-R curves. Tensile tests were made in the three principal orientations and at four temperatures, ranging from room temperature to 550 degrees F (288 degrees C). Charpy V-notch transition temperature curves were obtained in longitudinal, transverse, and short transverse orientations. J-R curves were made using four specimen sizes (1/2T, IT, 2T, and 4T). None of the seven heats of modified A 302 grade showed size effects of any consequence on the J-R curve behavior. Crack orientation effects were present, but none were severe enough to be reported as atypical. A test temperature increase from 180 to 550 degrees F (82 to 288 degrees C) produced the usual loss in J-R curve fracture toughness. Generic J-R curves and mathematical curve fits to the same were generated to represent each heat of material. This volume is a compilation of all data developed

Master plan study - District heating Sillamaee municipality. Estonia. Final report. Appendices for chapter 9

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-03-01

The appendices to the final report on the master plan study on district heating in the municipality in Estonia, chapter nine, gives data related to general economic assumptions for financial and economic calculations, fuel consumption, financing, prices, fuel consumption. (ARW)

76 FR 64112 - Privacy Act of 1974; Privacy Act System of Records Appendices

Science.gov (United States)

2011-10-17

... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice (11-091)] Privacy Act of 1974; Privacy Act...: Revisions of NASA Appendices to Privacy Act System of Records. SUMMARY: Notice is hereby given that NASA is... Privacy Act of 1974. This notice publishes those amendments as set forth below under the caption...

Guidance and Control Software Project Data - Volume 4: Configuration Management and Quality Assurance Documents

Science.gov (United States)

Hayhurst, Kelly J. (Editor)

2008-01-01

The Guidance and Control Software (GCS) project was the last in a series of software reliability studies conducted at Langley Research Center between 1977 and 1994. The technical results of the GCS project were recorded after the experiment was completed. Some of the support documentation produced as part of the experiment, however, is serving an unexpected role far beyond its original project context. Some of the software used as part of the GCS project was developed to conform to the RTCA/DO-178B software standard, "Software Considerations in Airborne Systems and Equipment Certification," used in the civil aviation industry. That standard requires extensive documentation throughout the software development life cycle, including plans, software requirements, design and source code, verification cases and results, and configuration management and quality control data. The project documentation that includes this information is open for public scrutiny without the legal or safety implications associated with comparable data from an avionics manufacturer. This public availability has afforded an opportunity to use the GCS project documents for DO-178B training. This report provides a brief overview of the GCS project, describes the 4-volume set of documents and the role they are playing in training, and includes configuration management and quality assurance documents from the GCS project. Volume 4 contains six appendices: A. Software Accomplishment Summary for the Guidance and Control Software Project; B. Software Configuration Index for the Guidance and Control Software Project; C. Configuration Management Records for the Guidance and Control Software Project; D. Software Quality Assurance Records for the Guidance and Control Software Project; E. Problem Report for the Pluto Implementation of the Guidance and Control Software Project; and F. Support Documentation Change Reports for the Guidance and Control Software Project.

Plasma diagnostics package. Volume 2: Spacelab 2 section. Part B: Thesis projects. Final science report

International Nuclear Information System (INIS)

Pickett, J.S.; Frank, L.A.; Kurth, W.S.

1988-06-01

This volume (2), which consists of two parts (A and B), of the Plasma Diagnostics Package (PDP) Final Science Report contains a summary of all of the data reduction and scientific analyses which were performed using PDP data obtained on STS-51F as a part of the Spacelab 2 (SL-2) payload. This work was performed during the period of launch, July 29, 1985, through June 30, 1988. During this period the primary data reduction effort consisted of processing summary plots of the data received by 12 of the 14 instruments located on the PDP and submitting these data to the National Space Science Data Center (NSSDC). Three Master's and three Ph.D. theses were written using PDP instrumentation data. These theses are listed in Volume 2, Part B

Worldwide status of energy standards for buildings: Appendices

Energy Technology Data Exchange (ETDEWEB)

Janda, K.B.; Busch, J.F.

1993-02-01

This informal survey was designed to gain information about the worldwide status of energy efficiency standards for buildings, particularly non-residential buildings such as offices, schools, and hotels. The project has three goals: 1. To understand and learn from the experience of countries with existing building energy standards; 2. To locate areas where these lessons might be applied and energy standards might be effectively proposed and developed; and 3. To share the information gathered with all participating countries. These appendices include the survey cover letter, the survey, and the details of selected energy standards in 35 countries, thus providing supporting material for the authors` article of the same title.

Ocean Optics Protocols for Satellite Ocean Color Sensor Validation, Revision 4, Volume IV: Inherent Optical Properties: Instruments, Characterizations, Field Measurements and Data Analysis Protocols

Science.gov (United States)

Mueller, J. L.; Fargion, G. S.; McClain, C. R. (Editor); Pegau, S.; Zanefeld, J. R. V.; Mitchell, B. G.; Kahru, M.; Wieland, J.; Stramska, M.

2003-01-01

This document stipulates protocols for measuring bio-optical and radiometric data for the Sensor Intercomparision and Merger for Biological and Interdisciplinary Oceanic Studies (SIMBIOS) Project activities and algorithm development. The document is organized into 6 separate volumes as Ocean Optics Protocols for Satellite Ocean Color Sensor Validation, Revision 4. Volume I: Introduction, Background, and Conventions; Volume II: Instrument Specifications, Characterization and Calibration; Volume III: Radiometric Measurements and Data Analysis Methods; Volume IV: Inherent Optical Properties: Instruments, Characterization, Field Measurements and Data Analysis Protocols; Volume V: Biogeochemical and Bio-Optical Measurements and Data Analysis Methods; Volume VI: Special Topics in Ocean Optics Protocols and Appendices. The earlier version of Ocean Optics Protocols for Satellite Ocean Color Sensor Validation, Revision 3 is entirely superseded by the six volumes of Revision 4 listed above.

Resource Conservation and Recovery Act: Part B, Permit application

International Nuclear Information System (INIS)

1991-02-01

The Waste Isolation Pilot Plant (WIPP) project was authorized by the Department of Energy National Security and Military Applications of Nuclear Energy Authorization Act of 1980 (Public Law 96-164) as a research and development facility to demonstrate the safe, environmentally sound disposal of transuranic (TRU) radioactive wastes derived from the defense activities of the United States. The WIPP facility is owned and operated by the US Department of Energy (DOE). The TRU waste to be received at WIPP consists largely of such items as laboratory glassware and utensils, tools, scrap metal, shielding, personnel protection equipment, and solidified sludges from the treatment of waste water. Approximately 60 percent of this waste is ''mixed,'' that is, it is also contaminated with hazardous waste or hazardous waste constituents as defined by the Resource Conservation and Recovery Act (RCRA) and by the New Mexico Hazardous Waste Management Regulations (HWMR-5). Therefore, emplacement of TRU mixed waste in the WIPP repository is subject to regulation under HWMR-5 and RCRA. The permit application under the Resource Conservation and Recovery Act for WIPP is divided into five volumes. This document, Volume 5, contains Appendices E1, H1, I1--3, K1, K2, and L1. These appendices cover a RCRA ground water monitoring waiver, a list of job titles, the operational closure plan, the waste retrieval plan for wastes placed during the test phase, and listings of agreements between WIPP, DOE, and various state and federal agencies. 91 refs., 21 figs., 3 tabs

Oak Ridge National Laboratory Technology Logic Diagram. Volume 1, Technology Evaluation: Part B, Remedial Action

Energy Technology Data Exchange (ETDEWEB)

1993-09-01

The Oak Ridge National Laboratory Technology Logic Diagram (TLD) was developed to provide a decision-support tool that relates environmental restoration (ER) and waste management (WM) problems at Oak Ridge National Laboratory (ORNL) to potential technologies that can remediate these problems. The TLD identifies the research, development, demonstration, testing, and evaluation needed to develop these technologies to a state that allows technology transfer and application to decontamination and decommissioning (D&D), remedial action (RA), and WM activities. The TLD consists of three fundamentally separate volumes: Vol. 1 (Technology Evaluation), Vol. 2 (Technology Logic Diagram), and Vol. 3 (Technology Evaluation Data Sheets). Part A of Vols. 1 and 2 focuses on D&D. Part B of Vols. 1 and 2 focuses on RA of contaminated facilities. Part C of Vols. 1 and 2 focuses on WM. Each part of Vol. 1 contains an overview of the TLD, an explanation of the program-specific responsibilities, a review of identified technologies, and the ranking os remedial technologies. Volume 2 (Pts. A, B, and C) contains the logic linkages among EM goals, environmental problems, and the various technologies that have the potential to solve these problems. Volume 3 (Pts. A, B, and C) contains the TLD data sheets. The focus of Vol. 1, Pt. B, is RA, and it has been divided into six chapters. The first chapter is an introduction, which defines problems specific to the ER Program for ORNL. Chapter 2 provides a general overview of the TLD. Chapters 3 through 5 are organized into necessary subelement categories: RA, characterization, and robotics and automation. The final chapter contains regulatory compliance information concerning RA.

Altitude Acclimatization and Blood Volume: Effects of Exogenous Erythrocyte Volume Expansion

National Research Council Canada - National Science Library

Sawka, M

1996-01-01

...: (a) altitude acclimatization effects on erythrocyte volume and plasma volume; (b) if exogenous erythrocyte volume expansion alters subsequent erythrocyte volume and plasma volume adaptations; (c...

14 CFR Appendix A to Part 147 - Curriculum Requirements

Science.gov (United States)

2010-01-01

...) SCHOOLS AND OTHER CERTIFICATED AGENCIES AVIATION MAINTENANCE TECHNICIAN SCHOOLS Pt. 147, App. A Appendix A... must be taught, as outlined in appendices B, C, and D. (a) Definitions. As used in appendices B, C, and... application. (3) Level 3 requires: (i) Knowledge of general principles, and performance of a high degree of...

