Technical baseline description for in situ vitrification laboratory test equipment

International Nuclear Information System (INIS)

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

1991-09-01

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

100-D Area technical baseline report

International Nuclear Information System (INIS)

Carpenter, R.W.

1993-01-01

This document is prepared in support of the 100 Area Environmental Restoration activity at the US Department of Energy's Hanford Site near Richland, Washington. It provides a technical baseline of waste sites located at the 100-D Area. The report is based on an environmental investigation undertaken by the Westinghouse Hanford Company (WHC) History Office in support of the Environmental Restoration Engineering Function and on review and evaluation of numerous Hanford Site current and historical reports, drawings, and photographs, supplemented by site inspections and employee interviews. No intrusive field investigation or sampling was conducted. All Hanford coordinate locations are approximate locations taken from several different maps and drawings of the 100-D Area. Every effort was made to derive coordinate locations for the center of each facility or waste site, except where noted, using standard measuring devices. Units of measure are shown as they appear in reference documents. The 100-D Area is made up of three operable units: 100-DR-1, 100-DR-2, and 100-DR-3. All three are addressed in this report. These operable units include liquid and solid waste disposal sites in the vicinity of, and related to, the 100-D and 100-DR Reactors. A fourth operable unit, 100-HR-3, is concerned with groundwater and is not addressed here. This report describes waste sites which include cribs, trenches, pits, french drains, retention basins, solid waste burial grounds, septic tanks, and drain fields. Each waste site is described separately and photographs are provided where available. A complete list of photographs can be found in Appendix A. A comprehensive environmental summary is not provided here but may be found in Hanford Site National Environmental Policy Act Characterization (Cushing 1988), which describes the geology and soils, meteorology, hydrology, land use, population, and air quality of the area

200-UP-2 Operable Unit technical baseline report

International Nuclear Information System (INIS)

Deford, D.H.

1991-02-01

This report is prepared in support of the development of a Remedial Investigation/Feasibility Study (RI/FS) Work Plan for the 200-UP-2 Operable Unit by EBASCO Environmental, Incorporated. It provides a technical baseline of the 200-UP-2 Operable Unit and results from an environmental investigation undertaken by the Technical Baseline Section of the Environmental Engineering Group, Westinghouse Hanford Company (Westinghouse Hanford). The 200-UP-2 Operable Unit Technical Baseline Report is based on review and evaluation of numerous Hanford Site current and historical reports, Hanford Site drawings and photographs and is supplemented with Hanford Site inspections and employee interviews. No field investigations or sampling were conducted. Each waste site in the 200-UP-2 Operable Unit is described separately. Close relationships between waste units, such as overflow from one to another, are also discussed. The 200-UP-2 Operable Unit consists of liquid-waste disposal sites in the vicinity of, and related to, U Plant operations in the 200 West Area of the Hanford Site. The ''U Plant'' refers to the 221-U Process Canyon Building, a chemical separations facility constructed during World War 2. It also includes the Uranium Oxide (UO 3 ) Plant, which was constructed at the same time and, like the 221-U Process Canyon Building, was later converted for other missions. Waste sites in the 200-UP-2 Operable Unit are associated with the U Plant Uranium Metal Recovery Program mission that occurred between 1952 and 1958 and the UO 3 Plant's ongoing uranium oxide mission and include one or more cribs, reverse wells, french drains, septic tanks and drain fields, trenches, catch tanks, settling tanks, diversion boxes, waste vaults, and the lines and encasements that connect them. 11 refs., 1 tab

FHWA vehicle crash analysis conference proceedings : technical summary

Science.gov (United States)

1997-04-01

This technical summary announces the publication of conference proceedings as a Federal Highway Administration (FHWA) report (FHWA-RD-96-212) of the same title. The report represents a compilation of seven research papers presented at The FHWA Veh...

KBS Technical report 1-120 (1977-1978). Summaries

International Nuclear Information System (INIS)

1979-05-01

The Swedish nuclear utilities started early in 1977 the KBS (nuclear fuel safety) project to study the high level waste problem and report on how and where a safe final storage could be arranged in Sweden. The docummentation produced by the project during 1977 and 1978 has been collected in a series of technical reports numbered from 1 to 120. The English summaries of the technical reports have been collected in this separate volume, No. 121. (G.B.)

Tank waste remediation system retrieval and disposal mission initial updated baseline summary

International Nuclear Information System (INIS)

Swita, W.R.

1998-01-01

This document provides a summary of the proposed Tank Waste Remediation System Retrieval and Disposal Mission Initial Updated Baseline (scope, schedule, and cost) developed to demonstrate the Tank Waste Remediation System contractor's Readiness-to-Proceed in support of the Phase 1B mission

US Department of Energy mixed waste characterization, treatment, and disposal focus area technical baseline development process

International Nuclear Information System (INIS)

Roach, J.A.; Gombert, D.

1996-01-01

The US Department of Energy (DOE) created the Mixed Waste Characterization, Treatment, and Disposal Focus Area (MWFA) to develop and facilitate implementation of technologies required to meet its commitments for treatment of mixed wastes under the Federal Facility Compliance Act (FFCA), and in accordance with the Land Disposal Restrictions (LDR) of the Resource Conservation and Recovery Act (RCRA). Mixed wastes include both mixed low-level waste (MLLW) and mixed transuranic (MTRU) waste. The goal of the MWFA is to develop mixed waste treatment systems to the point of implementation by the Environmental Management (EM) customer. To accomplish this goal, the MWFA is utilizing a three step process. First, the treatment system technology deficiencies were identified and categorized. Second, these identified needs were prioritized. This resulted in a list of technical deficiencies that will be used to develop a technical baseline. The third step, the Technical Baseline Development Process, is currently ongoing. When finalized, the technical baseline will integrate the requirements associated with the identified needs into the planned and ongoing environmental research and technology development activities supported by the MWFA. Completion of this three-step process will result in a comprehensive technology development program that addresses customer identified and prioritized needs. The MWFA technical baseline will be a cost-effective, technically-defensible tool for addressing and resolving DOE's mixed waste problems

Z plant aggregate area management study technical baseline report

International Nuclear Information System (INIS)

DeFord, D.H.; Carpenter, R.W.

1995-05-01

This document was prepared in support of the development of a Aggregate Area Management Study of Z Plant, 200 West Area, at the US Department of Energy (DOE) Hanford Site near Richland, Washington. It provides a technical description and operational history of the aggregate area and results from an environmental investigation undertaken by the Technical Baseline Section of the Environmental Engineering Group, Westinghouse Hanford Company (WHC) which is currently the Waste Site and Facility Research Office, Natural Resources, Bechtel Hanford, Inc. (BHI). It is based upon review and evaluation of numerous Hanford Site current and historical reports, drawings and photographs, supplemented with site inspections and employee interviews. No intrusive field investigations or sampling were conducted in support of this report

Spent Nuclear Fuel Project technical baseline document. Fiscal year 1995: Volume 1, Baseline description

International Nuclear Information System (INIS)

Womack, J.C.; Cramond, R.; Paedon, R.J.

1995-01-01

This document is a revision to WHC-SD-SNF-SD-002, and is issued to support the individual projects that make up the Spent Nuclear Fuel Project in the lower-tier functions, requirements, interfaces, and technical baseline items. It presents results of engineering analyses since Sept. 1994. The mission of the SNFP on the Hanford site is to provide safety, economic, environmentally sound management of Hanford SNF in a manner that stages it to final disposition. This particularly involves K Basin fuel, although other SNF is involved also

U Plant Aggregate Area Management study technical baseline report

International Nuclear Information System (INIS)

DeFord, D.H.; Carpenter, R.W.

1995-05-01

This document was prepared in support of an Aggregate Area Management Study of U Plant. It provides a technical baseline of the aggregate area and results from an environmental investigation that was undertaken by the Technical Baseline Section of the Environmental Engineering Group, Westinghouse Hanford Company (WHC), which is currently the Waste Site and Facility Research Office, Natural Resources, Bechtel Hanford, Inc. (BHI). It is based upon review and evaluation of numerous Hanford Site current and historical reports, drawings and photographs, supplemented with site inspections and employee interviews. U Plant refers to the 221-U Process Canyon Building, a chemical separation facility constructed during World War II. It also includes the Uranium Oxide (UO 3 ) Plant constructed at the same time as 221-U as an adjunct to the original plutonium separation process but which, like 221-U, was converted for other missions. Waste sites are associated primarily with U Plant's 1952 through 1958 Uranium Metal Recovery Program mission and the U0 3 Plant's ongoing U0 3 mission. Waste sites include cribs, reverse wells, french drains, septic tanks and drain fields, trenches, catch tanks, settling tanks, diversion boxes, a waste vault, and the lines and encasements that connect them. It also includes the U Pond and its feed ditches and an underground tank farm designed for high-level liquid wastes

Summary Report for the Technical Interchange Meeting on Development of Baseline Material Properties and Design Guidelines for In-Space Manufacturing Activities

Science.gov (United States)

Prater, T. J.; Bean, Q. A.; Werkheiser, N. J.; Johnston, M. M.; Ordonez, E. A.; Ledbetter, F. E.; Risdon, D. L.; Stockman, T. J.; Sandridge, S. K. R.; Nelson, G. M.

2016-01-01

NASA Marshall Space Flight Center (MSFC) and the Agency as a whole are currently engaged in a number of in-space manufacturing (ISM) activities that have the potential to reduce launch costs, enhance crew safety, and provide the capabilities needed to undertake long-duration spaceflight. The recent 3D Printing in Zero-G experiment conducted on board the International Space Station (ISS) demonstrated that parts of acrylonitrile butadiene styrene (ABS) plastic can be manufactured in microgravity using fused deposition modeling (FDM). This project represents the beginning of the development of a capability that is critical to future NASA missions. Current and future ISM activities will require the development of baseline material properties to facilitate design, analysis, and certification of materials manufactured using in-space techniques. The purpose of this technical interchange meeting (TIM) was to bring together MSFC practitioners and experts in materials characterization and development of baseline material properties for emerging technologies to advise the ISM team as we progress toward the development of material design values, standards, and acceptance criteria for materials manufactured in space. The overall objective of the TIM was to leverage MSFC's shared experiences and collective knowledge in advanced manufacturing and materials development to construct a path forward for the establishment of baseline material properties, standards development, and certification activities related to ISM. Participants were asked to help identify research and development activities that will (1) accelerate acceptance and adoption of ISM techniques among the aerospace design community; (2) benefit future NASA programs, commercial technology developments, and national needs; and (3) provide opportunities and avenues for further collaboration.

Airborne incidents : an econometric analysis of severity, December 31, 2014 : technical summary

Science.gov (United States)

2014-12-31

This is a technical summary of the Airborne Incidents: An Econometric Analysis of Severity main report. : Airborne loss of separation incidents occur when an aircraft breaches the defined separation limit (vertical and/or horizontal) with anoth...

International Linear Collider Technical Design Report (Volumes 1 through 4)

Energy Technology Data Exchange (ETDEWEB)

Harrison M.

2013-03-27

The design report consists of four volumes: Volume 1, Executive Summary; Volume 2, Physics; Volume 3, Accelerator (Part I, R and D in the Technical Design Phase, and Part II, Baseline Design); and Volume 4, Detectors.

Tank waste remediation system retrieval and disposal mission initial updated baseline summary

International Nuclear Information System (INIS)

Swita, W.R.