Draft no-migration variance petition. Volume 7, Appendices: SUM, SURV, VOC, WAP

International Nuclear Information System (INIS)

1995-01-01

The Department of Energy is responsible for the disposition of transuranic (TRU) waste generated by national defense-related activities. Approximately 2,6 million cubic feet of these waste have been generated and are stored at various facilities across the country. The Waste Isolation Pilot Plant (WIPP), was sited and constructed to meet stringent disposal requirements. In order to permanently dispose of TRU waste, the DOE has elected to petition the US EPA for a variance from the Land Disposal Restrictions of RCRA. This document fulfills the reporting requirements for the petition. This report is volume 7 of the petition which presents details about the waste analysis plan for WIPP. VOC screening methodologies; and a summary of the site characterization studies conducted from 1983 through 1987 at WIPP

Preliminary conceptual design study of the RIGGATRON approach to fusion power. Appendices P--T

International Nuclear Information System (INIS)

1978-01-01

The following appendices are included: (1) background information on high strength materials; (2) parametric systems analysis and economic studies; (3) RIGGATRON plants for materials irradiation testing; (4) RIGGATRON recycling model and cost; and (5) impact analysis of the commerical application of RIGGATRON fusion power concept

Final safety analysis report for the Galileo mission: Volume 3 (Book 2), Nuclear risk analysis document: Appendices: Revision 1

Energy Technology Data Exchange (ETDEWEB)

1989-01-25

It is the purpose of the NRAD to provide an analysis of the range of potential consequences of accidents which have been identified that are associated with the launching and deployment of the Galileo mission spacecraft. The specific consequences analyzed are those associated with the possible release of radioactive material (fuel) of the Radioisotope Thermoelectric Generators (RTGs). They are in terms of radiation doses to people and areas of deposition of radioactive material. These consequence analyses can be used in several ways. One way is to identify the potential range of consequences which might have to be dealt with if there were to be an accident with a release of fuel, so as to assure that, given such an accident, the health and safety of the public will be reasonably protected. Another use of the information, in conjunction with accident and release probabilities, is to estimate the risks associated with the mission. That is, most space launches occur without incident. Given an accident, the most probable result relative to the RTGs is complete containment of the radioactive material. Only a small fraction of accidents might result in a release of fuel and subsequent radiological consequences. The combination of probability with consequence is risk, which can be compared to other human and societal risks to assure that no undue risks are implied by undertaking the mission. Book 2 contains eight appendices.

Resource Conservation and Recovery Act, Part B permit application

International Nuclear Information System (INIS)

1993-01-01

This volume contains appendices D4 through D17 which cover the following: Waste Isolation Pilot Plant site environmental report; ecological monitoring program at the Waste Isolation Pilot Plant; site characterization; regional and site geology and hydrology; general geology; dissolution features; ground water hydrology; typical carbon sorption bed efficiency; VOC monitoring plan for bin-room tests; chemical compatibility analysis of waste forms and container materials; probable maximum precipitation; WHIP supplementary roof support system room 1, panel 1; and corrosion risk assessment of the Waste Isolation Pilot Plant ''humid'' test bins

New York City School Survey 2008-2010: Assessing the Reliability and Validity of a Progress Report Measure. Technical Appendices

Science.gov (United States)

Nathanson, Lori; Cole, Rachel; Kemple, James J.; Lent, Jessica; McCormick, Meghan; Segeritz, Micha

2013-01-01

The Research Alliance for New York City Schools examined Department of Education (DOE) School Survey data from 2008-2010 to better understand the richness and complexities of the information elicited by the Survey from parents, students, and teachers. This document provides the appendices to the technical report "New York City School Survey…

Analysis of core damage frequency: Peach Bottom, Unit 2 internal events appendices

International Nuclear Information System (INIS)

Kolaczkowski, A.M.; Cramond, W.R.; Sype, T.T.; Maloney, K.J.; Wheeler, T.A.; Daniel, S.L.

1989-08-01

This document contains the appendices for the accident sequence analysis of internally initiated events for the Peach Bottom, Unit 2 Nuclear Power Plant. This is one of the five plant analyses conducted as part of the NUREG-1150 effort for the Nuclear Regulatory Commission. The work performed and described here is an extensive reanalysis of that published in October 1986 as NUREG/CR-4550, Volume 4. It addresses comments from numerous reviewers and significant changes to the plant systems and procedures made since the first report. The uncertainty analysis and presentation of results are also much improved, and considerable effort was expended on an improved analysis of loss of offsite power. The content and detail of this report is directed toward PRA practitioners who need to know how the work was done and the details for use in further studies. The mean core damage frequency is 4.5E-6 with 5% and 95% uncertainty bounds of 3.5E-7 and 1.3E-5, respectively. Station blackout type accidents (loss of all ac power) contributed about 46% of the core damage frequency with Anticipated Transient Without Scram (ATWS) accidents contributing another 42%. The numerical results are driven by loss of offsite power, transients with the power conversion system initially available operator errors, and mechanical failure to scram. 13 refs., 345 figs., 171 tabs

On 'light' fermions and proton stability in 'big divisor' D3/D7 large volume compactifications

International Nuclear Information System (INIS)

Misra, Aalok; Shukla, Pramod

2011-01-01

Building on our earlier work (Misra and Shukla, Nucl. Phys. B 827:112, 2010; Phys. Lett. B 685:347-352, 2010), we show the possibility of generating ''light'' fermion mass scales of MeV-GeV range (possibly related to the first two generations of quarks/leptons) as well as eV (possibly related to first two generations of neutrinos) in type IIB string theory compactified on Swiss-Cheese orientifolds in the presence of a mobile space-time filling D3-brane restricted to (in principle) stacks of fluxed D7-branes wrapping the ''big'' divisor Σ B . This part of the paper is an expanded version of the latter half of Sect. 3 of a published short invited review (Misra, Mod. Phys. Lett. A 26:1, 2011) written by one of the authors [AM ]. Further, we also show that there are no SUSY GUT-type dimension-five operators corresponding to proton decay, and we estimate the proton lifetime from a SUSY GUT-type four-fermion dimension-six operator to be 10 61 years. Based on GLSM calculations in (Misra and Shukla, Nucl. Phys. B 827:112, 2010) for obtaining the geometric Kaehler potential for the ''big divisor,'' using further the Donaldson's algorithm, we also briefly discuss in the first of the two appendices the metric for the Swiss-Cheese Calabi-Yau used, which we obtain and which becomes Ricci flat in the large-volume limit. (orig.)

On `light' fermions and proton stability in `big divisor' D3/ D7 large volume compactifications

Science.gov (United States)

Misra, Aalok; Shukla, Pramod

2011-06-01

Building on our earlier work (Misra and Shukla, Nucl. Phys. B 827:112, 2010; Phys. Lett. B 685:347-352, 2010), we show the possibility of generating "light" fermion mass scales of MeV-GeV range (possibly related to the first two generations of quarks/leptons) as well as eV (possibly related to first two generations of neutrinos) in type IIB string theory compactified on Swiss-Cheese orientifolds in the presence of a mobile space-time filling D3-brane restricted to (in principle) stacks of fluxed D7-branes wrapping the "big" divisor Σ B . This part of the paper is an expanded version of the latter half of Sect. 3 of a published short invited review (Misra, Mod. Phys. Lett. A 26:1, 2011) written by one of the authors [AM]. Further, we also show that there are no SUSY GUT-type dimension-five operators corresponding to proton decay, and we estimate the proton lifetime from a SUSY GUT-type four-fermion dimension-six operator to be 1061 years. Based on GLSM calculations in (Misra and Shukla, Nucl. Phys. B 827:112, 2010) for obtaining the geometric Kähler potential for the "big divisor," using further the Donaldson's algorithm, we also briefly discuss in the first of the two appendices the metric for the Swiss-Cheese Calabi-Yau used, which we obtain and which becomes Ricci flat in the large-volume limit.

Replacement Nuclear Research Reactor: Draft Environmental Impact Statement. Vol. 2. Appendices

International Nuclear Information System (INIS)

1998-07-01

The appendices contains additional relevant information on: Environment Australia EIS Guidelines, composition of the Study Team, Consultation Activities and Resuits, Relevant Legislation and Regulatory Requirements, Exampies of Multi-Purpose Research Reactors, Impacts of Radioactive Emissions and Wastes Generated at Lucas Heights Science and Technology Centre, Technical Analysis of the Reference Accident, Flora and Fauna Species Lists, Summary of Environmental Commitments and an Outline of the Construction Environmental Management Plan Construction Environmental Management Plan

The environmental survey manual: Appendices E, F, G, H, I, J, and K

International Nuclear Information System (INIS)

1987-08-01

Appendices E, F, G, H, I, J and K of the Environmental Survey Manual address the following topics: Field Sampling Protocols and Guidance; Guidelines for Preparation of Quality Assurance Plans; Decontamination Guidance; Data Management and Analysis; Sample and Document Management; Health and Safety Guidance for Sampling and Analysis Teams; Documents for Sampling and Analysis Program

[Appendiceal abscess in the third gestational trimester of pregnancy, complications pre and postoperatively].

Science.gov (United States)

Cyrkowicz, A; Cibor, Z; Słowińska-Zabówka, M; Kisiel, W; Oleksy, P; Orczyk, K; Bajorek, M; Kwiek, G

1996-01-01

Delayed surgical intervention connected with misdiagnosis of preterm labour and urinary tract infection caused in gravida 3 in 34th gestational week appendiceal abscess, septic shock, stillbirth by cesarean section, necessity of hysterectomy, recidivism of multi peritoneal and pleural abscesses. Although the patient was rescued the retrospective pro memoria considerations of our procedure are regarded.

Final Environmental Impact Statement on 10 CFR Part 61 licensing requirements for land disposal of radioactive waste. Summary and main report

International Nuclear Information System (INIS)

1982-11-01

The three-volume final environmental impact statement (FEIS) is prepared to guide and support publication of a final regulation, 10 CFR Part 61, for the land disposal of low-level radioactive waste. The FEIS is prepared in response to public comments received on the draft environmental impact statement (DEIS) on the proposed Part 61 regulation. The DEIS was published in September 1981 as NUREG-0782. Public comments received on the proposed Part 61 regulation separate from the DEIS are also considered in the FEIS. The FEIS is not a rewritten version of the DEIS, which contains an exhaustive and detailed analysis of alternatives, but rather references the DEIS and presents the final decision bases and conclusions (costs and impacts) which are reflected in the Part 61 requirements. Four cases are specifically considered in the FEIS representing the following: past disposal practice, existing disposal practice, Part 61 requirements, and an upper bound example. The Summary and Main Report are contained in Volume 1. Volume 2 consists of Appendices A - Staff Analysis of Public Comments on the DEIS for 10 CFR Part 61, and Appendices B - Staff Analysis of Public Comments on Proposed 10 CFR Part 61 Rulemaking. Volume 3 contains Appendices C-F, entitled as follows: Appendix C - Revisions to Impact Analysis Methodology, Appendix D - Computer Codes Used for FEIS Calculations, Appendix E - Errata for the DEIS for 10 CFR Part 61 and last, Appendix F - Final Rule and Supplementary Information

Final Environmental Impact Statement on 10 CFR Part 61 licensing requirements for land disposal of radioactive waste

International Nuclear Information System (INIS)