1998-01-01

This document provides a summary of the Tank Waste Remediation System (TWRS) Retrieval and Disposal Mission Initial Updated Baseline (scope, schedule, and cost), developed to demonstrate Readiness-to-Proceed (RTP) in support of the TWRS Phase 1B mission. This Updated Baseline is the proposed TWRS plan to execute and measure the mission work scope. This document and other supporting data demonstrate that the TWRS Project Hanford Management Contract (PHMC) team is prepared to fully support Phase 1B by executing the following scope, schedule, and cost baseline activities: Deliver the specified initial low-activity waste (LAW) and high-level waste (HLW) feed batches in a consistent, safe, and reliable manner to support private contractors' operations starting in June 2002; Deliver specified subsequent LAW and HLW feed batches during Phase 1B in a consistent, safe, and reliable manner; Provide for the interim storage of immobilized HLW (IHLW) products and the disposal of immobilized LAW (ILAW) products generated by the private contractors; Provide for disposal of byproduct wastes generated by the private contractors; and Provide the infrastructure to support construction and operations of the private contractors' facilities

Fiscal year 1996 U.S. Department of Energy, Richland Operations Office Site summary baseline

International Nuclear Information System (INIS)

Johndro-Collins, A.

1995-10-01

The technical baseline is a hierarchical description of the Hanford Site cleanup mission. This technical baseline does not address the science, technology, or economic transition missions. It begins with a definition of the existing conditions at the Hanford Site, provides a description of the end product or mission accomplishments at completion, presents a statement of the major requirements and constraints that must be observed during the performance of the mission, and provides a statement of the top-level strategic approach to accomplish the mission. Mission-level interfaces are also described. This information is further defined hierarchically in increasing levels of detail. This definition is composed of the following major elements: functions that are key task descriptions; requirements that are the measurable standards to which the functions must be performed; architectures which are specific engineering solutions or systems that perform the functions described earlier; and verification ensuring the system satisfies the requirements and fulfills the functions. The above information is supplemented with the following: interface data; risk analyses and watch lists; assumptions; and required analyses

INDOT Technical Training Plan : [Technical Summary

Science.gov (United States)

2012-01-01

A wide range of job classifications, increasing technical : performance expectations, licensing and certification requirements, : budget restrictions and frequent department : reorganization has made technical training of employees : more difficult, ...

Proceedings of the ninth annual DOE low-level waste management forum: executive summary, technical and special session summaries, attendees

International Nuclear Information System (INIS)

Anon.

1988-01-01

This first volume of proceedings contains summaries of each of six technical sessions as well as three special sessions held during the conference. The six technical sessions were: Disposal technology and facility development (15 papers); Institutional and regulatory issues (10); Performance assessment (14); Waste characterization and verification (7); Site closure and stabilization (6); and Waste treatment (8). The three special sessions were: 1) Review of criteria for guidance on alternative disposal technology; 2) Hazardous waste regulatory update; and 3) Challenges to meeting the 1993 deadline. All papers have been indexed for inclusion on the Energy Data Base

KBS Annual Report 1982. Summaries of technical reports issued during 1982

International Nuclear Information System (INIS)

1983-07-01

The purpose of the KBS Annual Report is to inform interested organizations and individuals of the research and development work perfomed by the division KBS within the Swedish Nuclear Fuel Supply Co. (SKBF) on the handling, treatment and final storage of nuclear wastes in Sweden. In the Annual Report for 1982 the summaries of 27 technical reports and other publications issued during the year are listed. (K.A.E.)

2011 PERFORMANCE ASSESSMENT COMMUNITY OF PRACTICE TECHNICAL EXCHANGE - SUMMARY

Energy Technology Data Exchange (ETDEWEB)

Seitz, R.

2011-12-30

The Performance Assessment Community of Practice (PA CoP) was developed in 2008 to improve consistency and quality in the preparation of performance assessments (PAs) and risk assessments across the Department of Energy (DOE) Complex. The term, PA, is used to represent all of these modeling applications in this report. The PA CoP goals are to foster the exchange of information among PA practitioners and to share lessons learned from PAs conducted for DOE, commercial disposal facilities, and international entities. Technical exchanges and workshops are a cornerstone of PA CoP activities. Previous technical exchanges have addressed Engineered Barriers (2009 - http://www.cresp.org/education/workshops/pacop/), the Advanced Simulation Capability for Environmental Management and the Cementitious Barriers Partnership (2010 - http://srnl.doe.gov/copexchange/links.htm). Each technical exchange also includes summary presentations regarding activities at DOE, the Nuclear Regulatory Commission (NRC) and other organizations (e.g., International Atomic Energy Agency (IAEA)) as well as a number of presentations from selected sites to provide insight and perspective from on-going modeling activities. Through the deployment of PA Assistance Teams, the PA CoP has also been engaged in the development of new PAs across the DOE Complex. As a way of improving consistency in the preparation of new PAs, the teams provide technical advice and share experiences, noteworthy practices, and lessons learned from previous Low-Level Waste Disposal Facility Federal Review Group (LFRG) reviews. Teams have provided support for PAs at Hanford, Idaho, Paducah and Portsmouth. The third annual PA CoP Technical Exchange was held on May 25-26, 2011 in Atlanta, GA. The PA CoP Steering Committee Meeting held its first meeting on May 24 prior to the Technical Exchange. Decision making using models and software quality assurance were the topical emphasis for the exchange. A new feature at the 2011 technical

Yucca Mountain Project: A summary of technical support activities, January 1987--June 1988

International Nuclear Information System (INIS)

1989-05-01

This report is a summary of the technical support activities of Mifflin ampersand Associates, Inc., during the 18-month period beginning 01 January 1987 and ending on 30 June 1988. It covers the following topics: Vadose zone drilling site selection, permits and quality assurance (QA) procedures; climate change; geochemistry, mineralogy; disturbed zone; hydrogeology; and review of technical documents. The report is organized by generally discussing each topic from the following perspectives: issue(s), objective(s) of activity, finding(s), interpretation of finding(s), additional work needed, recommended program, and existing program

Summary report of technical meeting on neutron cross section covariances

International Nuclear Information System (INIS)

Trkov, A.; Smith, D.L.; Capote Noy, R.

2011-01-01

A summary is given of the Technical Meeting on Neutron Cross Section Covariances. The meeting goal was to assess covariance data needs and recommend appropriate methodologies to address those needs. Discussions on covariance data focused on three general topics: 1) Resonance and unresolved resonance regions; 2) Fast neutron region; and 3) Users' perspective: benchmarks' uncertainty and reactor dosimetry. A number of recommendations for further work were generated and the important work that remains to be done in the field of covariances was identified. (author)

Preliminary technical data summary defense waste processing facility stage 2

International Nuclear Information System (INIS)

1980-12-01

This Preliminary Technical Data Summary presents the technical basis for design of Stage 2 of the Staged Defense Waste Processing Facility (DWPF). Process changes incorporated in the staged DWPF relative to the Alternative DWPF described in PTDS No. 3 (DPSTD-77-13-3) are the result of ongoing research and development and are aimed at reducing initial capital investment and developing a process to efficiently immobilize the radionuclides in Savannah River Plant (SRP) high-level liquid waste. The radionuclides in SRP waste are present in sludge that has settled to the bottom of waste storage tanks and in crystallized salt and salt solution (supernate). Stage 1 of the DWPF receives washed, aluminum dissolved sludge from the waste tank farms and immobilizes it in a borosilicate glass matrix. The supernate is retained in the waste tank farms until completion of Stage 2 of the DWPF at which time it is filtered and decontaminated by ion exchange in the Stage 2 facility. The decontaminated supernate is concentrated by evaporation and mixed with cement for burial. The radioactivity removed from the supernate is fixed in borosilicate glass along with the sludge. This document gives flowsheets, material and curie balances, material and curie balance bases, and other technical data for design of Stage 2 of the DWPF. Stage 1 technical data are presented in DPSTD-80-38

Critical evaluation of the nonradiological environmental technical specifications. Program description, summary, and recommendations. Vol. 1

International Nuclear Information System (INIS)

Adams, S.M.; Cunningham, P.A.; Gray, D.D.; Kumar, K.D.; Witten, A.J.

1976-01-01

A comprehensive study of the data collected as part of the environmental Technical Specifications program for eight nuclear power plants was conducted for the Office of Nuclear Regulatory Research of the U.S. Nuclear Regulatory commission. This report includes a summary of the screening phase in which the adequacy of the hydrothermal and ecological monitoring data for each plant were evaluated, and the summary and recommendations resulting from a detailed examination of the three nuclear power plants selected in the initial screening

PUREX Plant aggregate area management study technical baseline report

International Nuclear Information System (INIS)

DeFord, D.H.; Carpenter, R.W.

1995-05-01

The PUREX aggregate area is made up of six operable units; 200-PO-1 through 200-PO-6 and consists of liquid and solid waste disposal sites in the vicinity of, and related to, PUREX Plant operations. This report describes PUREX and its waste sites, including cribs, french drains, septic tanks and drain fields, trenches and ditches, ponds, catch tanks, settling tanks, diversion boxes, underground tank farms, and the lines and encasements that connect them. Each waste site in the aggregate area is described separately. Close relationships between waste units, such as overflow from one to another, are also discussed. This document provides a technical baseline of the aggregate area and results from an environmental investigation. This document is based upon review and evaluation of numerous Hanford Site current and historical reports, drawings and photographs, supplemented with site inspections and employee interviews. No intrusive field investigations or sampling were conducted

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

Eleventh annual U.S. DOE low-level radioactive waste management conference: Executive summary, opening plenary, technical session summaries, and attendees

Energy Technology Data Exchange (ETDEWEB)

NONE

1990-01-01

The conference consisted of ten technical sessions, with three sessions running simultaneously each day. Session topics included: regulatory updates; performance assessment;understanding remedial action efforts; low-level waste strategy and planning (Nuclear Energy); low-level waste strategy and planning (Defense); compliance monitoring; decontamination and decommissioning; waste characterization; waste reduction and minimization; and prototype licensing application workshop. Summaries are presented for each of these sessions.

B Plant aggregate area management study technical baseline report

International Nuclear Information System (INIS)

DeFord, D.H.; Carpenter, R.W.

1995-05-01

The B aggregate area is made up of 13 operable units; 200-BP 1 through 200-BP 1 1, 200-IU-6, and 200-SS-1 that consist of liquid and solid waste disposal sites in the vicinity of, and related to, B Plant operations. This report describes B Plant and its waste sites, including cribs, french drains, septic tanks and drain fields, trenches and ditches, ponds, catch tanks, settling tanks, diversion boxes, underground tank farms designed for high-level liquid wastes, and the lines and encasements that connect them. Each waste site in the aggregate area is described separately. Close relationships between waste units, such as overflow from one to another, are also discussed. This document provides a technical baseline of the aggregate area and results from an environmental investigation. This document is based upon review and evaluation of numerous Hanford Site current and historical reports, drawings and photographs, supplemented with site inspections and employee interviews. No intrusive field investigations or sampling were conducted

Preliminary technical data summary for the Defense Waste Processing Facility, Stage 1

International Nuclear Information System (INIS)

1980-09-01

This Preliminary Technical Data Summary presents the technical basis for design of Stage 1 of the Staged Defense Waste Processing Facility (DWPF), a process to efficiently immobilize the radionuclides in Savannah River Plant (SRP) high-level liquid waste. The radionuclides in SRP waste are present in sludge that has settled to the bottom of waste storage tanks and in crystallized salt and salt solution (supernate). Stage 1 of the DWPF receives washed, aluminum dissolved sludge from the waste tank farms and immobilizes it in a borosilicate glass matrix. The supernate is retained in the waste tank farms until completion of Stage 2 of the DWPF at which time it filtered and decontaminated by ion exchange in the Stage 2 facility. The decontaminated supernate is concentrated by evaporation and mixed with cement for burial. The radioactivity removed from the supernate is fixed in borosilicate glass along with the sludge. This document gives flowsheets, material, and curie balances, material and curie balance bases, and other technical data for design of the Stage 1 DWPF

Estimating the cold war mortgage: The 1995 baseline environmental management report. Volume II: Site summaries

International Nuclear Information System (INIS)