1982-11-01

The three-volume final environmental impact statement (FEIS) is prepared to guide and support publication of a final regulation, 10 CFR Part 61, for the land disposal of low-level radioactive waste. The FEIS is prepared in response to public comments received on the draft environmental impact statement (DEIS) on the proposed Part 61 regulation. The DEIS was published in September 1981 as NUREG-0782. Public comments received on the proposed Part 61 regulation separate from the DEIS are also considered in the FEIS. The FEIS is not a rewritten version of the DEIS, which contains an exhaustive and detailed analysis of alternatives, but rather references the DEIS and presents the final decision bases and conclusions (costs and impacts) which are reflected in the Part 61 requirements. Four cases are specifically considered in the FEIS representing the following: past disposal practice, existing disposal practice, Part 61 requirements, and an upper bound example. The Summary and Main Report are contained in Volume 1. Volume 2 consists of Appendices A - Staff Analysis of Public Comments on the DEIS for 10 CFR Part 61, and Appendices B - Staff Analysis of Public Comments on Proposed 10 CFR Part 61 Rulemaking. Volume 3 contains Appendices C-F, entitled as follows: Appendix C - Revisions to Impact Analysis Methodology, Appendix D - Computer Codes Used for FEIS Calculations, Appendix E - Errata for the DEIS for 10 CFR Part 61 and last, Appendix F - Final Rule and Supplementary Information

Department of Defense Materiel Distribution System Study. Volume 3, Book 2. Appendices A, B and C

Science.gov (United States)

1978-07-01

DODMDS Product Group Generic Commodity Group/ Number Product Group Description Weapons and Fire Control 101 ana 11 Arras 102 Guns Over 75 mm...Major Components 104 Arms and Fire Control-Parts 121 Fire Control-Reparables Federal Supply Groups or Classes 1005R, 1010R 1015-1095R 1005-1095C...Floor Tow- Conveyor Overheac Monorail Document Conveyoi Pallet Loader Auto- mated Storage Jetrleval Ele- Syeteml vator Guided Elec

Recovery of Navy distillate fuel from reclaimed product. Volume II. Literature review

Energy Technology Data Exchange (ETDEWEB)

Brinkman, D.W.; Whisman, M.L.

1984-11-01

In an effort to assist the Navy to better utilize its waste hydrocarbons, NIPER, with support from the US Department of Energy, is conducting research designed to ultimately develop a practical technique for converting Reclaimed Product (RP) into specification Naval Distillate Fuel (F-76). This first phase of the project was focused on reviewing the literature and available information from equipment manufacturers. The literature survey has been carefully culled for methodology applicable to the conversion of RP into diesel fuel suitable for Navy use. Based upon the results of this study, a second phase has been developed and outlined in which experiments will be performed to determine the most practical recycling technologies. It is realized that the final selection of one particular technology may be site-specific due to vast differences in RP volume and available facilities. A final phase, if funded, would involve full-scale testing of one of the recommended techniques at a refueling depot. The Phase I investigations are published in two volumes. Volume 1, Technical Discussion, includes the narrative and Appendices I and II. Appendix III, a detailed Literature Review, includes both a narrative portion and an annotated bibliography containing about 800 references and abstracts. This appendix, because of its volume, has been published separately as Volume 2.

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.

Assessment of the Public Health impact from the accidental release of UF6 at the Sequoyah Fuels Corporation Facility at Gore, Oklahoma (Docket No. 40-8027). Volume 2

International Nuclear Information System (INIS)

1986-03-01

Following the accidental release of UF 6 from the Sequoyah Fuels Facility on January 4, 1986, an Ad Hoc Interagency Public Health Assessment Task Force was established. The Task Force consists of technical staff members from various agencies who have prepared this assessment of the public health impact associated with the accidental release. Volume 2 of the report contains Appendices which provide more detailed information used in the assessment and support the discussion in Volume 1

AGARD Bulletin: Meetings - Publications - Membership.

Science.gov (United States)

1982-01-01

onde de choc ou de bord de fuite, la situation est bien avanc~e en &coulement bidimensionnel stationnaire non ddcoll., avec approximation potentielle...targets. The study is presented in two volumes, Volume I is the Executive Summary and Volume 2 contains the Main Report and Appendices. This Study was...presented in two volumes, Volume I is the Executive Summary and Volume 2 contains the Main Report and Appendices. This Study was conducted in response to

APS 6BM-B Large Volume High Pressure Beamline: A Workhorse for Rock and Mineral Physics

Science.gov (United States)

Chen, H.; Whitaker, M. L.; Baldwin, K. J.; Huebsch, W. R.; Vaughan, M. T.; Weidner, D. J.

2017-12-01

With the inheritance of decades of technical innovations at the NSLS X17B2 Beamline, APS 6BM-B Beamline was established in 2015 and is a dedicated beamline for synchrotron-based large volume high pressure research in earth sciences, especially rock and mineral physics. Currently a 250-ton hydraulic press equipped with a D-DIA module is installed and a Rotational Drickamer Apparatus from Yale University is hosted every cycle, covering a pressure range from crust to lower mantle. 6BM-B operates in white beam mode with an effective energy range of 20-100 keV. Energy dispersive X-ray diffraction data is collected using a 10-element solid state Ge array detector arranged in a circular geometry to allow for the real time assessment of stress. Direct radiographic imaging using Prosillica CCD camera and scintillating YAG crystals yields sample strain and strain rate. In addition to applications in phase transitions, equation of states measurements, sound velocity measurements, this setup is ideal for studies of steady state and dynamic deformation process. In this presentation, technical features and strengths of 6BM-B will be discussed. Most recent progress and science highlights of our user community will be showcased.

Development of the NRC`s Human Performance Investigation Process (HPIP). Volume 2, Investigators`s Manual

Energy Technology Data Exchange (ETDEWEB)

Paradies, M.; Unger, L. [System Improvements, Inc., Knoxville, TN (United States); Haas, P.; Terranova, M. [Concord Associates, Inc., Knoxville, TN (United States)

1993-10-01

The three volumes of this report detail a standard investigation process for use by US Nuclear Regulatory Commission (NRC) personnel when investigating human performance related events at nuclear power plants. The process, called the Human Performance Investigation Process (HPIP), was developed to meet the special needs of NRC personnel, especially NRC resident and regional inspectors. HPIP is a systematic investigation process combining current procedures and field practices, expert experience, NRC human performance research, and applicable investigation techniques. The process is easy to learn and helps NRC personnel perform better field investigations of the root causes of human performance problems. The human performance data gathered through such investigations provides a better understanding of the human performance issues that cause event at nuclear power plants. This document, Volume II, is a field manual for use by investigators when performing event investigations. Volume II includes the HPIP Procedure, the HPIP Modules, and Appendices that provide extensive documentation of each investigation technique.

Oak Ridge National Laboratory Technology Logic Diagram. Volume 2, Technology Logic Diagram: Part B, Remedial Action

Energy Technology Data Exchange (ETDEWEB)

1993-09-01

The Oak Ridge National Laboratory Technology Logic Diagram (TLD) was developed to provide a decision support tool that relates environmental restoration (ER) and waste management (WM) problems at Oak Ridge National Laboratory (ORNL) to potential technologies that can remediate these problems. The TLD identifies the research, development, demonstration, testing, and evaluation needed to develop these technologies to a state that allows technology transfer and application to decontamination and decommissioning (D&D), remedial action (RA), and WM activities. The TLD consists of three fundamentally separate volumes: Vol. 1 (Technology Evaluation), Vol. 2 (Technology Logic Diagram), and Vol. 3 (Technology Evaluation Data Sheets). Part A of Vols. 1. and 2 focuses on D&D. Part B of Vols. 1 and 2 focuses on the RA of contaminated facilities. Part C of Vols. 1 and 2 focuses on WM. Each part of Vol. 1 contains an overview of the TLD, an explanation of the program-specific responsibilities, a review of identified technologies, and the rankings of remedial technologies. Volume 2 (Pts. A, B, and C) contains the logic linkages among EM goals, environmental problems, and the various technologies that have the potential to solve these problems. Volume 3 (Pts. A, B, and C) contains the TLD data sheets. Remedial action is the focus of Vol. 2, Pt. B, which has been divided into the three necessary subelements of the RA: characterization, RA, and robotics and automation. Each of these sections address general ORNL problems, which are then broken down by problem area/constituents and linked to potential remedial technologies. The diagrams also contain summary information about a technology`s status, its science and technology needs, and its implementation needs.

Oak Ridge National Laboratory Technology Logic Diagram. Volume 3, Technology evaluation data sheets: Part B, Dismantlement, Remedial action

Energy Technology Data Exchange (ETDEWEB)

1993-09-01

The Oak Ridge National Laboratory Technology Logic Diagram (TLD) was developed to provide a decision support tool that relates environmental restoration (ER) and waste management (WM) problems at Oak Ridge National Laboratory (ORNL) to potential technologies that can remediate these problems. The TLD identifies the research, development, demonstration testing, and evaluation needed to develop these technologies to a state that allows technology transfer and application to decontamination and decommissioning (D&D), remedial action (RA), and WM activities. The TLD consists of three fundamentally separate volumes: Vol. 1, Technology Evaluation; Vol. 2, Technology Logic Diagram and Vol. 3, Technology EvaLuation Data Sheets. Part A of Vols. 1 and 2 focuses on RA. Part B of Vols. 1 and 2 focuses on the D&D of contaminated facilities. Part C of Vols. 1 and 2 focuses on WM. Each part of Vol. 1 contains an overview of the TM, an explanation of the problems facing the volume-specific program, a review of identified technologies, and rankings of technologies applicable to the site. Volume 2 (Pts. A. B. and C) contains the logic linkages among EM goals, environmental problems, and the various technologies that have the potential to solve these problems. Volume 3 (Pts. A. B, and C) contains the TLD data sheets. This volume provides the technology evaluation data sheets (TEDS) for ER/WM activities (D&D, RA and WM) that are referenced by a TEDS code number in Vol. 2 of the TLD. Each of these sheets represents a single logic trace across the TLD. These sheets contain more detail than is given for the technologies in Vol. 2.

Integrated operations plan for the MFTF-B Mirror Fusion Test Facility. Volume I. Organization plan

International Nuclear Information System (INIS)

1981-12-01

This plan and the accompanying MFTF-B Integrated Operations Plan are submitted in response to UC/LLNL Purchase Order 3883801, dated July 1981. The organization plan also addresses the specific tasks and trade studies directed by the scope of work. The Integrated Operations Plan, which includes a reliability, quality assurance, and safety plan and an integrated logistics plan, comprises the burden of the report. In the first section of this volume, certain underlying assumptions and observations are discussed setting the requirements and limits for organization. Section B presents the recommended structure itself. Section C Device Availability vs Maintenance and Support Efforts and Section D Staffing Levels and Skills provide backup detail and justification. Section E is a trade study on maintenance and support by LLNL staff vs subcontract and Section F is a plan for transitioning from the construction phase into operation. A brief summary of schedules and estimated costs concludes the volume

Guidelines for selecting codes for ground-water transport modeling of low-level waste burial sites. Volume 2. Special test cases

International Nuclear Information System (INIS)

Simmons, C.S.; Cole, C.R.

1985-08-01

This document was written for the National Low-Level Waste Management Program to provide guidance for managers and site operators who need to select ground-water transport codes for assessing shallow-land burial site performance. The guidance given in this report also serves the needs of applications-oriented users who work under the direction of a manager or site operator. The guidelines are published in two volumes designed to support the needs of users having different technical backgrounds. An executive summary, published separately, gives managers and site operators an overview of the main guideline report. Volume 1, titled ''Guideline Approach,'' consists of Chapters 1 through 5 and a glossary. Chapters 2 through 5 provide the more detailed discussions about the code selection approach. This volume, Volume 2, consists of four appendices reporting on the technical evaluation test cases designed to help verify the accuracy of ground-water transport codes. 20 refs

Potential actionable targets in appendiceal cancer detected by immunohistochemistry, fluorescent in situ hybridization, and mutational analysis

Science.gov (United States)

Millis, Sherri Z.; Kimbrough, Jeffery; Doll, Nancy; Von Hoff, Daniel; Ramanathan, Ramesh K.

2017-01-01

Background Appendiceal cancers are rare and consist of carcinoid, mucocele, pseudomyxoma peritonei (PMP), goblet cell carcinoma, lymphoma, and adenocarcinoma histologies. Current treatment involves surgical resection or debulking, but no standard exists for adjuvant chemotherapy or treatment for metastatic disease. Methods Samples were identified from approximately 60,000 global tumors analyzed at a referral molecular profiling CLIA-certified laboratory. A total of 588 samples with appendix primary tumor sites were identified (male/female ratio of 2:3; mean age =55). Sixty-two percent of samples were adenocarcinomas (used for analysis); the rest consisted of 9% goblet cell, 15% mucinous; 6% pseudomyxoma, and less than 5% carcinoids and 2% neuroendocrine. Tests included sequencing [Sanger, next generation sequencing (NGS)], protein expression/immunohistochemistry (IHC), and gene amplification [fluorescent in situ hybridization (FISH) or CISH]. Results Profiling across all appendiceal cancer histological subtypes for IHC revealed: 97% BRCP, 81% MRP1, 81% COX-2, 71% MGMT, 56% TOPO1, 5% PTEN, 52% EGFR, 40% ERCC1, 38% SPARC, 35% PDGFR, 35% TOPO2A, 25% RRM1, 21% TS, 16% cKIT, and 12% for TLE3. NGS revealed mutations in the following genes: 50.4% KRAS, 21.9% P53, 17.6% GNAS, 16.5% SMAD4, 10% APC, 7.5% ATM, 5.5% PIK3CA, 5.0% FBXW7, and 1.8% BRAF. Conclusions Appendiceal cancers show considerable heterogeneity with high levels of drug resistance proteins (BCRP and MRP1), which highlight the difficulty in treating these tumors and suggest an individualized approach to treatment. The incidence of low TS (79%) could be used as a backbone of therapy (using inhibitors such as 5FU/capecitabine or newer agents). Therapeutic options includeTOPO1 inhibitors (irinotecan/topotecan), EGFR inhibitors (erlotinib, cetuximab), PDGFR antagonists (regorafenib, axitinib), MGMT (temozolomide). Clinical trials targeting pathways involving KRAS, p53, GNAS, SMAD4, APC, ATM, PIK3CA, FBXW7, and

Master plan study - District heating Kohtla-Jaerve and Johvi municipalities. Estonia. Final report. Appendices for chapter 7

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-03-01

The appendices to chapter 7 of the master plan study on district heating in the municipalities of Kohtla-Jarve and Johvi (Estonia) present technical data on production units, also with regard to new facilities. (ARW)

CT and MR imaging findings of appendiceal and hepatic mucormycosis in a patient with acute T-lymphoblastic leukemia

Energy Technology Data Exchange (ETDEWEB)

Choi, Seo Youn; Lee, Min Hee; Lee, Hae Kyung; Yi, Boem Ha; Chin, Su Sie; Park, Seong Kyu; Chung, Jun Chul [Soonchunhyang University Bucheon Hospital, Bucheon (Korea, Republic of)

2015-11-15

Fungal infections occur in severely immunocompromised patients having profound and prolonged neutropenia. Here, we report a case of a 41-year-old female who, at the conclusion of induction chemotherapy for acute T-lymphoblastic leukemia, developed angioinvasive mucormycosis involving the appendix and liver, which presented as abdominal pain. This case is the first to provide detailed computed tomography and magnetic resonance imaging findings of angioinvasive appendiceal and hepatic mucormycosis. The implications of these findings as well as the diagnosis and management of mucormycosis, is further discussed.

CT and MR imaging findings of appendiceal and hepatic mucormycosis in a patient with acute T-lymphoblastic leukemia

International Nuclear Information System (INIS)

Choi, Seo Youn; Lee, Min Hee; Lee, Hae Kyung; Yi, Boem Ha; Chin, Su Sie; Park, Seong Kyu; Chung, Jun Chul

2015-01-01

Fungal infections occur in severely immunocompromised patients having profound and prolonged neutropenia. Here, we report a case of a 41-year-old female who, at the conclusion of induction chemotherapy for acute T-lymphoblastic leukemia, developed angioinvasive mucormycosis involving the appendix and liver, which presented as abdominal pain. This case is the first to provide detailed computed tomography and magnetic resonance imaging findings of angioinvasive appendiceal and hepatic mucormycosis. The implications of these findings as well as the diagnosis and management of mucormycosis, is further discussed

Replacement Nuclear Research Reactor: Draft Environmental Impact Statement. Vol. 2. Appendices

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-07-01

The appendices contains additional relevant information on: Environment Australia EIS Guidelines, composition of the Study Team, Consultation Activities and Resuits, Relevant Legislation and Regulatory Requirements, Exampies of Multi-Purpose Research Reactors, Impacts of Radioactive Emissions and Wastes Generated at Lucas Heights Science and Technology Centre, Technical Analysis of the Reference Accident, Flora and Fauna Species Lists, Summary of Environmental Commitments and an Outline of the Construction Environmental Management Plan Construction Environmental Management Plan figs., ills., refs. Prepared for Australian Nuclear Science and Technology Organisation (ANSTO)

Geophysical drillhole logging and optical imaging of the drillholes OL-KR43, OL-KR44, OL-KR44B, OL-KR45, OL-KR45B, OL-KR46, OL-KR46B, OL-KR47, OL-KR47B and OL-KR48, at Olkiluoto 2007 and 2008

International Nuclear Information System (INIS)

Tarvainen, A.-M.; Heikkinen, E.

2008-09-01

Suomen Malmi Oy conducted geophysical drillhole logging and optical imaging of the drillholes OL-KR43, OL-KR44, OL-KR44B, OL-KR45, OL-KR45B, OL-KR46, OL-KR46B, OL-KR47, OL-KR47B and OL-KR48 at the Olkiluoto site in Eurajoki during December 2007, May 2008. The survey is a part of Posiva Oy's detailed investigation program for the final disposal of spent nuclear fuel. The assignment included the field work and data processing. The report describes field operation, equipment as well as processing procedures and shows the obtained results and an analysis of their quality in the appendices. The raw and processed data are delivered digitally in WellCAD, PDF and Excel format. (orig.)

Recovery of Navy distillate fuel from reclaimed product. Volume I. Technical discussion

Energy Technology Data Exchange (ETDEWEB)

Brinkman, D.W.; Whisman, M.L.

1984-11-01

In an effort to assist the Navy to better utilize its waste hydrocarbons, NIPER, with support from the US Department of Energy, is conducting research designed to ultimately develop a practical technique for converting Reclaimed Product (RP) into specification Naval Distillate Fuel (F-76). The first phase of the project was focused on reviewing the literature and available information from equipment manufacturers. The literature survey has been carefully culled for methodology applicable to the conversion of RP into diesel fuel suitable for Navy use. Based upon the results of this study, a second phase has been developed and outlined in which experiments will be performed to determine the most practical recycling technologies. It is realized that the final selection of one particular technology may be site-specific due to vast differences in RP volume and available facilities. A final phase, if funded, would involve full-scale testing of one of the recommended techniques at a refueling depot. The Phase I investigations are published in two volumes. Volume 1, Technical Discussion, includes the narrative and Appendices I and II. Appendix III, a detailed Literature Review, includes both a narrative portion and an annotated bibliography containing about 800 referenvces and abstracts. This appendix, because of its volume, has been published separately as Volume 2. 18 figures, 4 tables.

Final report of the Multiprogram Laboratory Panel Energy Research Advisory Board. Volume II. Support studies

International Nuclear Information System (INIS)

Spiewak, I.; Guthrie, M.P.; Nichols, J.P.; Preston, E.L.; West, C.D.; Wilbanks, T.J.; Wilkes, B.Y.; Zerby, A.C.

1982-09-01

Volume II - support studies for nine national laboratories include: report of statistical data on the multiprogram laboratories; examples of national laboratory use in foreign countries; domestic models for national laboratory utilization; relationships of laboratories with industry and universities; uses of laboratories for training industrial R and D personnel; legal mandates and constraints on the national laboratories; with appendices on facts about Harwell, CEN-Saclay, TNO, Studsvik, and JAERI-Tokai; the Requirements Boards of the United Kingdom Department of Industry; impact of President's FY 1983 budget; and the PNL experiment

Technology, safety, and costs of decommissioning reference light-water reactors following postulated accidents. Appendices

Energy Technology Data Exchange (ETDEWEB)

Murphy, E S; Holter, G M

1982-11-01

Appendices contain information concerning the reference site description; reference PWR facility description; details of reference accident scenarios and resultant contamination levels; generic cleanup and decommissioning information; details of activities and manpower requirements for accident cleanup at a reference PWR; activities and manpower requirements for decommissioning at a reference PWR; costs of decommissioning at a reference PWR; cost estimating bases; safety assessment details; and details of post-accident cleanup and decommissioning at a reference BWR.