1995-03-01

This volume, Volume II presents the site data that was used to generate the Department of Energy's (DOE) initial Baseline Environmental Management Report (BEMR). The raw data was obtained by DOE field personnel from existing information sources and anticipated environmental management strategies for their sites and was tempered by general assumptions and guidance developed by DOE Headquarters personnel. This data was then integrated by DOE Headquarters personnel and modified to ensure that overall constraints such as funding and waste management capacity were addressed. The site summaries are presented by State and broken out by discrete activities and projects. The Volume I Glossary has been repeated to facilitate the reader's review of Volume II. The information presented in the site summaries represents the best data and assumptions available as of February 1, 1995. Assumptions that have not been mandated by formal agreement with appropriate regulators and other stakeholders do not constitute decisions by the Department nor do they supersede existing agreements. In addition, actions requiring decisions from external sources regarding unknowns such as future land use and funding/scheduling alternatives, as well as internal actions such as the Department's Strategic Realignment initiative, will alter the basis and general assumptions used to generate the results for this report. Consequently, the numbers presented in the site summaries do not represent outyear budget requests by the field installations

The Agency's Technical Co-operation programme with Algeria, 1982-1992. Country programme summaries

International Nuclear Information System (INIS)

1992-01-01

The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With $3.6 million of Agency support received, Algeria ranks 41st among all recipients of technical assistance in the period 1958-1991. Seventy per cent of the assistance received during the past ten years has been in the form of equipment, followed by expert services (17%) and training (13%). Almost all of the resources were provided by the Technical Assistance and Co-operation Fund (97%), the remaining 3% were made available through assistance in kind. With regard to project disbursement by sector, the three major areas have been nuclear physics and chemistry (28%), agriculture (27%) and nuclear medicine (20%)

Summary Report of the Technical Meeting on International Network of Nuclear Reaction Data Centres

International Nuclear Information System (INIS)

Otsuka, Naohiko

2013-07-01

This report summarizes the IAEA Technical Meeting on the International Network of Nuclear Reaction Data Centres, held at the IAEA Headquarters in Vienna, Austria from 23 to 25 April 2013. The meeting was attended by 24 participants representing 13 cooperative centres from 8 Member States and 2 International Organisations. A summary of the meeting is given in this report along with the conclusions and actions. (author)

Technical summary of geological, hydrological, and engineering studies at the Slick Rock Uranium Mill Tailings sites, Slick Rock, Colorado

International Nuclear Information System (INIS)

1990-12-01

The purpose of this document is to provide the Colorado Department of Health (CDH) with a summary of the technical aspects of the proposed remedial action for the Slick Rock tailings near Slick Rock, Colorado. The technical issues summarized in this document are the geology and groundwater at the Burro Canyon disposal site and preliminary engineering considerations for the disposal cell

The Agency's Technical Co-operation programme with Niger, 1982-1992. Country programme summaries

International Nuclear Information System (INIS)

1992-01-01

The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With some $1.5 million of Agency support received, Niger ranks 65th among all recipients of technical assistance in the period 1958 through 1991. About two-thirds of the assistance received during the past ten years has been provided in the form of equipment (62%), complemented by expert services (26%) and training (12%). Almost the entire resources utilized were provided by the Technical Assistance and Co-operation Fund (96%), with only a small share made available through assistance in kind (4%). With regard to project disbursements by sector, the four major areas have been agriculture (34%), general atomic energy development (31%), hydrology (18%) and nuclear safety (12%)

Analysis of factors affecting baseline SF-36 Mental Component Summary in Adult Spinal Deformity and its impact on surgical outcomes.

Science.gov (United States)

Mmopelwa, Tiro; Ayhan, Selim; Yuksel, Selcen; Nabiyev, Vugar; Niyazi, Asli; Pellise, Ferran; Alanay, Ahmet; Sanchez Perez Grueso, Francisco Javier; Kleinstuck, Frank; Obeid, Ibrahim; Acaroglu, Emre

2018-03-01

To identify the factors that affect SF-36 mental component summary (MCS) in patients with adult spinal deformity (ASD) at the time of presentation, and to analyse the effect of SF-36 MCS on clinical outcomes in surgically treated patients. Prospectively collected data from a multicentric ASD database was analysed for baseline parameters. Then, the same database for surgically treated patients with a minimum of 1-year follow-up was analysed to see the effect of baseline SF-36 MCS on treatment results. A clinically useful SF-36 MCS was determined by ROC Curve analysis. A total of 229 patients with the baseline parameters were analysed. A strong correlation between SF-36 MCS and SRS-22, ODI, gender, and diagnosis were found (p baseline SF-36 MCS (p baseline SF-36 MCS in an ASD population are other HRQOL parameters such as SRS-22 and ODI as well as the baseline thoracic kyphosis and gender. This study has also demonstrated that baseline SF-36 MCS does not necessarily have any effect on the treatment results by surgery as assessed by SRS-22 or ODI. Level III, prognostic study. Copyright © 2018 Turkish Association of Orthopaedics and Traumatology. Production and hosting by Elsevier B.V. All rights reserved.

Summary report on [IAEA] technical meeting of the International Network of Nuclear Reaction Data Centres

International Nuclear Information System (INIS)

Dunaeva, S.; Otsuka, N.; Schwerer, O.

2009-08-01

An IAEA Technical Meeting of the International Network of Nuclear Reaction Data Centres was held at the IAEA Headquarters in Vienna from 25 to 26 May 2009. The meeting was attended by 23 participants from 13 cooperating data centres. A summary of the meeting is given in this report, along with the conclusions, actions, and status report of the participating data centres. (author)

Summary of the technical guidelines used in the project: The economics of greenhouse gas limitations

International Nuclear Information System (INIS)

Halsnaes, Kirsten

1998-01-01

This document is a summary version of the technical guidelines for climate change mitigation assessment developed as a part of the Global Environment Facility (GEF) project The Economics of Greenhouse Gas Limitations; Technical guidelines (UNEP 1998). The objectives of this project have been to support the development of a methodology, an implementing framework and a reporting system which countries can use in the construction of national climate change policies and in meeting their future reporting obligations under the FCCC. The methodological framework developed in the guidelines covers key economic concepts, scenario building, modelling tools and common assumptions. It was used by several country studies included in the project. (au)

The International Linear Collider Technical Design Report - Volume 3.II: Accelerator Baseline Design

CERN Document Server

Adolphsen, Chris; Barish, Barry; Buesser, Karsten; Burrows, Philip; Carwardine, John; Clark, Jeffrey; Durand, Helene Mainaud; Dugan, Gerry; Elsen, Eckhard; Enomoto, Atsushi; Foster, Brian; Fukuda, Shigeki; Gai, Wei; Gastal, Martin; Geng, Rongli; Ginsburg, Camille; Guiducci, Susanna; Harrison, Mike; Hayano, Hitoshi; Kershaw, Keith; Kubo, Kiyoshi; Kuchler, Victor; List, Benno; Liu, Wanming; Michizono, Shinichiro; Nantista, Christopher; Osborne, John; Palmer, Mark; Paterson, James McEwan; Peterson, Thomas; Phinney, Nan; Pierini, Paolo; Ross, Marc; Rubin, David; Seryi, Andrei; Sheppard, John; Solyak, Nikolay; Stapnes, Steinar; Tauchi, Toshiaki; Toge, Nobu; Walker, Nicholas; Yamamoto, Akira; Yokoya, Kaoru

2013-01-01

The International Linear Collider Technical Design Report (TDR) describes in four volumes the physics case and the design of a 500 GeV centre-of-mass energy linear electron-positron collider based on superconducting radio-frequency technology using Niobium cavities as the accelerating structures. The accelerator can be extended to 1 TeV and also run as a Higgs factory at around 250 GeV and on the Z0 pole. A comprehensive value estimate of the accelerator is give, together with associated uncertainties. It is shown that no significant technical issues remain to be solved. Once a site is selected and the necessary site-dependent engineering is carried out, construction can begin immediately. The TDR also gives baseline documentation for two high-performance detectors that can share the ILC luminosity by being moved into and out of the beam line in a "push-pull" configuration. These detectors, ILD and SiD, are described in detail. They form the basis for a world-class experimental programme that promises to incr...

Summary of Technical Sessions - Summary and Recommendations

International Nuclear Information System (INIS)

2013-01-01

Technical Session 1 - Development achievements of BEPU methods and State of the Art: The objective of this session was to present the different approaches dealing with Best Estimate codes and uncertainties evaluations. Existing methods were summarized and different papers were focused on specific methods stressing their bases, peculiarities, advantages and limitations. As a result of the session a picture of the current State of the Art was obtained. The session comprised six papers. Technical Session 2 - International comparative activities: This session had as a main objective to review the activities launched in the past and present from the NEA in connection with BEPU methods, with focus on the applicability of conclusions derived from former benchmarks like UMS, the main outcomes of the recently finished BEMUSE project, and the objectives and relevance of UAM and PREMIUM projects. The session comprised four papers. Technical Session 3 - Applications: Licensing, safety analysis support, regulatory body views and industry activities: This session focused on the application of current methods in safety analyses. Contributions from industry, technical safety organizations and regulatory bodies were provided. As a result, a view of the penetration of BEPU methods in current safety analyses was obtained, as well as an indication of the evolution in the near future. Elements such as licensing practices, assessment process, etc. were considered. The session comprised nine papers. Technical Session 4. BEPU methods extension to new fields The session addressed the extension of BEPU methods beyond their current use. By now such methods are mainly applied to classic deterministic environment but it is believed that their benefits could be extended to other fields. Seven papers were presented in the session dealing with subjects that fit in the objectives established in the workshop programme. The papers cover areas like: extension to CFD, quantification of global safety

Revision of the European Ecolabel Criteria for Personal, Notebook and Tablet Computers TECHNICAL REPORT Summary of the final criteria proposals

OpenAIRE

DODD NICHOLAS; VIDAL ABARCA GARRIDO CANDELA; WOLF Oliver; GRAULICH Kathrin; BUNKE Dirk; GROSS Rita; LIU Ran; MANHART Andreas; PRAKASH Siddharth

2015-01-01

This technical report provide the background information for the revision of the EU Ecolabel criteria for Personal and Notebook Computers. The study has been carried out by the Joint Research Centre with technical support from the Oeko-Institut. The work has been developed for the European Commission's Directorate General for the Environment. The main purpose of this report is to provide a summary of the technical background and rationale for each criterion proposal. This document is compl...

Program Baseline Change Control Procedure

International Nuclear Information System (INIS)

1993-02-01

This procedure establishes the responsibilities and process for approving initial issues of and changes to the technical, cost, and schedule baselines, and selected management documents developed by the Office of Civilian Radioactive Waste Management (OCRWM) for the Civilian Radioactive Waste Management System. This procedure implements the OCRWM Baseline Management Plan and DOE Order 4700.1, Chg 1. It streamlines the change control process to enhance integration, accountability, and traceability of Level 0 and Level I decisions through standardized Baseline Change Proposal (BCP) forms to be used by the Level 0, 1, 2, and 3 Baseline Change Control Boards (BCCBs) and to be tracked in the OCRWM-wide Configuration Information System (CIS) Database.This procedure applies to all technical, cost, and schedule baselines controlled by the Energy System Acquisition Advisory Board (ESAAB) BCCB (Level 0) and, OCRWM Program Baseline Control Board (PBCCB) (Level 1). All baseline BCPs initiated by Level 2 or lower BCCBs, which require approval from ESAAB or PBCCB, shall be processed in accordance with this procedure. This procedure also applies to all Program-level management documents controlled by the OCRWM PBCCB

Summary Report of the Technical Meeting on International Network of Nuclear Reaction Data Centres

International Nuclear Information System (INIS)

Otsuka, Naohiko

2012-06-01

This report summarizes the IAEA Technical Meeting on the International Network of Nuclear Reaction Data Centres, held at the OECD Nuclear Energy Agency (NEA) in Issy-les-Moulineaux, France from 16 to 19 April 2012. The meeting was attended by twenty-three participants representing thirteen cooperative centres from eight Member States and two International Organisations. A summary of the meeting is given in this report along with the conclusions and actions. (author)

The Agency's Technical Co-operation programme with Ethiopia, 1982-1992. Country programme summaries

International Nuclear Information System (INIS)

1992-01-01

The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With some $2.5 million of Agency support received, Ethiopia ranks 54th among all recipients of technical assistance in the period 1958 through 1991. More than half of the assistance received during the past ten years has been provided in the form of equipment (55%), complemented by expert services (16%) and training (29%). The best part of the resources was provided by the Technical Assistance and Co-operation Fund (88%), the remainder was made available through assistance in kind (6%), UNDP and extrabudgetary contributions (3% each). During the past ten years, project disbursements went to four major areas: agriculture (45%), nuclear medicine (35%), nuclear safety (14%) and nuclear engineering and technology (6%)

The Agency's Technical Co-operation programme with Uganda, 1982-1992. Country programme summaries

International Nuclear Information System (INIS)

1992-01-01

The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With $1.6 million of Agency support received, Uganda ranks 61st among all recipients of technical assistance in the period 1958 through 1991. Almost half of the assistance received during the past ten years has been provided in the form of equipment (47%), complemented by a strong training component (37%), while expert services have received only a relatively small share (16%). Ninety-eight per cent of the resources were provided by the Technical Assistance and Co-operation Fund, the remaining two per cent were made available through assistance in kind. During the past ten years, project activities - and disbursements - have concentrated exclusively on three major areas: agriculture (64%), nuclear medicine (24%) and nuclear safety (12%)

The Agency's Technical Co-operation programme with Cameroon, 1982-1992. Country programme summaries

International Nuclear Information System (INIS)

1992-01-01

The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With $1.3 million of Agency support received, Cameroon ranks 68th among all recipients of technical assistance in the period 1958 through 1991. More than half of the assistance received during the past ten years has been provided in the form of equipment (61%), followed by expert services (24%) and training (15%). The best part of the resources were provided by the Technical Assistance and Co-operation Fund (90%); the remaining ten per cent were made available through extrabudgetary contributions (8%) and assistance in kind (2%). With regard to project disbursements by sector, the four major areas have been nuclear physics and chemistry (38%), agriculture (23%), nuclear medicine (14%) and hydrology (13%)

Mixed Methods in Education Research. IES Technical Working Group Meeting. Meeting Summary (Washington, DC, May 29, 2015)

Science.gov (United States)

Institute of Education Sciences, 2015

2015-01-01

This meeting summary is organized into two major sections. The first section captures the individual contribution of meeting participants, including both Institute of Education Sciences (IES) staff and the invited technical working group members. The second section captures themes that arose during the group discussions, which were organized…

The Agency's technical co-operation programme with Ecuador 1983-1993 country programme summaries

International Nuclear Information System (INIS)

1993-01-01

This report contains a review of the Agency's technical co-operation activities in Ecuador carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with Thailand 1984-1994 country programme summaries

International Nuclear Information System (INIS)

1994-01-01

This report contains a review of the Agency's technical co-operation activities in Thailand carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with Malaysia 1984-1994 country programme summaries

International Nuclear Information System (INIS)

1994-01-01

This report contains a review of the Agency's technical co-operation activities in Malaysia carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with Pakistan 1985-1995 country programme summaries

International Nuclear Information System (INIS)

1995-01-01

This report contains a review of the Agency's technical co-operation activities in Pakistan carried out during 1985-1995. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with Nigeria 1986-1996 country programme summaries

International Nuclear Information System (INIS)

1996-01-01

This report contains a review of the Agency's technical co-operation activities in Nigeria carried out during 1986-1996. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with Colombia 1983-1993 country programme summaries

International Nuclear Information System (INIS)

1993-01-01

This report contains a review of the Agency's technical co-operation activities in Colombia carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with Portugal 1984-1994 country programme summaries

International Nuclear Information System (INIS)

1994-01-01

This report contains a review of the Agency's technical co-operation activities in Portugal carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with Jamaica 1983-1993 country programme summaries

International Nuclear Information System (INIS)

1993-01-01

This report contains a review of the Agency's technical co-operation activities in Jamaica carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with Bolivia 1983-1993 country programme summaries

International Nuclear Information System (INIS)

1993-01-01

This report contains a review of the Agency's technical co-operation activities in Bolivia carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with Panama 1983-1993 country programme summaries

International Nuclear Information System (INIS)

1993-01-01

This report contains a review of the Agency's technical co-operation activities in Panama carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with Bangladesh 1984-1994 country programme summaries

International Nuclear Information System (INIS)

1994-01-01

This report contains a review of the Agency's technical co-operation activities in Bangladesh carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with Panama 1985-1995 country programme summaries

International Nuclear Information System (INIS)

1995-01-01

This report contains a review of the Agency's technical co-operation activities in Panama carried out during 1985-1995. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with Guatemala 1985-1995 country programme summaries

International Nuclear Information System (INIS)

1995-01-01

This report contains a review of the Agency's technical co-operation activities in Guatemala carried out during 1985-1995. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with Iceland 1984-1994 country programme summaries

International Nuclear Information System (INIS)

1994-01-01

This report contains a review of the Agency's technical co-operation activities in Iceland carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with Bangladesh 1983-1993 country programme summaries

International Nuclear Information System (INIS)

1993-01-01

This report contains a review of the Agency's technical co-operation activities in Bangladesh carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with Cyprus 1984-1994 country programme summaries

International Nuclear Information System (INIS)

1994-01-01

This report contains a review of the Agency's technical co-operation activities in Cyprus carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with Albania 1984-1994 country programme summaries

International Nuclear Information System (INIS)

1994-01-01

This report contains a review of the Agency's technical co-operation activities in Albania carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with Indonesia 1984-1994 country programme summaries

International Nuclear Information System (INIS)

1994-01-01

This report contains a review of the Agency's technical co-operation activities in Indonesia carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with Poland 1983-1993 country programme summaries

International Nuclear Information System (INIS)

1993-01-01

This report contains a review of the Agency's technical co-operation activities in Poland carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with Romania 1983-1993 country programme summaries

International Nuclear Information System (INIS)

1993-01-01

This report contains a review of the Agency's technical co-operation activities in Romania carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with Greece 1983-1993 country programme summaries

International Nuclear Information System (INIS)

1993-01-01

This report contains a review of the Agency's technical co-operation activities in Greece carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with Nicaragua 1983-1993 country programme summaries

International Nuclear Information System (INIS)

1993-01-01

This report contains a review of the Agency's technical co-operation activities in Nicaragua carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with Afghanistan 1983-1993 country programme summaries

International Nuclear Information System (INIS)

1993-01-01

This report contains a review of the Agency's technical co-operation activities in Afghanistan carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with Bolivia 1986-1996 country programme summaries

International Nuclear Information System (INIS)

1996-01-01

This report contains a review of the Agency's technical co-operation activities in Bolivia carried out during 1986-1996. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with Myanmar 1985-1995 country programme summaries

International Nuclear Information System (INIS)

1995-01-01

This report contains a review of the Agency's technical co-operation activities in Myanmar carried out during 1985-1995. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with Jordan 1983-1993 country programme summaries

International Nuclear Information System (INIS)

1993-01-01

This report contains a review of the Agency's technical co-operation activities in Jordan carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with Hungary 1983-1993 country programme summaries

International Nuclear Information System (INIS)

1993-01-01

This report contains a review of the Agency's technical co-operation activities in Hungary carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with Egypt 1985-1995 country programme summaries

International Nuclear Information System (INIS)

1995-01-01

This report contains a review of the Agency's technical co-operation activities in Egypt carried out during 1985-1995. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with Mongolia 1985-1995 country programme summaries

International Nuclear Information System (INIS)

1995-01-01

This report contains a review of the Agency's technical co-operation activities in Mongolia carried out during 1985-1995. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with Paraguay 1983-1993 country programme summaries

International Nuclear Information System (INIS)

1993-01-01

This report contains a review of the Agency's technical co-operation activities in Paraguay carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with Mexico 1986-1996 country programme summaries

International Nuclear Information System (INIS)

1996-01-01

This report contains a review of the Agency's technical co-operation activities in Mexico carried out during 1986-1996. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with Paraguay 1984-1994 country programme summaries

International Nuclear Information System (INIS)

1994-01-01

This report contains a review of the Agency's technical co-operation activities in Paraguay carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's Technical Co-operation programme with Guatemala, 1982-1992. Country programme summaries

International Nuclear Information System (INIS)

1992-01-01

The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $3 million of Agency support received, Guatemala ranks 46th among all recipients of technical assistance in the period 1958 - 1991. Almost three quarters of the assistance during the past ten years has been provided in the form of equipment (72%), followed by training (15%) and expert services (13%). Seventy-eight per cent of the resources were provided by the Technical Assistance and Co-operation Fund, the rest was made available through extrabudgetary contributions (21%) and assistance in kind (1%). With regard to project disbursement by sector, the largest areas have been nuclear physics and chemistry (37%), agriculture (28%), nuclear medicine (16%) and hydrology (8%). The remaining 11% were shared by general atomic energy development, nuclear raw materials, nuclear engineering and technology, and nuclear safety

The Agency's Technical Co-operation programme with Uruguay, 1982-1992. Country programme summaries

International Nuclear Information System (INIS)

1992-01-01

The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $4.2 million of Agency support received, Uruguay ranks 37th among all recipients of technical assistance in the period 1958 - 1991. More than half of the assistance during the past ten years has been provided in the form of equipment (67%), followed by expert services (19%) and training (14%). Seventy-three per cent of the resources were provided through the Technical Assistance and Co-operation Fund, while 24% were made available through extrabudgetary contributions. The remaining 3% were provided through assistance in kind, with only an insignificant contribution by UNDP. With regard to project disbursement by sector, the largest areas have been nuclear medicine (35%), agriculture (23%), general atomic energy development (17%), followed by nuclear physics and chemistry (11%) and industry and hydrology (7%)

The Agency's Technical Co-operation programme with Kenya, 1982-1992. Country programme summaries

International Nuclear Information System (INIS)

1992-01-01

The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With almost $3.9 million of Agency support received, Kenya ranks 39th among all recipients of technical assistance during the period 1958-1991. Almost half of the assistance during the past ten years has been provided in the form of the equipment (44%), followed by training (33%) and expert services (23%). Two-thirds of the funds available were provided by the Technical Assistance and Co-operation Fund (66%), while extra-budgetary contributions accounted for 18%, in-kind contributions for 14%, and UNDP for 2% of the resources. With regard to project disbursements during the past ten years, by sector, the four major areas have been general atomic energy development (30%), agriculture (22%), nuclear medicine and nuclear safety (13% each)

The Agency's Technical Co-operation programme with Mali, 1982-1992. Country programme summaries

International Nuclear Information System (INIS)

1992-01-01

The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $2.7 million of Agency support received, Mali ranks 51st among all recipients of technical assistance in the period 1958 through 1991. More than half of the assistance during the past ten years has been provided in the form of equipment (58%), followed by expert services (27%) and training (15%). With a share of 93%, the Technical Assistance and Co-operation Fund has provided the best part of the resources, while only very small shares were made available through extrabudgetary contributions and assistance in kind (5% and 2%, respectively). With regard to project disbursements during the past ten years, by sector, the four major areas have been hydrology (31%), nuclear medicine (24%), agriculture (21%) and nuclear raw materials (16%)

The Agency's Technical Co-operation programme with Zambia, 1982-1992. Country programme summaries

International Nuclear Information System (INIS)

1992-01-01

The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With $5.5 million of Agency support received, Zambia ranks 33rd among all recipients of technical assistance in the period 1958 through 1991. More than half of the assistance during the past ten years has been provided in the form of equipment (61%), followed by expert services (25%) and training (14%). Almost all of the resources made available came from the Technical Assistance and Co-operation Fund (93%), with only very small shares provided through extrabudgetary contributions (4%) and assistance in kind (3%). With regard to project disbursements during the past ten years, by sector, the largest areas have been agriculture (33%) and general atomic energy development (23%), followed by industry and hydrology (19%), nuclear raw materials (13%) and nuclear safety (6%)

The Agency's Technical Co-operation programme with Senegal, 1982-1992. Country programme summaries

International Nuclear Information System (INIS)

1992-01-01

The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With $2.2 million of Agency support received, Senegal ranks 56th among all recipients of technical assistance in the period 1958 - 1991. More than one-third of the assistance during the past ten years has been provided in the form of equipment (67%), followed by expert services (21%) and training (12%). Eighty per cent of the resources were provided by the Technical Assistance and Co-operation Fund, while 16% were made available by UNDP and about 2% each through extrabudgetary contributions and assistance in kind. With regard to project disbursement by sector, by far the largest area has been agriculture (43%). Smaller shares have gone to general atomic energy development (15%), nuclear physics and chemistry (13%), nuclear medicine and hydrology (11% each), and nuclear safety (7%)

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

The International Linear Collider Technical Design Report - Volume 3.II: Accelerator Baseline Design

Energy Technology Data Exchange (ETDEWEB)

Adolphsen, Chris [SLAC National Accelerator Lab., Menlo Park, CA (United States); et al.