Implementation of Energy Strategies in Communities (Annex 63) Volume 2: Development of strategic measures

DEFF Research Database (Denmark)

Kellenberger, Daniel; Schmid, Christian; Quitzau, Maj-Britt

This report describes the further development of the analysed measures from Volume 1 into strategic measures. As with the term measure, a strategic measure refers to an essential measure in concept that can be used to develop individual implementation strategies on a local level for part...... or the whole life cycle of a project (from the first vision to monitoring of the implemented solution). The developed strategic measures deal with the following topics: Setting Vision and Targets Developing Renewable Energy Strategies Making Full use of Legal Frameworks Designing an Urban Competition Processes...... a summary of each strategic measure supported by nine appendices, each a detailed description of each strategic measure....

Geophysical drillhole logging of the drillholes OL-KR40, OL-KR41, OL-KR41B, OL-KR42, OLKR42B, OL-KR43 and OL-KR43B, at Olkiluoto 2006 and 2007

International Nuclear Information System (INIS)

Tarvainen, A.-M.

2007-05-01

Suomen Malmi Oy conducted geophysical borehole logging of the boreholes drillholes OL-KR40, OL-KR41, OL-KR41B, OL-KR42, OL-KR42B, OL-KR43 and OL-KR43B at the Olkiluoto site in Eurajoki during August, September, December 2006 and January 2007. The survey is a part of Posiva Oy's detailed investigation program for the final disposal of spent nuclear fuel. The assignment included the field work and processing of the acoustic data. The report describes field operation, equipment as well as processing procedures and shows the obtained results and an analysis of their quality in the appendices. The raw and processed data are delivered digitally in WellCAD, PDF and Excel format. (orig.)

Analysis of the structural parameters that influence gas production from the Devonian shale. Annual progress report, 1979-1980. Volume II. Data repository and reports published during fiscal year 1979-1980: regional structure, surface structure, surface fractures, hydrology

Energy Technology Data Exchange (ETDEWEB)

Negus-De Wys, J.; Dixon, J. M.; Evans, M. A.; Lee, K. D.; Ruotsala, J. E.; Wilson, T. H.; Williams, R. T.

1980-10-01

This volume comprises appendices giving regional structure data, surface structure data, surface fracture data, and hydrology data. The fracture data covers oriented Devonian shale cores from West Virginia, Ohio, Virginia, Pennsylvania, and Kentucky. The subsurface structure of the Eastern Kentucky gas field is also covered. (DLC)

Draft no-migration variance petition. Volume 6, Appendices: QAPD, REG, RM, SCR, SER

International Nuclear Information System (INIS)

1995-01-01

The Department of Energy is responsible for the disposition of transuranic (TRU) waste generated by national defense-related activities. Approximately 2,6 million cubic feet of these waste have been generated and are stored at various facilities across the country. The Waste Isolation Pilot Plant (WIPP), was sited and constructed to meet stringent disposal requirements. In order to permanently dispose of TRU waste, the DOE has elected to petition the US EPA for a variance from the Land Disposal Restrictions of RCRA. This document fulfills the reporting requirements for the petition. This is Volume 6 of the petition which presents details about the 1993 site environmental report; metorite impact; damage from rock mechanics; regulatory interpretations; and the quality assurance program

Transportation Sector Model of the National Energy Modeling System. Volume 2 -- Appendices: Part 3

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-01-01

This Appendix consists of two unpublished reports produced by Energy and Environmental Analysis, Inc., under contract to Oak Ridge National Laboratory. These two reports formed the basis for the subsequent development of the Fuel Economy Model described in Volume 1. They are included in order to document more completely the efforts undertaken to construct a comprehensive model of automobile fuel economy. The supplemental reports are as follows: Supplement 1--Documentation Attributes of Technologies to Improve Automotive Fuel Economy; Supplement 2--Analysis of the Fuel Economy Boundary for 2010 and Comparison to Prototypes.

Probabilistic safety analysis procedures guide. Sections 1-7 and appendices. Volume 1, Revision 1

International Nuclear Information System (INIS)

Bari, R.A.; Buslik, A.J.; Cho, N.Z.

1985-08-01

A procedures guide for the performance of probabilistic safety assessment has been prepared for interim use in the Nuclear Regulatory Commission programs. It will be revised as comments are received, and as experience is gained from its use. The probabilistic safety assessment studies performed are intended to produce probabilistic predictive models that can be used and extended by the utilities and by NRC to sharpen the focus of inquiries into a range of issues affecting reactor safety. This first volume of the guide describes the determination of the probability (per year) of core damage resulting from accident initiators internal to the plant (i.e., intrinsic to plant operation) and from loss of off-site electric power. The scope includes human reliability analysis, a determination of the importance of various core damage accident sequences, and an explicit treatment and display of uncertainties for key accident sequences. The second volume deals with the treatment of the so-called external events including seismic disturbances, fires, floods, etc. Ultimately, the guide will be augmented to include the plant-specific analysis of in-plant processes (i.e., containment performance). This guide provides the structure of a probabilistic safety study to be performed, and indicates what products of the study are valuable for regulatory decision making. For internal events, methodology is treated in the guide only to the extent necessary to indicate the range of methods which is acceptable; ample reference is given to alternative methodologies which may be utilized in the performance of the study. For external events, more explicit guidance is given

Advanced Neutron Source enrichment study -- Volume 1: Main report. Final report, Revision 12/94

International Nuclear Information System (INIS)

Bari, R.A.; Ludewig, H.; Weeks, J.

1994-01-01

A study has been performed of the impact on performance of using low enriched uranium (20% 235 U) or medium enriched uranium (35% 235 U) as an alternative fuel for the Advanced Neutron Source, which is currently designed to use uranium enriched to 93% 235 U. Higher fuel densities and larger volume cores were evaluated at the lower enrichments in terms of impact on neutron flux, safety, safeguards, technical feasibility, and cost. The feasibility of fabricating uranium silicide fuel at increasing material density was specifically addressed by a panel of international experts on research reactor fuels. The most viable alternative designs for the reactor at lower enrichments were identified and discussed. Several sensitivity analyses were performed to gain an understanding of the performance of the reactor at parametric values of power, fuel density, core volume, and enrichment that were interpolations between the boundary values imposed on the study or extrapolations from known technology. Volume 2 of this report contains 26 appendices containing results, meeting minutes, and fuel panel presentations

Mixed waste focus area technical baseline report. Volume 2

International Nuclear Information System (INIS)

1997-04-01

As part of its overall program, the MWFA uses a national mixed waste data set to develop approaches for treating mixed waste that cannot be treated using existing capabilities at DOE or commercial facilities. The current data set was originally compiled under the auspices of the 1995 Mixed Waste Inventory Report. The data set has been updated over the past two years based on Site Treatment Plan revisions and clarifications provided by individual sites. The current data set is maintained by the MWFA staff and is known as MWFA97. In 1996, the MWFA developed waste groupings, process flow diagrams, and treatment train diagrams to systematically model the treatment of all mixed waste in the DOE complex. The purpose of the modeling process was to identify treatment gaps and corresponding technology development needs for the DOE complex. Each diagram provides the general steps needed to treat a specific type of waste. The NWFA categorized each MWFA97 waste stream by waste group, treatment train, and process flow. Appendices B through F provide the complete listing of waste streams by waste group, treatment train, and process flow. The MWFA97 waste strewn information provided in the appendices is defined in Table A-1

Rate of Appendiceal Metastasis with Non-Serous Epithelial Ovarian Cancer in Manitoba.

Science.gov (United States)

Altman, Alon D; Lefas, Georgia; Power, Laura; Lambert, Pascal; Lotocki, Robert; Dean, Erin; Nachtigal, Mark W

2018-02-01

This study sought to evaluate the rate of appendiceal involvement in non-serous mucinous and endometrioid-associated epithelial ovarian cancers. The Manitoba Cancer Registry and CancerCare database were used to find all women with non-serous epithelial ovarian, fallopian tube, or primary peritoneal cancer between 1995 and 2011. All patients with an appendectomy were then identified, and their final pathology findings were reviewed. Women who did not receive treatment or lacked follow-up were excluded. We identified 338 patients from 1995-2011 with no prior appendectomy. Of these, 16.6% received an appendectomy, and 22.8% were clinically evaluated. Most cases within this cohort were mucinous (62%) and stage 1 (63%). Four appendiceal metastases were identified (7.2%), and one half appeared clinically normal at the time of surgery (3.6%). Within the mucinous histologic type, 32.7% of patients received an appendectomy, with a metastatic rate of 5.7%. Of the 127 endometrioid cases, only 10 patients received an appendectomy, and 2 were found to have metastases. No metastases were found in the 85 patients in the clear cell cohort, only 5 of whom received an appendectomy. Routine appendectomy or clinical assessment of the appendix is valuable for all non-serous ovarian cancers. The rate of involvement for endometriosis-associated ovarian cancers may be significantly higher than expected, and further studies need to be conducted. Copyright © 2018 Society of Obstetricians and Gynaecologists of Canada. Published by Elsevier Inc. All rights reserved.

Ductile fracture toughness of modified A 302 Grade B Plate materials, data analysis. Volume 1

Energy Technology Data Exchange (ETDEWEB)

McCabe, D.E.; Manneschmidt, E.T.; Swain, R.L.

1997-01-01

The goal of this work was to develop ductile fracture toughness data in the form of J-R curves for modified A302 grade B plate materials typical of those used in reactor pressure vessels. A previous experimental study on one heat of A302 grade B plate showed decreasing J-R curves with increased specimen thickness. This characteristic has not been observed in tests made on recent production materials of A533 grade B and A508 class 2 pressure vessel steels. It was unknown if the departure from norm for the material was a generic characteristic for all heats of A302 grade B steels or unique to that particular plate. Seven heats of modified A302 grade B steel and one heat of vintage A533 grade B steel were tested for chemical content, tensile properties, Charpy transition temperature curves, drop-weight nil-ductility transition (NDT) temperature, and J-R curves. Tensile tests were made in the three principal orientations and at four temperatures, ranging from room temperature to 550F. Charpy V-notch transition temperature curves were obtained in longitudinal, transverse, and short transverse orientations. J-R curves were made using four specimen sizes (1/2T, 1T, 2T, and 4T). The fracture mechanics-based evaluation method covered three test orientations and three test temperatures (80, 400, and 550F). However, the coverage of these variables was contingent upon the amount of material provided. Drop-weight NDT temperature was determined for the T-L orientation only. None of the heats of modified A302 grade B showed size effects of any consequence on the J-R curve behavior. Crack orientation effects were present, but none were severe enough to be reported as atypical. A test temperature increase from 180 to 550F produced the usual loss in J-R curve fracture toughness. Generic J-R curves and curve fits were generated to represent each heat of material. This volume deals with the evaluation of data and the discussion of technical findings. 8 refs., 18 figs., 8 tabs.