2013-06-26

The International Linear Collider Technical Design Report (TDR) describes in four volumes the physics case and the design of a 500 GeV centre-of-mass energy linear electron-positron collider based on superconducting radio-frequency technology using Niobium cavities as the accelerating structures. The accelerator can be extended to 1 TeV and also run as a Higgs factory at around 250 GeV and on the Z0 pole. A comprehensive value estimate of the accelerator is give, together with associated uncertainties. It is shown that no significant technical issues remain to be solved. Once a site is selected and the necessary site-dependent engineering is carried out, construction can begin immediately. The TDR also gives baseline documentation for two high-performance detectors that can share the ILC luminosity by being moved into and out of the beam line in a "push-pull" configuration. These detectors, ILD and SiD, are described in detail. They form the basis for a world-class experimental programme that promises to increase significantly our understanding of the fundamental processes that govern the evolution of the Universe.

Summary Report on IAEA Technical Meeting on the International Network of Nuclear Reaction Data Centres

International Nuclear Information System (INIS)

Otsuka, Naohiko

2011-07-01

This report summarizes the IAEA Technical Meeting of the International Network of Nuclear Reaction Data Centres, held at the IAEA Headquarters in Vienna, Austria from 23 - 24 May 2011. The meeting was attended by 25 participants from 13 cooperating data centres of nine Member States and two International Organizations. The report contains a summary of the meeting, the conclusions and actions, the lists of working papers and presentations presented at the meeting. (author)

The Agency's Technical Co-operation programme with Mexico, 1982-1992. Country programme summaries

International Nuclear Information System (INIS)

1992-01-01

The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With almost $7.7 million of Agency support received, Mexico ranks 21st among all recipients of technical assistance during the period 1958 through 1991. The largest share of the assistance received during the past ten years has been in the form of expert services (36%), followed by equipment and training (27% each) and sub-contracts (10%). Almost two-thirds of the funds available were provided by the Technical Assistance and Co-operation Fund (65%), the rest was made available through extrabudgetary contributions (21%) and assistance in kind (14%). With regard to project disbursements during the past ten years, by sector the five major areas have been nuclear safety (34%), nuclear engineering and technology (27%), agriculture (17%), nuclear physics and chemistry (9%), and nuclear techniques in industry and hydrology (9%)

The Agency's Technical Co-operation programme with Zaire, 1982-1992. Country programme summaries

International Nuclear Information System (INIS)

1992-01-01

The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With $3.9 million of Agency support received, Zaire ranks 38th among all recipients of technical assistance in the period 1958 through 1991. More than half of the assistance during the past ten years has been provided in the form of equipment (60%), followed by training (24%) and expert services (16%). With a share of 76%, the Technical Assistance and Co-operation Fund has provided more than three quarters of the total resources available, while only small shares were made available through UNDP (11%), extrabudgetary contributions (4%) and assistance in kind (9%). With regard to project disbursements during the past ten years, by sector, the largest area has been general atomic energy development (26%), followed by agriculture (18%), nuclear safety (18%), nuclear techniques in industry and hydrology (13%), and nuclear physics and chemistry (11%)

The Agency's Technical Co-operation programme with Nigeria, 1982-1992. Country programme summaries

International Nuclear Information System (INIS)

1992-01-01

The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $9.3 million of Agency support received, Nigeria ranks 14th among all recipients of technical assistance in the period 1958 through 1991. During the past ten years, 44% of this assistance has been provided in the form of equipment, followed by training (27%), expert services (26%) and sub-contracts (3%). With 45% and 44%, respectively, the Technical Assistance and Co-operation Fund and extrabudgetary contributions hold almost equal shares in the total resources made available, while in-kind assistance accounts for 9% and UNDP for 2% of the resources. With regard to project disbursement during the past ten years, by sector, by far the largest area has been agriculture (70%), with significantly smaller shares going to nuclear physics and chemistry (11%), nuclear medicine (8%) and nuclear safety (7%)

The Agency's Technical Co-operation programme with Sierra Leone, 1982-1992. Country programme summaries

International Nuclear Information System (INIS)

1992-01-01

The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $1.1 million of Agency support received, Sierra Leone ranks 70th among all recipients of technical assistance in the period 1958 through 1991. Almost equal shares of the assistance during the past ten years have been provided in the form of equipment (40%) and expert services (37%), while the share of the training component was 23%. The best part of the resources was provided by the Technical Assistance and Co-operation Fund (96%), the remaining 4% was made available through assistance in kind. During the past ten years, project activities - and disbursements - have concentrated exclusively on three major areas: nuclear medicine (52%), general atomic energy development (25%) and agriculture (23%)

NEXT-100 Technical Design Report (TDR). Executive Summary

CERN Document Server

,

2012-01-01

In this Technical Design Report (TDR) we describe the NEXT-100 detector that will search for neutrinoless double beta decay in Xe-136. The document formalizes the ANGEL design presented in our Conceptual Design Report (CDR). The baseline detector is designed to hold a maximum of about 150 kg of xenon at 15 bar, or 100 kg at 10 bar. This option builds in the capability to increase the total isotope mass by 50% while keeping the operating pressure at a manageable level. The ANGEL design calls for an asymmetric TPC, with photomultipliers behind a transparent cathode and position-sensitive light pixels behind the anode. We have chosen the low background R11410-10 PMTs for energy and timing and Hamamatsu MPPCs (S10362-11-050P model) as tracking pixels. Each individual PMT will be isolated from the gas by an individual, pressure resistant enclosure and will be coupled to the sensitive volume through a sapphire window coated with terphenyl-butadiene (TPB) . MPPCs will be arranged in Dice Boards (DB) holding 64 senso...

Baseline tests for arc melter vitrification of INEL buried wastes. Volume 1: Facility description and summary data report

International Nuclear Information System (INIS)

Oden, L.L.; O'Connor, W.K.; Turner, P.C.; Soelberg, N.R.; Anderson, G.L.

1993-01-01

This report presents field results and raw data from the Buried Waste Integrated Demonstration (BWID) Arc Melter Vitrification Project Phase 1 baseline test series conducted by the Idaho National Engineering Laboratory (INEL) in cooperation with the U.S. Bureau of Mines (USBM). The baseline test series was conducted using the electric arc melter facility at the USBM Albany Research Center in Albany, Oregon. Five different surrogate waste feed mixtures were tested that simulated thermally-oxidized, buried, TRU-contaminated, mixed wastes and soils present at the INEL. The USBM Arc Furnace Integrated Waste Processing Test Facility includes a continuous feed system, the arc melting furnace, an offgas control system, and utilities. The melter is a sealed, 3-phase alternating current (ac) furnace approximately 2 m high and 1.3 m wide. The furnace has a capacity of 1 metric ton of steel and can process as much as 1,500 lb/h of soil-type waste materials. The surrogate feed materials included five mixtures designed to simulate incinerated TRU-contaminated buried waste materials mixed with INEL soil. Process samples, melter system operations data and offgas composition data were obtained during the baseline tests to evaluate the melter performance and meet test objectives. Samples and data gathered during this program included (a) automatically and manually logged melter systems operations data, (b) process samples of slag, metal and fume solids, and (c) offgas composition, temperature, velocity, flowrate, moisture content, particulate loading and metals content. This report consists of 2 volumes: Volume I summarizes the baseline test operations. It includes an executive summary, system and facility description, review of the surrogate waste mixtures, and a description of the baseline test activities, measurements, and sample collection. Volume II contains the raw test data and sample analyses from samples collected during the baseline tests

KBS Annual Report 1983. Including summaries of technical reports issued during 1983

International Nuclear Information System (INIS)

1984-06-01

The purpose of the KBS Annual Report is to inform interested organizations and individuals of the research and development work performed by the division KBS within the Swedish Nuclear Fuel Supply Co (SKBF) on the handling, treatment and final storage of nuclear wastes in Sweden. The Annual Report normally contains a presentation of the legal and organizational situation followed by an account of the progress within different areas of the R and D-work. This account also includes indications of the activities planned for the future. At the end of the report the summaries of 76 technical reports and other publications issued during the year are listed in special appendices. (K.A.E.)

The Agency's technical co-operation programme with El Salvador 1983-1993 country programme summaries

International Nuclear Information System (INIS)

1993-01-01

This report contains a review of the Agency's technical co-operation activities in El Salvador carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

Summary Report of the Technical Meeting on International Network of Nuclear Reaction Data Centres

International Nuclear Information System (INIS)

Otuka, Naohiko; Herman, Michal

2016-07-01

This report summarizes the IAEA Technical Meeting on the International Network of Nuclear Reaction Data Centres held at the China Hall of Science and Technology in Beijing, China from 7 to 10 June 2016. The meeting was attended by 23 participants representing 13 cooperative Centres from 8 Member States (China, Hungary, India, Japan, Korea, Russia, Ukraine and USA) and 2 International Organisations (NEA, IAEA) as well as two participants from Kazakhstan. A summary of the meeting is given in this report along with the conclusions and actions. (author)

The Agency's technical co-operation programme with Sri Lanka 1983-1993 country programme summaries

International Nuclear Information System (INIS)

1993-01-01

This report contains a review of the Agency's technical co-operation activities in Sri Lanka carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with Viet Nam 1983-1993 country programme summaries

International Nuclear Information System (INIS)

1993-01-01

This report contains a review of the Agency's technical co-operation activities in Viet Nam carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with the Philippines 1985-1995 country programme summaries

International Nuclear Information System (INIS)

1995-01-01

This report contains a review of the Agency's technical co-operation activities in Philippines carried out during 1985-1995. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with The Philippines 1984-1994 country programme summaries

International Nuclear Information System (INIS)

1994-01-01

This report contains a review of the Agency's technical co-operation activities in The Philippines carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with Dominican Republic 1983-1993 country programme summaries

International Nuclear Information System (INIS)

1993-01-01

This report contains a review of the Agency's technical co-operation activities in Dominican Republic carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The International Linear Collider Technical Design Report - Volume 1: Executive Summary

Energy Technology Data Exchange (ETDEWEB)

Behnke, Ties [Deutsches Elektronen-Synchrotron (DESY), Hamburg (Germany); Brau, James E. [Univ. of Oregon, Eugene, OR (United States); Foster, Brian [Deutsches Elektronen-Synchrotron (DESY), Hamburg (Germany); Fuster, Juan [Univ. of Valencia (Spain); Harrison, Mike [Brookhaven National Lab. (BNL), Upton, NY (United States); Paterson, James McEwan [SLAC National Accelerator Lab., Menlo Park, CA (United States); Peskin, Michael [SLAC National Accelerator Lab., Menlo Park, CA (United States); Stanitzki, Marcel [Deutsches Elektronen-Synchrotron (DESY), Hamburg (Germany); Walker, Nicholas [Deutsches Elektronen-Synchrotron (DESY), Hamburg (Germany); Yamamoto, Hitoshi [Tohoku Univ., Sendai (Japan)

2013-06-26

The International Linear Collider Technical Design Report (TDR) describes in four volumes the physics case and the design of a 500 GeV centre-of-mass energy linear electron-positron collider based on superconducting radio-frequency technology using Niobium cavities as the accelerating structures. The accelerator can be extended to 1 TeV and also run as a Higgs factory at around 250 GeV and on the Z0 pole. A comprehensive value estimate of the accelerator is give, together with associated uncertainties. It is shown that no significant technical issues remain to be solved. Once a site is selected and the necessary site-dependent engineering is carried out, construction can begin immediately. The TDR also gives baseline documentation for two high-performance detectors that can share the ILC luminosity by being moved into and out of the beam line in a "push-pull" configuration. These detectors, ILD and SiD, are described in detail. They form the basis for a world-class experimental programme that promises to increase significantly our understanding of the fundamental processes that govern the evolution of the Universe.

Summary of technical information and agreements from Nuclear Management and Resources Council industry reports addressing license renewal

International Nuclear Information System (INIS)

Regan, C.; Lee, S.

1996-10-01

In about 1990, the Nuclear Management and Resources Council (NUMARC) submitted for NRC review ten industry reports (IRs) addressing aging issues associated with specific structures and components of nuclear power plants ad one IR addressing the screening methodology for integrated plant assessment. The NRC staff had been reviewing the ten NUMARC IRs; their comments on each IR and NUMARC responses to the comments have been compiled as public documents. This report provides a brief summary of the technical information and NUMARC/NRC agreements from the ten IRs, except for the Cable License Renewal IR. The technical information and agreements documented herein represent the status of the NRC staffs review when the NRC staff and industry resources were redirected to address rule implementation issues. The NRC staff plans to incorporate appropriate technical information and agreements into the draft standard review plan for license renewal

The Agency's Technical Co-operation programme with Madagascar, 1982-1992. Country programme summaries

International Nuclear Information System (INIS)

1992-01-01

The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $3.5 million of Agency support received, Madagascar ranks 42nd among all recipients of technical assistance in the period 1958 through 1991. More than half of the assistance during the past ten years has been provided in the form of equipment (55%), followed by expert services (32%) and training (13%). With a share of 69%, the Technical Assistance and Co-operation Fund has provided more than two-thirds of the total resources available, while 29% were made available through UNDP and 2% through assistance in kind. Extrabudgetary contributions accounted for less than one per cent. With regard to project disbursements during the past ten years, by sector, by far the largest area has been nuclear raw materials (66%), followed by nuclear physics and chemistry (18%). Only small shares have gone to nuclear safety (7%), agriculture (5%) and nuclear engineering and technology (4%)

The Agency's Technical Co-operation programme with Cuba, 1982-1992. Country programme summaries

International Nuclear Information System (INIS)

1992-01-01

The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With almost $8.2 million of Agency support received, Cuba ranks 19th among all recipients of technical assistance in the period 1958 - 1991, whereby it ranked as high as 3rd in 1982 and 4th in 1984. Over three quarters of the assistance during the past ten years has been provided in the form of equipment (81%), followed by expert services (10%) and training (9%). Seventy-one per cent of the resources were made available through the Technical Assistance and Co-operation Fund, while 28% of the resources were provided by UNDP. The remaining 1% was made available through extrabudgetary and in-kind contributions. With regard to project disbursements by sector, the largest areas have been general atomic energy development (36%), agriculture (20%), nuclear physics and chemistry (10%) and nuclear safety (10%). Industry and hydrology, nuclear engineering and technology, and nuclear medicine have each received less than ten per cent of the assistance provided

The Agency's Technical Co-operation programme with Ghana, 1982-1992. Country programme summaries

International Nuclear Information System (INIS)

1992-01-01

The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $6.5 million of Agency support received, Ghana ranks 29th among all recipients of technical assistance in the period 1958 - 1991. More than half of the assistance during the past ten years has been provided in the form of equipment (53%), followed by training through fellowships and scientific visits (34%) and expert services (13%). Seventy-four per cent of the resources were provided by the Technical Assistance and Co-operation Fund, 13% through assistance in kind, 11% through extrabudgetary contributions, and 2% by UNDP. It should be noted that the share for extrabudgetary contributions includes an amount of $250,000 made available by the Ghanaian Government for the purchase of equipment by the Agency under a funds-in-trust arrangement. With regard to project disbursement by sector, the largest share has gone to agriculture (36%), followed by nuclear physics and chemistry (21%), nuclear medicine (16%), industry and hydrology (14%) and nuclear engineering and technology (9%)

The Agency's Technical Co-operation programme with Sudan, 1982-1992. Country programme summaries

International Nuclear Information System (INIS)

1992-01-01

The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $5.7 million of Agency support received, Sudan ranks 31st among all recipients of technical assistance in the period 1958 through 1991. Over the past ten years, almost equal shares of this assistance were provided in the form of equipment (46%) and training (42%), and only a small percentage was provided in the form of expert services (12%). The best part of the resources was made available through the Technical Assistance and Co-operation Fund (77%), while in-kind and extrabudgetary contributions account for 13% and 10% of the resources, respectively. With regard to project disbursement during the past ten years, by sector, the two largest areas have been general atomic energy development (37%) and agriculture (21%), followed by nuclear medicine (14%). Smaller shares (6% each) have gone to nuclear physics and chemistry, nuclear engineering and technology, hydrology, and nuclear safety

The Agency's Technical Co-operation programme with Cote d'Ivoire, 1982-1992. Country programme summaries

International Nuclear Information System (INIS)

1992-01-01

The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $1.7 million of Agency support received, Cote d'Ivoire ranks 60th among all recipients of technical assistance in the period 1958 through 1991. Over half of the assistance received during the past ten years has been in the form of equipment (59%), complemented by expert services (26%) and training (15%). The best part of the resources was provided by the Technical Assistance and Co-operation Fund (91%), the remainder was made available through extrabudgetary contributions (7%) and through assistance in kind (2%). During the past ten years, project activities - and disbursements - have concentrated exclusively on three major areas: agriculture (59%), general atomic energy development (30%) and nuclear safety (11%)

The Agency's Technical Co-operation programme with Costa Rica, 1982-1992. Country programme summaries

International Nuclear Information System (INIS)

1992-01-01

The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $2.8 million of Agency support received, Costa Rica ranks 49th among all recipients of technical assistance in the period 1958-1991. Over half of the assistance during the past ten years has been provided in the form of equipment (52%), followed by expert services (37%) and training (11%). Sixty-two per cent of the resources were made available through the Technical Assistance and Co-operation Fund, while 37% of the resources were provided by UNDP. The rest was made available through extrabudgetary contributions (5%) and through in-kind assistance (1%). With regard to project disbursement by sector, the largest areas have been nuclear raw materials (36%), nuclear physics and chemistry (24%) and agriculture (20%). Smaller shares have gone to hydrology (11%) and nuclear medicine (8%)

Technical data summary: Uranium(IV) production using a large scale electrochemical cell

International Nuclear Information System (INIS)

Hsu, T.C.

1984-05-01

This Technical Data Summary outlines an electrochemical process to produce U(IV), in the form of uranous nitrate, from U(VI), as uranyl nitrate. U(IV) with hydrazine could then be used as an alternative plutonium reductant to substantially reduce the waste volume from the Purex solvent extraction process. This TDS is divided into three parts. The first part (Chapters I to IV) generally describes the electrochemical production of U(IV). The second part (Chapters V to VII) describes a pilot scale U(IV) production facility that was constructed and operated at an engineering semiworks area of SRP, referred to as TNX. The lst part (Chapter VIII) describes a preliminary design for a full-scale facility that would meet the projected need for U(IV) as a reductant in SRP's separations processes. The preliminary design was described in a Basic Data Summary for the U(IV) production facility, and a Venture Guidance Appraisal (VGA) was prepared from the Basic Data Summary. The VGA for the U(IV) process showed that because of the large capital investment required, this approach to waste reduction was not economically competitive with another alternative that required only modifying the ongoing Purex process at no additional capital cost. However, implementing he U(IV) process as part of an overall canyon renovation, presently scheduled for the 1990's, may be economically attractive. The purpose of this TDS is therefore to bring together the information and experience obtained thus far in the U(IV) program so that a useful body of information will be available to support any future development of this process

Spent nuclear fuel project technical databook

Energy Technology Data Exchange (ETDEWEB)

Reilly, M.A.

1998-07-22

The Spent Nuclear Fuel (SNF) project technical databook provides project-approved summary tables of selected parameters and derived physical quantities, with nominal design and safety basis values. It contains the parameters necessary for a complete documentation basis of the SNF Project technical and safety baseline. The databook is presented in two volumes. Volume 1 presents K Basins SNF related information. Volume 2 (not yet available) will present selected sludge and water information, as it relates to the sludge and water removal projects. The values, within this databook, shall be used as the foundation for analyses, modeling, assumptions, or other input to SNF project safety analyses or design. All analysis and modeling using a parameter available in this databook are required to use and cite the appropriate associated value, and document any changes to those values (i.e., analysis assumptions, equipment conditions, etc). Characterization and analysis efforts are ongoing to validate, or update these values.

Spent nuclear fuel project technical databook

International Nuclear Information System (INIS)

Reilly, M.A.

1998-01-01

The Spent Nuclear Fuel (SNF) project technical databook provides project-approved summary tables of selected parameters and derived physical quantities, with nominal design and safety basis values. It contains the parameters necessary for a complete documentation basis of the SNF Project technical and safety baseline. The databook is presented in two volumes. Volume 1 presents K Basins SNF related information. Volume 2 (not yet available) will present selected sludge and water information, as it relates to the sludge and water removal projects. The values, within this databook, shall be used as the foundation for analyses, modeling, assumptions, or other input to SNF project safety analyses or design. All analysis and modeling using a parameter available in this databook are required to use and cite the appropriate associated value, and document any changes to those values (i.e., analysis assumptions, equipment conditions, etc). Characterization and analysis efforts are ongoing to validate, or update these values

The Agency's technical co-operation programme with Syrian Arab Republic 1984-1994 country programme summaries

International Nuclear Information System (INIS)

1994-01-01

This report contains a review of the Agency's technical co-operation activities in Syrian Arab Republic carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with Cote d'Ivoire 1985-1995 country programme summaries

International Nuclear Information System (INIS)

1995-01-01

This report contains a review of the Agency's technical co-operation activities in Cote d'Ivoire carried out during 1985-1995. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

Nagra technical report 14-02, geological basics - Dossier I - Introduction and summary

International Nuclear Information System (INIS)

Gautschi, A.; Zuidema, P.

2014-01-01

This dossier is the first of a series of eight reports concerning the safety and technical aspects of locations for the disposal of radioactive wastes in Switzerland. It presents an introduction to and a summary of the further seven dossiers on basic geological conditions. Dossier II considers the sediments that can be used along with tectonic considerations, Dossier III takes a look at long-term geological developments and Dossier IV considers the geo-mechanical documentation available. Dossier V looks at hydro-geological considerations. Dossier VI reports on the barrier properties of the proposed host rock sediments and neighbouring rock layers. Dossiers VII takes a look at usage conflicts and Dossier VIII considers the possibilities for the characterisation of the substrates and for the ways in which they can be explored

High integrity software for nuclear power plants: Candidate guidelines, technical basis and research needs. Executive summary: Volume 1

International Nuclear Information System (INIS)

Seth, S.; Bail, W.; Cleaves, D.; Cohen, H.; Hybertson, D.; Schaefer, C.; Stark, G.; Ta, A.; Ulery, B.