Ductile fracture toughness of modified A 302 Grade B Plate materials, data analysis. Volume 1

International Nuclear Information System (INIS)

McCabe, D.E.; Manneschmidt, E.T.; Swain, R.L.

1997-01-01

The goal of this work was to develop ductile fracture toughness data in the form of J-R curves for modified A302 grade B plate materials typical of those used in reactor pressure vessels. A previous experimental study on one heat of A302 grade B plate showed decreasing J-R curves with increased specimen thickness. This characteristic has not been observed in tests made on recent production materials of A533 grade B and A508 class 2 pressure vessel steels. It was unknown if the departure from norm for the material was a generic characteristic for all heats of A302 grade B steels or unique to that particular plate. Seven heats of modified A302 grade B steel and one heat of vintage A533 grade B steel were tested for chemical content, tensile properties, Charpy transition temperature curves, drop-weight nil-ductility transition (NDT) temperature, and J-R curves. Tensile tests were made in the three principal orientations and at four temperatures, ranging from room temperature to 550F. Charpy V-notch transition temperature curves were obtained in longitudinal, transverse, and short transverse orientations. J-R curves were made using four specimen sizes (1/2T, 1T, 2T, and 4T). The fracture mechanics-based evaluation method covered three test orientations and three test temperatures (80, 400, and 550F). However, the coverage of these variables was contingent upon the amount of material provided. Drop-weight NDT temperature was determined for the T-L orientation only. None of the heats of modified A302 grade B showed size effects of any consequence on the J-R curve behavior. Crack orientation effects were present, but none were severe enough to be reported as atypical. A test temperature increase from 180 to 550F produced the usual loss in J-R curve fracture toughness. Generic J-R curves and curve fits were generated to represent each heat of material. This volume deals with the evaluation of data and the discussion of technical findings. 8 refs., 18 figs., 8 tabs

A study of toxic emissions from a coal-fired power plant utilizing an ESP/Wet FGD system. Volume 1, Sampling, results, and special topics: Final report

Energy Technology Data Exchange (ETDEWEB)

1994-07-01

This was one of a group of assessments of toxic emissions from coal-fired power plants, conducted for DOE-PETC in 1993 as mandated by the 1990 Clean Air Act. It is organized into 2 volumes; Volume 1 describes the sampling effort, presents the concentration data on toxic chemicals in several power plant streams, and reports the results of evaluations and calculations. The study involved solid, liquid, and gaseous samples from input, output, and process streams at Coal Creek Station Unit No. 1, Underwood, North Dakota (1100 MW mine-mouth plant burning lignite from the Falkirk mine located adjacent to the plant). This plant had an electrostatic precipitator and a wet scrubber flue gas desulfurization unit. Measurements were conducted on June 21--24, 26, and 27, 1993; chemicals measured were 6 major and 16 trace elements (including Hg, Cr, Cd, Pb, Se, As, Be, Ni), acids and corresponding anions (HCl, HF, chloride, fluoride, phosphate, sulfate), ammonia and cyanide, elemental C, radionuclides, VOCs, semivolatiles (incl. PAH, polychlorinated dioxins, furans), and aldehydes. Volume 2: Appendices includes process data log sheets, field sampling data sheets, uncertainty calculations, and quality assurance results.

Generic environmental impact statement on handling and storage of spent light water power reactor fuel. Appendices

International Nuclear Information System (INIS)

1978-03-01

Detailed appendices are included with the following titles: light water reactor fuel cycle, present practice, model 1000MW(e) coal-fired power plant, increasing fuel storage capacity, spent fuel transshipment, spent fuel generation and storage data (1976-2000), characteristics of nuclear fuel, and ''away-from-reactor'' storage concept

Probabilistic accident consequence uncertainty analysis: Food chain uncertainty assessment. Volume 1: Main report

Energy Technology Data Exchange (ETDEWEB)

Brown, J. [National Radiological Protection Board (United Kingdom); Goossens, L.H.J.; Kraan, B.C.P. [Delft Univ. of Technology (Netherlands)] [and others

1997-06-01

This volume is the first of a two-volume document that summarizes a joint project conducted by the US Nuclear Regulatory Commission and the European Commission to assess uncertainties in the MACCS and COSYMA probabilistic accident consequence codes. These codes were developed primarily for estimating the risks presented by nuclear reactors based on postulated frequencies and magnitudes of potential accidents. This document reports on an ongoing project to assess uncertainty in the MACCS and COSYMA calculations for the offsite consequences of radionuclide releases by hypothetical nuclear power plant accidents. A panel of sixteen experts was formed to compile credible and traceable uncertainty distributions for food chain variables that affect calculations of offsite consequences. The expert judgment elicitation procedure and its outcomes are described in these volumes. Other panels were formed to consider uncertainty in other aspects of the codes. Their results are described in companion reports. Volume 1 contains background information and a complete description of the joint consequence uncertainty study. Volume 2 contains appendices that include (1) a summary of the MACCS and COSYMA consequence codes, (2) the elicitation questionnaires and case structures for both panels, (3) the rationales and results for the panels on soil and plant transfer and animal transfer, (4) short biographies of the experts, and (5) the aggregated results of their responses.

Probabilistic accident consequence uncertainty analysis: Food chain uncertainty assessment. Volume 1: Main report

International Nuclear Information System (INIS)

Brown, J.; Goossens, L.H.J.; Kraan, B.C.P.

1997-06-01

This volume is the first of a two-volume document that summarizes a joint project conducted by the US Nuclear Regulatory Commission and the European Commission to assess uncertainties in the MACCS and COSYMA probabilistic accident consequence codes. These codes were developed primarily for estimating the risks presented by nuclear reactors based on postulated frequencies and magnitudes of potential accidents. This document reports on an ongoing project to assess uncertainty in the MACCS and COSYMA calculations for the offsite consequences of radionuclide releases by hypothetical nuclear power plant accidents. A panel of sixteen experts was formed to compile credible and traceable uncertainty distributions for food chain variables that affect calculations of offsite consequences. The expert judgment elicitation procedure and its outcomes are described in these volumes. Other panels were formed to consider uncertainty in other aspects of the codes. Their results are described in companion reports. Volume 1 contains background information and a complete description of the joint consequence uncertainty study. Volume 2 contains appendices that include (1) a summary of the MACCS and COSYMA consequence codes, (2) the elicitation questionnaires and case structures for both panels, (3) the rationales and results for the panels on soil and plant transfer and animal transfer, (4) short biographies of the experts, and (5) the aggregated results of their responses

Operational Assessment of Tools for Accelerating Leader Development (ALD): Volume 2, Appendices

Science.gov (United States)

2009-06-01

and were designed to be used interactively in small group settings as filmed case studies incorporating many storytelling elements which are proven...program staff. - Facilitate the Sessions 1. Schedule the AXL vignette session a. Classroom or other suitable area b. Means of showing the vignette 2...the unit situation. Classroom , Training Area 1. With the exception of the AXL Vignettes, all materials are designed for web- delivered individual

United States Air Force F-35A Operational Basing Environmental Impact Statement. Volume 2, Appendices

Science.gov (United States)

2013-09-01

the natural soundscapes of parks consistent with our Management Policies. NPS Management Policies, Section 4.9, Soundscape Management, states “the...Department will restore to the natural condition wherever possible those park soundscapes that have become degraded by unnatural sounds (noise...and will protect natural soundscapes from unacceptable impacts.” This is consistent with 40 CFR. §1508-27b, “Unique characteristics of the geographic

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

International Nuclear Information System (INIS)

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

1988-09-01

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

Export Controls and the U.S. Defense Industrial Base. Volume 1. Summary Report, and Volume 2. Appendices

Science.gov (United States)

2007-01-01

el que se aprueba el reglamento del comercio exterior de material de defensa y de doble uso • Ley Orgánica 12...export restrictions. A-63 S T P I 60 Supplying Other Primes • India (ISRO), Israel ( El -Opt, Israel Aircraft Industries), Japan...200 400 600 800 1000 1200 1400 1600 A lg er ia Ar ge nt in a A us tra lia B el ar us Br az il C an ad a C hi le Eg yp t In do ne si a Ira n Is ra el

Literature review of environmental qualification of safety-related electric cables: Literature analysis and appendices. Volume 2

International Nuclear Information System (INIS)

Lofaro, R.; Bowerman, B.; Carbonaro, J.

1996-04-01

In support of the US NRC Environmental Qualification (EQ) Research Program, a literature review was performed to identify past relevant work that could be used to help fully or partially resolve issues of interest related to the qualification of low-voltage electric cable. A summary of the literature reviewed is documented in Volume 1 of this report. In this, Volume 2 of the report, dossiers are presented which document the issues selected for investigation in this program, along with recommendations for future work to resolve the issues, when necessary. The dossiers are based on an analysis of the literature reviewed, as well as expert opinions. This analysis includes a critical review of the information available from past and ongoing work in thirteen specific areas related to EQ. The analysis for each area focuses on one or more questions which must be answered to consider a particular issue resolved. Results of the analysis are presented, along with recommendations for future work. The analysis is documented in the form of a dossier for each of the areas analyzed

Master plan study - District heating Kohtla-Jaerve and Johvi municipalities. Estonia. Final report. Appendices for chapter 9

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-03-01

The appendices to chapter nine of the final report of the master plan study on district heating in the municipalities of Kohtla-Jarve and Johvi municipalities (Estonia) present extensive data relating to economic, financial and environmental calculations, fuel consumption, energy balance and prices. (ARW)

The METAL System. Volume I and Volume II. Appendices.

Science.gov (United States)

1981-01-01

Chapter VI, can be performed by a monolingual person with very little training. In addition, the use of one of the more sophisticated text editing...paradigmatic or stylistic manipu- lation. Usually the form most likely to be included in a dictionary is selected, such as nominative singular for nouns...34, "low", "better", "most") OTR = other ("left") Participial adjectives which occur in the reference dictionary will be coded on the assumption that they

Procedures for treating common cause failures in safety and reliability studies: Volume 2, Analytic background and techniques: Final report

International Nuclear Information System (INIS)

Mosleh, A.; Fleming, K.N.; Parry, G.W.; Paula, H.M.; Worledge, D.H.; Rasmuson, D.M.