1995-06-01

The work documented in this report was performed in support of the US Nuclear Regulatory Commission to examine the technical basis for candidate guidelines that could be considered in reviewing and evaluating high integrity computer software used in the safety systems of nuclear power plants. The framework for the work consisted of the following software development and assurance activities: requirements specification; design; coding; verification and validation, including static analysis and dynamic testing; safety analysis; operation and maintenance; configuration management; quality assurance; and planning and management. Each activity (framework element) was subdivided into technical areas (framework subelements). The report describes the development of approximately 200 candidate guidelines that span the entire range of software life-cycle activities; the assessment of the technical basis for those candidate guidelines; and the identification, categorization and prioritization of research needs for improving the technical basis. The report has two volumes: Volume 1, Executive Summary, includes an overview of the framework and of each framework element, the complete set of candidate guidelines, the results of the assessment of the technical basis for each candidate guideline, and a discussion of research needs that support the regulatory function; Volume 2 is the main report

Technical data summary supporting the spent nuclear fuel environmental impact statement, November 1993

International Nuclear Information System (INIS)

Geddes, R.L.; Claxton, R.E.; Lengel, J.D.

1993-11-01

This report has been compiled by the WSRC Nuclear Materials Processing Division's Planning Section at the request of the Office of Spent Fuel Management and Special Projects (EM-37) to support issuance of the Spent Nuclear Fuel Environmental Impact Statement. Savannah River site data evaluates five programmatic options including open-quotes No Actionclose quotes ranging up to transfer of all DOE responsibility spent fuel to the SRS. For each option, a range of management/disposition scenarios has been examined. Each case summary provides information relative to the technical proposal, technical issues, environmental impacts, and projected costs for a 50 period (to 2044) when it is assumed that the material will be dispositioned from the SRS. It must be recognized that this report was prepared under severe time constraints and contains many simplifications and assumptions. It is highly recommended that significant additional study be performed before basing key decisions upon the data contained in this report. It represents a best effort by a significant group of technical personnel familiar with nuclear materials processing, handlings and storage but it is likely that careful scrutiny will reveal numerous discrepancies and omissions. The bulk of the effort went into defining the engineering approaches necessary to execute the various mission scenarios. Collection and/or calculation of much of the various waste, emission, and utility consumption data, so important to an Environmental Impact Statement, has not been completed at this time

The Agency's Technical Co-operation programme with Brazil, 1982-1992. Country programme summaries

International Nuclear Information System (INIS)

1992-01-01

The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $17 million of Agency support received, Brazil ranks 2nd among all recipients of technical assistance during the period 1958 through 1991. Over half of the assistance received during the past ten years has been provided in the form of equipment (51%), complemented by expert services (34%) and training (15%). Almost two-thirds of the funds were made available through the Technical Assistance and Co-operation Fund (63%), the rest was provided through extrabudgetary contributions (30%), assistance in kind (4%) and UNDP (3%). With regard to total disbursements - by sector - under those projects that were operational during the period 1982 through November 1992, the three major areas have been: general atomic energy development (47%), nuclear safety (22%) and agriculture (13%). During the same period, the country has provided experts and training course lectures for a total of 405 assignments, and has hosted 178 fellowships and scientific visits as well as 46 regional and interregional training events with a total of 603 participants

The Agency's Technical Co-operation programme with Peru, 1982-1992. Country programme summaries

International Nuclear Information System (INIS)

1992-01-01

The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $12.6 million of Agency support received, Peru ranks 4th among all recipients of technical assistance in the period 1958 - 1991, whereby it ranked as high as 2nd in each of the four years 1982 through 1985. More than half of the assistance during the past ten years has been provided in the form of equipment (59%), followed by expert services (29%) and training (12%). Forty-five per cent of the resources were provided by the Technical Assistance and Co-operation Fund, while 29% of the resources were made available through extrabudgetary contributions, and 21% by UNDP. The remaining 5% were provided in kind. With regard to project disbursement by sector, the largest areas have been agriculture (27%), general atomic energy development (17%), nuclear raw materials (14%), nuclear medicine (12%) and industry and hydrology (11%). Nuclear safety, nuclear engineering and technology, and nuclear physics and chemistry have each received less than ten per cent of the assistance provided

The Agency's Technical Co-operation programme with Egypt, 1982-1992. Country programme summaries

International Nuclear Information System (INIS)

1992-01-01

The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $22.2 million of Agency support received, Egypt ranks first among all recipients of technical assistance, not only for the period 1958 - 1991, but also held this rank in each of the five years 1982 through 1986 and in 1988. More than half of this assistance has been provided in the form of equipment (57%), followed by expert services (19%), training (17%) and sub-contracts (7%). With 42% and 43%, respectively, the Technical Assistance and Co-operation Fund and extrabudgetary contributions hold almost equal shares in the total resources available, while in-kind assistance accounts for 9% and UNDP for 6% of the resources. With regard to project disbursement during the past ten years, by sector, the two largest areas have been nuclear safety (34%) and agriculture (33%), followed by nuclear engineering and technology (11%). Smaller shares - from 4% to 7% each-- have gone to industry and hydrology, nuclear medicine, nuclear physics and chemistry, and general atomic energy development

Summary of Tiger Team Assessment and Technical Safety Appraisal recurring concerns in the Maintenance Area

International Nuclear Information System (INIS)

1993-01-01

Tiger Team Assessments and Technical Safety Appraisals (TSA) were reviewed and evaluated for concerns in the Maintenance Area (MA). Two hundred and thirty one (231) maintenance concerns were identified by the Tiger Team Assessments and TSA reports. These recurring concerns appear below. A summary of the Noteworthy Practices that were identified and a compilation of the maintenance concerns for each performance objective that were not considered as recurring are also included. Where the Tiger Team Assessment and TSA identified the operating contractor or facility by name, the concern has been modified to remove the name while retaining the intent of the comment

Design mentoring tool : [technical summary].

Science.gov (United States)

2011-01-01

In 2004 a design engineer on-line mentoring tool was developed and implemented The purpose of the tool was to assist senior engineers mentoring new engineers to the INDOT design process and improve their technical competency. This approach saves seni...

Baseline Projection Data Book: GRI baseline projection of U.S. Energy Supply and Demand to 2010. 1992 Edition. Volume 1 and Volume 2

International Nuclear Information System (INIS)

Holtberg, P.D.; Woods, T.J.; Lihn, M.L.; Koklauner, A.K.

1992-01-01

The 1992 Baseline Projection Data Book provides backup data in tabular form for the 1992 GRI Baseline Projection of U.S. Energy Supply and Demand to 2010. Summary tables and data for the residential, commercial, industrial, electric utility, and transportation sectors are presented in the volume

The Agency's technical co-operation programme with the United Arab Emirates 1984-1994 country programme summaries

International Nuclear Information System (INIS)

1994-01-01

This report contains a review of the Agency's technical co-operation activities in the United Arab Emirates carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with the Republic of Korea 1985-1995 country programme summaries

International Nuclear Information System (INIS)

1995-01-01

This report contains a review of the Agency's technical co-operation activities in the Republic of Korea carried out during 1985-1995. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

Baseline atmospheric program Australia 1993

International Nuclear Information System (INIS)

Francey, R.J.; Dick, A.L.; Derek, N.

1996-01-01

This publication reports activities, program summaries and data from the Cape Grim Baseline Air Pollution Station in Tasmania, during the calendar year 1993. These activities represent Australia's main contribution to the Background Air Pollution Monitoring Network (BAPMoN), part of the World Meteorological Organization's Global Atmosphere Watch (GAW). The report includes 5 research reports covering trace gas sampling, ozone and radon interdependence, analysis of atmospheric dimethylsulfide and carbon-disulfide, sampling of trace gas composition of the troposphere, and sulfur aerosol/CCN relationship in marine air. Summaries of program reports for the calendar year 1993 are also included. Tabs., figs., refs

Integrated planning: A baseline development perspective

International Nuclear Information System (INIS)

Clauss, L.; Chang, D.

1994-01-01

The FEMP Baseline establishes the basis for integrating environmental activity technical requirements with their cost and schedule elements. The result is a path forward to successfully achieving the FERMCO mission. Specific to cost management, the FEMP Baseline has been incorporate into the FERMCO Project Control System (PCS) to provide a time-phased budget plan against which contractor performance is measured with an earned value management system. The result is the Performance Measurement Baseline (PMB), an important tool for keeping cost under control

Baseline development, economic risk, and schedule risk: An integrated approach

International Nuclear Information System (INIS)

Tonkinson, J.A.

1994-01-01

The economic and schedule risks of Environmental Restoration (ER) projects are commonly analyzed toward the end of the baseline development process. Risk analysis is usually performed as the final element of the scheduling or estimating processes for the purpose of establishing cost and schedule contingency. However, there is an opportunity for earlier assessment of risks, during development of the technical scope and Work Breakdown Structure (WBS). Integrating the processes of risk management and baselining provides for early incorporation of feedback regarding schedule and cost risk into the proposed scope of work. Much of the information necessary to perform risk analysis becomes available during development of the technical baseline, as the scope of work and WBS are being defined. The analysis of risk can actually be initiated early on during development of the technical baseline and continue throughout development of the complete project baseline. Indeed, best business practices suggest that information crucial to the success of a project be analyzed and incorporated into project planning as soon as it is available and usable

Draft low level waste technical summary

International Nuclear Information System (INIS)

Powell, W.J.; Benar, C.J.; Certa, P.J.; Eiholzer, C.R.; Kruger, A.A.; Norman, E.C.; Mitchell, D.E.; Penwell, D.E.; Reidel, S.P.; Shade, J.W.

1995-09-01

The purpose of this document is to present an outline of the Hanford Site Low-Level Waste (LLW) disposal program, what it has accomplished, what is being done, and where the program is headed. This document may be used to provide background information to personnel new to the LLW management/disposal field and to those individuals needing more information or background on an area in LLW for which they are not familiar. This document should be appropriate for outside groups that may want to learn about the program without immediately becoming immersed in the details. This document is not a program or systems engineering baseline report, and personnel should refer to more current baseline documentation for critical information

Baseline Report on HB2320

Science.gov (United States)

State Council of Higher Education for Virginia, 2015

2015-01-01

Staff provides this baseline report as a summary of its preliminary considerations and initial research in fulfillment of the requirements of HB2320 from the 2015 session of the General Assembly. Codified as § 23-7.4:7, this legislation compels the Education Secretary and the State Council of Higher Education for Virginia (SCHEV) Director, in…

Technical assistance to Ohio closure sites; Recommendations toaddress contaminated soils, concrete, and corrective action managementunit/groundwater contamination at Ashtabula, Ohio

Energy Technology Data Exchange (ETDEWEB)

Charoglu, Emily; Eddy-Dilek, Carol; Gombert, Dirk; Hazen, Terry; Johnson, Bob; Looney, Brian; Krstich, Michael A.; Rautman, Chris; Tripp,Julia; Whitmill, Larry

2002-08-26

The Ashtabula Environmental Management Project (AEMP) at Department of Energy-Ohio (DOE-OH) requested technical assistance from the EM-50 Lead Lab to aid in defining new cost and time effective approaches in the following problem areas: soils, concrete, and groundwater/Corrective Action Management Unit (CAMU) at RMIES in Ashtabula, Ohio. Attachment 1 provides the site request for assistance. The technical assistance team assembled for this request is provided in Attachment 2. These individuals reviewed key site information prior to convening with DOE and contractor personnel (RMIES and Earthline) for a three-and-a-half-day meeting to better understand baseline technologies, limitations, and site-specific issues. After listening to presentations about the nature and extent of known contamination, the team broke out into several groups to brainstorm ideas and develop viable solutions. This executive summary details unresolved issues requiring management attention as well as recommendations to address soils, concrete, and groundwater/CAMU. It also provides a summary of additional technical assistance that could be provided to the site. More details are presented in the body of this report.