1988-12-01

This report presents a framework for the inclusion of the impact of common cause failures in risk and reliability evaluations. Common cause failures are defined as that subset of dependent failures for which causes are not explicitly included in the logic model as basic events. The emphasis here is on providing procedures for a practical, systematic approach that can be used to perform and clearly document the analysis. The framework and the methods discussed for performing the different stages of the analysis integrate insights obtained from engineering assessments of the system and the historical evidence from multiple failure events into a systematic, reproducible, and defensible analysis. This document, Volume 2, contains a series of appendices that provide additional background and methodological detail on several important topics discussed in Volume 1

Hydrostatic Mooring System. Final Technical Report: Main Report plus Appendices A, B, and C - Volume 1 and 2

Energy Technology Data Exchange (ETDEWEB)

Jens Korsgaard

2000-08-08

The main conclusions from the work carried out under this contract are: An ordinary seafarer can learn by training on a simulator, to moor large tanker vessels to the Hydrostatic Mooring, safely and quickly, in all weather conditions up to storms generating waves with a significant wave height of 8 m. Complete conceptual design of the Hydrostatic Mooring buoy was carried out which proved that the buoy could be constructed entirely from commercially available standard components and materials. The design is robust, and damage resistant. The mooring tests had a 100% success rate from the point of view of the buoy being securely attached and moored to the vessel following every mooring attempt. The tests had an 80% success rate from the point of view of the buoy being adequately centered such that petroleum transfer equipment on the vessel could be attached to the corresponding equipment on the buoy. The results given in Table 3-2 of the mooring tests show a consistently improving performance from test to test by the Captain that performed the mooring operations. This is not surprising, in view of the fact that the Captain had only three days of training on the simulator prior to conducting the tests, that the maneuvering required is non-standard, and the test program itself lasted four days. One conclusion of the test performance is that the Captain was not fully trained at the initiation of the test. It may therefore be concluded that a thoroughly trained navigator would probably be able to make the mooring such that the fluid transfer equipment can be connected with reliability in excess of 90%. Considering that the typical standard buoy has enough power aboard to make eight mooring attempts, this implies that the probability that the mooring attempt should fail because of the inability to connect the fluid transfer equipment is of the order of 10{sup {minus}8}. It may therefore be concluded that the mooring operation between a Hydrostatic Mooring and a large

Indian Point Nuclear Generating Plant Unit No. 3 (Docket No. 50-286): Final environmental statement: Volume 2

International Nuclear Information System (INIS)

1975-02-01

This document contains nine appendices to Volume I, The Final Environmental Impact Statement for the Indian Point Nuclear Generating Plant Unit Number Three. Topics covered include thermal discharges to the Hudson River; supplemental information relating to biological models; radiation effects on aquatic biota; conditions, assumptions, and parameters used in calculating radioactive releases; meteorology for radiological dispersion calculations; life history information of important fish species in the Hudson River near Indian Point; additional information on cooling towers considered as alternatives; data and calculations for assessment of predicted electrical demand; and comments on draft environmental statement

A new method to estimate the atomic volume of ternary intermetallic compounds

International Nuclear Information System (INIS)

Pani, M.; Merlo, F.

2011-01-01

The atomic volume of an A x B y C z ternary intermetallic compound can be calculated starting from volumes of some proper A-B, A-C and B-C binary phases. The three methods by Colinet, Muggianu and Kohler, originally used to estimate thermodynamic quantities, and a new method here proposed, were tested to derive volume data in eight systems containing 91 ternary phases with the known structure. The comparison between experimental and calculated volume values shows the best agreement both for the Kohler method and for the new proposed procedure. -- Graphical abstract: Synopsys: the volume of a ternary intermetallic compound can be calculated starting from volumes of some binary phases, selected by the methods of Colinet, Muggianu, Kohler and a new method proposed here. The so obtained values are compared with the experimental ones for eight ternary systems. Display Omitted Research highlights: → The application of some thermodinamic methods to a crystallochemical problem. → The prevision of the average atomic volume of ternary intermetallic phases. → The proposal of a new procedure to select the proper starting set of binary phases.

Environmental and Cultural Impact. Proposed Tennessee Colony Reservoir, Trinity River, Texas. Volume II. Appendices A, B and C.

Science.gov (United States)

1972-01-01

voir itself. Even slight traces of mercury in water are considered a health hazard since mercury retention in the body is a cumulative process, and...latifolia Buckl. Golden Aster, Camphor Weed Ileterotheca pilosa (Nutt.) Golden Aster, Camphor Shinners Weed Hibiscus lasiocarpos Cav. Woolly rose...mallow Hibiscus militaris Cay. Scarlet Rose Mallow Hibiscus trionum L. Flower-of-an-hour Hydrocotyle unbellata L. Water-pennywort Hydrocotyle

Biomass, the green motor in transition. State-of-the-art after the second phase. Appendices

International Nuclear Information System (INIS)

Gigler, J.

2004-01-01

The project Transition Biomass is part of the transition towards a sustainable energy economy in the Netherlands, initiated by the Ministry of Economic Affairs. The aim of the project is to start a societal process of changes to realize a large-scale and sustainable use of biomass for the production of energy, transportation fuels and products. In the main report an overview is given of the results in 2003. This report comprises the appendices [nl

Preoperational baseline and site characterization report for the Environmental Restoration Disposal Facility. Volume 1, Revision 2

International Nuclear Information System (INIS)

Weekes, D.C.; Lindsey, K.A.; Ford, B.H.; Jaeger, G.K.

1996-12-01

This document is the first in a two-volume series that comprise the site characterization report. Volume 1 contains data interpretation and information supporting the conclusions in the text (Appendices A through G). Volume 2 provides raw data. A site located between 200 East and 200 West Areas, in the central portion of the Hanford Site, was selected as the prime location for the ERDF. Modifications to the facility design minimize the footprint and have resulted in a significant reduction in the areal size. This change was initiated in part as a response to recommendations of the Hanford Future Site Uses Working Group to limit waste management activities to an exclusive zone within the squared-off boundary of the 200 Areas. Additionally, the reduction in size of the footprint was initiated to minimize impacts to ecology. The ERDF is designed for disposal of remediation wastes generated during the cleanup of Hanford Site and could be expanded to hold as much as 28 million yd 3 (21.4 million m 3 ) of solid waste

Mirror Advanced Reactor Study (MARS). Final report. Volume 1-B. Commercial fusion electric plant

International Nuclear Information System (INIS)

Donohue, M.L.; Price, M.E.

1984-07-01

Volume 1-B contains the following chapters: (1) blanket and reflector; (2) central cell shield; (3) central cell structure; (4) heat transport and energy conversion; (5) tritium systems; (6) cryogenics; (7) maintenance; (8) safety; (9) radioactivity, activation, and waste disposal; (10) instrumentation and control; (11) balance of plant; (12) plant startup and operation; (13) plant availability; (14) plant construction; and (15) economic analysis

Mirror Advanced Reactor Study (MARS). Final report. Volume 1-B. Commercial fusion electric plant

Energy Technology Data Exchange (ETDEWEB)

Donohue, M.L.; Price, M.E. (eds.)

1984-07-01

Volume 1-B contains the following chapters: (1) blanket and reflector; (2) central cell shield; (3) central cell structure; (4) heat transport and energy conversion; (5) tritium systems; (6) cryogenics; (7) maintenance; (8) safety; (9) radioactivity, activation, and waste disposal; (10) instrumentation and control; (11) balance of plant; (12) plant startup and operation; (13) plant availability; (14) plant construction; and (15) economic analysis.

Weightless Environment Training Facility (WETF) materials coating evaluation, volume 1

Science.gov (United States)

1995-01-01

The Weightless Environment Training Facility Material Coating Evaluation project has included preparing, coating, testing, and evaluating 800 test panels of three differing substrates. Ten selected coating systems were evaluated in six separate exposure environments and subject to three tests for physical properties. Substrate materials were identified, the manner of surface preparation described, and exposure environments defined. Exposure environments included immersion exposure, cyclic exposure, and field exposure. Cyclic exposures, specifically QUV-Weatherometer and the KTA Envirotest were found to be the most agressive of the environments included in the study when all three evaluation criteria are considered. This was found to result primarily from chalking of the coatings under ultraviolet (UV) light exposure. Volumes 2 and 3 hold the 5 appendices to this report.

Remedial investigation/feasibility study for the Clinch River/Poplar Creek operable unit. Volume 2. Appendixes A, B, C, D

International Nuclear Information System (INIS)

1995-09-01

This document contains appendices A (water characterization), B (sediment characterization), C (biota Characterization), D (applicable or relevant and appropriate requirements) from the combined Remedial Investigation/Feasibility Study Report for the Clinch River/Poplar Crack (CR/PC) Operable Unit (OU). The CR/PC OU is located in Anderson and Roane Counties, Tennessee and consists of the Clinch River and several of its embayments in Melton Hill and Watts Bar Reservoirs. These waters have received hazardous substances released over a period of 50 years from the US Department of Energy's Oak Ridge Reservation (ORR), a National Priority List site established under the Comprehensive Environmental Response, Compensation, and Liability Act. A remedial investigation has been conducted to determine the current nature and extent of any contamination and to assess the resulting risk to human health and the environment. The feasibility study evaluates remedial action alternatives to identify any that are feasible for implementation and that would effectively reduce risk. Historical studies had indicated that current problems would likely include 137 Cs in sediment of the Clinch River, mercury in sediment and fish of Poplar Creek and PCBs and pesticides in fish from throughout the OU. Peak releases of mercury and 137 Cs occurred over 35 years ago, and current releases are low. Past releases of PCBs from the ORR are poorly quantified, and current releases are difficult to quantify because levels are so low. The site characterization focused on contaminants in surface water, sediment, and biota. Contaminants in surface water were all found to be below Ambient Water Quality Criteria. Other findings included the following: elevated metals including cesium 137 and mercury in McCoy Branch sediments; PCBs and chlordane elevated in several fish species, presenting the only major human health risk, significant ecological risks in Poplar Creek but not in the Clinch River

Remedial investigation/feasibility study for the Clinch River/Poplar Creek operable unit. Volume 2. Appendixes A, B, C, D

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-09-01

This document contains appendices A (water characterization), B (sediment characterization), C (biota Characterization), D (applicable or relevant and appropriate requirements) from the combined Remedial Investigation/Feasibility Study Report for the Clinch River/Poplar Crack (CR/PC) Operable Unit (OU). The CR/PC OU is located in Anderson and Roane Counties, Tennessee and consists of the Clinch River and several of its embayments in Melton Hill and Watts Bar Reservoirs. These waters have received hazardous substances released over a period of 50 years from the US Department of Energy`s Oak Ridge Reservation (ORR), a National Priority List site established under the Comprehensive Environmental Response, Compensation, and Liability Act. A remedial investigation has been conducted to determine the current nature and extent of any contamination and to assess the resulting risk to human health and the environment. The feasibility study evaluates remedial action alternatives to identify any that are feasible for implementation and that would effectively reduce risk. Historical studies had indicated that current problems would likely include {sup 137}Cs in sediment of the Clinch River, mercury in sediment and fish of Poplar Creek and PCBs and pesticides in fish from throughout the OU. Peak releases of mercury and {sup 137}Cs occurred over 35 years ago, and current releases are low. Past releases of PCBs from the ORR are poorly quantified, and current releases are difficult to quantify because levels are so low. The site characterization focused on contaminants in surface water, sediment, and biota. Contaminants in surface water were all found to be below Ambient Water Quality Criteria. Other findings included the following: elevated metals including cesium 137 and mercury in McCoy Branch sediments; PCBs and chlordane elevated in several fish species, presenting the only major human health risk, significant ecological risks in Poplar Creek but not in the Clinch River.

Oak Ridge K-25 Site Technology Logic Diagram. Volume 3, Technology evaluation data sheets; Part B, Remedial action, robotics/automation, waste management

Energy Technology Data Exchange (ETDEWEB)

Fellows, R.L. [ed.

1993-02-26

The Oak Ridge K-25 Technology Logic Diagram (TLD), a decision support tool for the K-25 Site, was developed to provide a planning document that relates environmental restoration (ER) and waste management (WN) problems at the Oak Ridge K-25 Site. The TLD technique identifies the research necessary to develop these technologies to a state that allows for technology transfer and application to waste management, remediation, decontamination, and decommissioning activities. The TLD consists of four separate volumes-Vol. 1, Vol. 2, Vol. 3A, and Vol. 3B. Volume 1 provides introductory and overview information about the TLD. Volume 2 contains logic diagrams. Volume 3 has been divided into two separate volumes to facilitate handling and use. This volume 3 B provides the Technology Evaluation Data Sheets (TEDS) for ER/WM activities (Remedial Action Robotics and Automation, Waste Management) that are referenced by a TEDS code number in Vol. 2 of the TLD. Each of these sheets represents a single logic trace across the TLD. These sheets contain more detail than each technology in Vol. 2. The TEDS are arranged alphanumerically by the TEDS code number in the upper right corner of each data sheet. Volume 3 can be used in two ways: (1) technologies that are identified from Vol. 2 can be referenced directly in Vol. 3 by using the TEDS codes, and (2) technologies and general technology areas (alternatives) can be located in the index in the front of this volume.

Demonstration, testing, & evaluation of in situ heating of soil. Draft final report, Volume I

Energy Technology Data Exchange (ETDEWEB)

Dev, H.; Enk, J.; Jones, D.; Saboto, W.

1996-02-12

This document is a draft final report (Volume 1) for US DOE contract entitled, {open_quotes}Demonstration Testing and Evaluation of In Situ Soil Heating,{close_quotes} Contract No. DE-AC05-93OR22160, IITRI Project No. C06787. This report is presented in two volumes. Volume I contains the technical report and Volume II contains appendices with background information and data. In this project approximately 300 cu. yd. of clayey soil containing a low concentration plume of volatile organic chemicals was heated in situ by the application of electrical energy. It was shown that as a result of heating the effective permeability of soil to air flow was increased such that in situ soil vapor extraction could be performed. The initial permeability of soil was so low that the soil gas flow rate was immeasurably small even at high vacuum levels. When scaled up, this process can be used for the environmental clean up and restoration of DOE sites contaminated with VOCs and other organic chemicals boiling up to 120{degrees} to 130{degrees}C in the vadose zone. Although it may applied to many types of soil formations, it is particularly attractive for low permeability clayey soil where conventional in situ venting techniques are limited by low air flow.

Final environmental impact statement, Beaufort Sea oil and gas development/Northstar Project. Appendices L through P

International Nuclear Information System (INIS)

1999-02-01

BP Exploration (Alaska) Inc. (BPXA) submitted a permit application to the US Army Engineer District, Alaska to initiate the review process for BPXA's plans to develop and produce oil and gas from the Northstar Unit. This report contains Appendices L-P of an Environmental Impact Statement which was undertaken to identify and evaluate the potential effects the proposed project may have on the environment

A B Pandit

Indian Academy of Sciences (India)

Home; Journals; Resonance – Journal of Science Education. A B Pandit. Articles written in Resonance – Journal of Science Education. Volume 5 Issue 11 November 2000 pp 56-68 General Article. Techniques of WasteWater Treatment - Introduction to Effluent Treatment and Industrial Methods · Amol A Kulkarni Mugdha ...

Y-12 Plant remedial action Technology Logic Diagram: Volume 3, Technology evaluation data sheets: Part B, Characterization; robotics/automation

International Nuclear Information System (INIS)

1994-09-01

The Y-12 Plant Remedial Action Technology Logic Diagram (TLD) was developed to provide a decision-support tool that relates environmental restoration (ER) problems at the Y-12 Plant to potential technologies that can remediate theses problems. The TLD identifies the research, development, demonstration, testing, and evaluation needed for sufficient development of these technologies to allow for technology transfer and application to remedial action (RA) activities. The TLD consists of three volumes. Volume 1 contains an overview of the TLD, an explanation of the program-specific responsibilities, a review of identified technologies, and the rankings of remedial technologies. Volume 2 contains the logic linkages among environmental management goals, environmental problems, and the various technologies that have the potential to solve these problems. Volume 3 contains the TLD data sheets. This report is Part B of Volume 3 and contains the Characterization and Robotics/Automation sections

Annual report to the Atomic Energy Control Board on the regulatory research and support program April 1, 1993 - March 31, 1994. Appendices

International Nuclear Information System (INIS)

1995-05-01

Detailed information has been compiled into six appendices giving presenting information on the scope of RSP activities during the year and describes how the program was managed, organized and implemented. The membership of active review panels is given in Appendix A. Appendix B contains summary descriptions and information on the status of individual projects. Appendix C presents a list of those projects which were within the overall RSP but were not active during the year. Appendix D lists the projects which were complete but for which the post project evaluation had as yet to be completed. All projects worked on during the year are listed in Appendix E. Specific objectives set for the RSP for Fiscal Year 1993/94 and the degree to which the objectives were achieved are outlined in Appendix F. (DM). 207 tabs

Annual report to the Atomic Energy Control Board on the regulatory research and support program April 1, 1993 - March 31, 1994. Appendices

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-05-01

Detailed information has been compiled into six appendices giving presenting information on the scope of RSP activities during the year and describes how the program was managed, organized and implemented. The membership of active review panels is given in Appendix A. Appendix B contains summary descriptions and information on the status of individual projects. Appendix C presents a list of those projects which were within the overall RSP but were not active during the year. Appendix D lists the projects which were complete but for which the post project evaluation had as yet to be completed. All projects worked on during the year are listed in Appendix E. Specific objectives set for the RSP for Fiscal Year 1993/94 and the degree to which the objectives were achieved are outlined in Appendix F. (DM). 207 tabs.

Development of a dynamic model to evaluate economic recovery following a nuclear attack. Volume 1. Description and simulations. Final report

International Nuclear Information System (INIS)

Peterson, D.W.; Silverman, W.S.; Weil, H.B.; Willard, S.

1980-11-01

A highly-robust, dynamic simulation model of the US economy has been constructed to evaluate the likely economic response after various nuclear attacks or other severe disruptions, under various policies and assumptions. The model consists of a large system of nonlinear, recursive, time-difference equations. The solution-interval of the model is adjustable, with a maximum value of three weeks. The model represents the economy in thirteen sectors. Each sector contains a detailed representation of production, distribution, supply constraints, finance, employment, pricing, and wages. Also included are a full input-output representation of the interconnections among the sectors, and the psychological responses of corporate planners, consumers, and the labor force. The model's equations are formulated to remain consistent and realistic for all values of the variables, including the most extreme conditions. Therefore, the model can realistically simulate any degree or time sequence of nuclear attacks, pre-attack surges, mobilization, or policy shifts. Simulation experiments with the model suggest that the economy is highly vulnerable to nuclear attack, and that recovery requires extensive preparation, including psychological readiness, technology maintenance, special financial policies, and (if possible) maintenance of foreign trade. Civil defense policies must be adaptive (contingent on the nature of the damage) and must strive for balance among sectors, rather than maximum survival. This volume includes two appendices. Appendix A defines the aggregation of the model. Appendix B outlines the range of attack scenarios, pre-attack civil defense policies, and post-attack civil defense policies that can be evaluated with the model, including the model variables applicable to implementing those policies

Resource Conservation and Recovery Act, Part B permit application

International Nuclear Information System (INIS)

1993-01-01

This volume contains appendices for the following: results of extraction procedure (EP) toxicity data analyses; summary of headspace gas analysis in Rocky Flats Plant sampling program-FY 1988; waste drum gas generation sampling program at Rocky Flats Plant during FY 1988; TRU waste sampling program waste characterization; summary of headspace gas analyses in TRU waste sampling program; summary of volatile organic compounds analyses in TRU waste sampling program; totals analysis versus toxicity characteristic leaching procedure; Waste Isolation Pilot Plant waste characterization sampling and analysis methods; Waste Isolation Pilot Plant waste characterization analytical methods; data reduction, validation and reporting; examples of waste screening checklists; and Waste Isolation Pilot Plant generator/storage site waste screening and acceptance audit program

Chooz B

International Nuclear Information System (INIS)

Barillot, Pascale; Baize, Jean-Marc

1997-01-01

This EDF press communique give information related to the exploitation of the Chooz B NPP. A calendar of the Chooz B1 and B2 NPPs exploitation is given as well as information about the local economic impact. The exploitation of the PWR reactors of the French nuclear sector corresponds to a accumulated experience of 600 year-reactor. Significant technological evolution has been recorded, namely in the test-control system, the turbo-alternator group 'Arabelle' and in the vapor generators. The reactor safety is based on the high professionalism of the exploitation personnel, on the computer-assisted behaviour allowing the choice of operators and on the conception based upon the experience accumulated by the French nuclear power plants, equivalent to 600 year-reactor operation. EDF operates a system of continual surveillance which allows the monitoring the environmental effects caused by the NPP exploitation. The following issues concerning the environment impact are reported in this document: - The effluent releases in the environment; - Health studies conducted in the NPPs' neighbourhood; - New authorizations for waste release; - Radioactive waste management. The report also mentions the French-Belgian partnership in the PWR construction, the socio-economic regional impact of the EDF activities related with the Chooz NPP operation, and the partnership with the associated service companies. Six appendices are attached to the report containing the following information: - A general layout of Chooz NPP; - Chooz B key figures; Chooz B key data; - Security and public information; - Evolution of PWR system in France; - World's nuclear systems