LLNL/YMP Waste Container Fabrication and Closure Project; GFY technical activity summary

Energy Technology Data Exchange (ETDEWEB)

NONE

1990-10-01

The Department of Energy`s Office of Civilian Radioactive Waste Management (OCRWM) Program is studying Yucca Mountain, Nevada as a suitable site for the first US high-level nuclear waste repository. Lawrence Livermore National Laboratory (LLNL) has the responsibility for designing and developing the waste package for the permanent storage of high-level nuclear waste. This report is a summary of the technical activities for the LLNL/YMP Nuclear Waste Disposal Container Fabrication and Closure Development Project. Candidate welding closure processes were identified in the Phase 1 report. This report discusses Phase 2. Phase 2 of this effort involved laboratory studies to determine the optimum fabrication and closure processes. Because of budget limitations, LLNL narrowed the materials for evaluation in Phase 2 from the original six to four: Alloy 825, CDA 715, CDA 102 (or CDA 122) and CDA 952. Phase 2 studies focused on evaluation of candidate material in conjunction with fabrication and closure processes.

The Agency's technical co-operation programme with the People's Republic of China 1985-1995 country programme summaries

International Nuclear Information System (INIS)

1995-01-01

This report contains a review of the Agency's technical co-operation activities in the People's Republic of China carried out during 1985-1995. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with the Islamic Republic of Iran 1985-1995 country programme summaries

International Nuclear Information System (INIS)

1995-01-01

This report contains a review of the Agency's technical co-operation activities in the Islamic Republic of Iran carried out during 1985-1995. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's technical co-operation programme with the Islamic Republic of Iran 1983-1993 country programme summaries

International Nuclear Information System (INIS)

1993-01-01

This report contains a review of the Agency's technical co-operation activities in the Islamic Republic of Iran carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

The Agency's Technical Co-operation programme with the United Republic of Tanzania, 1982-1992. Country programme summaries

International Nuclear Information System (INIS)

1992-01-01

The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $ 3.4 million of Agency support received, the United Republic of Tanzania ranks 44th among all recipients of technical assistance in the period 1958 - 1991. Almost half of the assistance during the past ten years has been provided in the form of equipment (49%), followed by training through fellowships and scientific visits (29%) and expert services (22%). Ninety-two per cent of the resources were provided by the Technical Assistance and Co-operation Fund, the rest was made available through assistance in kind (5%) and through extrabudgetary contributions (3%). With regard to project disbursement by sector, by far the largest share has gone to agriculture (48%), followed by nuclear physics (20%), nuclear safety (17%) and nuclear medicine (11%)

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

Energy Technology Data Exchange (ETDEWEB)

1994-06-20

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

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

International Nuclear Information System (INIS)

1994-01-01

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

Safety Evaluation of the ESP Sludge Washing Baselines Runs. Revision 1

International Nuclear Information System (INIS)

Gupta, M.K.

1994-08-01

The purpose is to provide the technical basis for the evaluation of Unreviewed Safety Question for the Extended Sludge Processing (ESP) Sludge Washing Baseline Runs. The Baseline runs are necessary: to ascertain the mechanical fitness of the equipment and modifications not operated since 1988 and to resolve technical questions associated with process control; i.e., sludge suspension, sludge settling, heat transfer, and temperature control. These issues need to be resolved prior to resumption of normal ESP operations. The equipment used for the Baseline runs are Tanks 42H and 51H and their associated equipment

Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 5. Baseline rock properties-granite

International Nuclear Information System (INIS)

1978-04-01

This volume, Y/OWI/TM-36/5, Baseline Rock Properties--Granite, is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-36'' which supplements a ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-44.'' The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This report, on the rock properties of typical granites, includes an evaluation of the various test results reported in the literature. Firstly, a literature survey was made in order to obtain a feel for the range of rock properties encountered. Then, granites representative of different geologic ages and from different parts of the United States were selected and studied in further detail. Some of the special characteristics of granite, such as anisotropy, creep and weathering were also investigated. Lastly, intact properties for a typical granite were selected and rock mass properties were derived using appropriate correction factors

Technical data summary supporting the spent nuclear fuel environment impact statement, March 1994

International Nuclear Information System (INIS)

Geddes, R.L.; Claxton, R.E.; Lengel, J.D.

1994-03-01

This report has been compiled by the WSRC Nuclear Materials Processing Division's Planning Section at the request of the Office of Spent Fuel Management and Special Projects (EM-37) to support issuance of the Spent Nuclear Fuel Environmental Impact Statement. Savannah River Site input data evaluates five programmatic options (including open-quotes No Actionclose quotes) ranging up to transfer of all DOE responsibility spent fuel to the SRS. For each option, a range of management/disposition scenarios has been examined. Each case summary provides information relative to the technical proposal, technical issues, environmental impacts, and projected costs for a forty year period (FY-35) when it is assumed that the material will be dispositioned from the SRS. The original issue of the report which was prepared under severe time constraints contained many simplifications and assumptions. Although the revisions have corrected some of the shortcomings of the original report, it is still highly recommended that significant additional study be performed before basing key decisions upon the data contained in this report. The data represents the best effort by a significant group of technical personnel familiar with nuclear materials processing, handling, and storage; but it is likely that careful scrutiny will reveal numerous discrepancies, inconsistencies and omissions. Nor does this report attempt to analyze every potential disposal pathway, but probably establishes the bounds for the most of the viable pathways. The bulk of the effort went into defining the engineering approaches necessary to execute the various mission scenarios which were changed since the last revision. The decision to limit reprocessing to only SRS aluminum clad required a major alteration of the TDS. Collection and/or calculation of much of the various waste, emission, and utility consumption data, so important to an EIS, has been updated since the last revision, but not thoroughly completed

Summary of Tiger Team Assessment and Technical Safety Appraisal recurring concerns in the Operations Area

International Nuclear Information System (INIS)

1993-01-01

Fourteen Tiger Team Assessment and eight Technical Safety Appraisal (TSA) final reports have been received and reviewed by the DOE Training Coordination Program during Fiscal Year 1992. These assessments and appraisals included both reactor and non-reactor nuclear facilities in their reports. The Tiger Team Assessments and TSA reports both used TSA performance objectives, and list ''concerns'' as a result of their findings. However, the TSA reports categorized concerns into the following functional areas: (1) Organization and Administration, (2) Radiation Protection, (3) Nuclear Criticality Safety, (4) Occupational Safety, (5) Engineering/Technical Support, (6) Emergency Preparedness, (7) Safety Assessments, (8) Quality Verification, (9) Fire Protection, (10) Environmental Protection, and (11) Energetic Materials Safety. Although these functional areas match most of the TSA performance objectives, not all of the TSA performance objectives are addressed. For example, the TSA reports did not include Training, Maintenance, and Operations as functional areas. Rather, they included concerns that related to these topics throughout the 11 functional areas identified above. For consistency, the Operations concerns that were identified in each of the TSA report functional areas have been included in this summary with the corresponding TSA performance objective

Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 7. Baseline rock properties-basalt

International Nuclear Information System (INIS)

1978-04-01

This volume, Y/OWI/TM-36/7 Baseline Rock Properties--Basalt, is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-36'' which supplements a ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-44.'' The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This report contains an evaluation of the results of a literature survey to define the rock mass properties of a generic basalt, which could be considered as a geological medium for storing radioactive waste. The general formation and structure of basaltic rocks is described. This is followed by specific descriptions and rock property data for the Dresser Basalt, the Amchitka Island Basalt, the Nevada Test Site Basalt and the Columbia River Group Basalt. Engineering judgment has been used to derive the rock mass properties of a typical basalt from the relevant intact rock property data and the geological information pertaining to structural defects, such as joints and faults

SKB annual report 1993. Including summaries of technical reports issued during 1993

International Nuclear Information System (INIS)

1994-05-01

This is the annual report on the activities of the Swedish Nuclear and Waste Management Co., SKB. It contains in part I an overview of SKB activities in different fields. Part II gives a description of the research and development work on nuclear waste disposal performed during 1993. Lectures and publications during 1993 as well as reports issued in the SKB technical series are listed in part III. Part IV contains the summaries of all technical reports issued during 1993. SKB is the owner of CLAB, the Central Facility for Interim Storage of Spent Nuclear Fuel, located at Oskarshamn. CLAB was taken into operation in July 1985 and to the end of 1993 in total 1 885 tonnes of spent fuel (measured as uranium) have been received. Transportation from the nuclear sites to CLAB is made by a special ship, M/S Sigyn. At Forsmark the final repository for Radioactive Waste - SFR - was taken into operation in April 1988. The repository is situated in crystalline rock under the Baltic Sea. At the end of 1993 a total of 13 000 m 3 of waste have been deposited in SFR. SKB is in charge of a comprehensive research and development programme on geological disposal of nuclear waste. Some of the main areas for SKB research are: Groundwater movements; Bedrock stability; Groundwater chemistry and nuclide migration; Methods and instruments for in situ characterization of crystalline bedrock; Characterization and leaching of spent nuclear fuel; Properties of bentonite for buffer, backfilling and sealing; Radionuclide transport in biosphere and dose evaluations; Development of performance and safety assessment methodology and assessment models; Construction of an underground research laboratory

75 FR 13680 - Commutation of Sentence: Technical Change

Science.gov (United States)

2010-03-23

... Sentence: Technical Change AGENCY: Bureau of Prisons, Justice. ACTION: Interim rule. SUMMARY: This document makes a minor technical change to the Bureau of Prisons (Bureau) regulations on sentence commutation to.... Commutation of Sentence: Technical Change This document makes a minor technical change to the Bureau...

Summary of Research 1997

OpenAIRE

Maier, William B.; Cleary, David D.

1997-01-01

This report contains summaries of research projects in the Department of Physics. A list of recent publications in also included which consists of conference presentations and publications, books, contributions to books, published jounal papers, technical reports, and thesis abstracts.

Office of Geologic Repositories program baseline procedures notebook (OGR/B-1)

International Nuclear Information System (INIS)

1986-06-01

Baseline management is typically applied to aid in the internal control of a program by providing consistent programmatic direction, control, and surveillance to an evolving system development. This fundamental concept of internal program control involves the establishment of a baseline to serve as a point of departure for consistent technical program coordination and to control subsequent changes from that baseline. The existence of a program-authorized baseline ensures that all participants are working to the same ground rules. Baseline management also ensures that, once the baseline is defined, changes are assessed and approved by a process which ensures adequate consideration of overall program impact. Baseline management also includes the consideration of examptions from the baseline. The process of baseline management continues through all the phases of an evolving system development program. As the Program proceeds, there will be a progressive increase in the data contained in the baseline documentation. Baseline management has been selected as a management technique to aid in the internal control of the Office of Geologic Repositories (OGR) program. Specifically, an OGR Program Baseline, including technical and programmatic requirements, is used for program control of the four Mined Geologic Disposal System field projects, i.e., Basalt Waste Isolation Project, Nevada Nuclear Waste Storage Investigation, Salt Repository Project and Crystalline Repository Project. This OGR Program Baseline Procedures Notebook provides a description of the baseline mwanagement concept, establishes the OGR Program baseline itself, and provides procedures to be followed for controlling changes to that baseline. The notebook has a controlled distribution and will be updated as required

Research and Technology Objectives and Plans Summary (RTOPS)

Science.gov (United States)

1993-01-01

This publication represents the NASA research and technology program for FY-93. It is a compilation of the Summary portions of each of the RTOP's (Research and Technology Objectives and Plans) used for management review and control of research currently in progress throughout NASA. The RTOP Summary is designed to facilitate communication and coordination among concerned technical personnel in government, in industry, and in universities. The first section containing citations and abstracts of the RTOP's is followed by four indexes: Subject, Technical Monitor, Responsible NASA Organization, and RTOP Number.

Unresolved safety issues summary: aqua book

International Nuclear Information System (INIS)

1982-06-01

The unresolved safety issues summary is designed to provide the management of the Nuclear Regulatory Commission with a quarterly overview of the progress and plans for completion of generic tasks addressing unresolved safety issues reported to Congress pursuant to Section 210 of the Energy Reorganization Act of 1974 as amended. This summary utilizes data collected from the Office of Nuclear Reactor Regulation, Office of Nuclear Regulatory Research, and the National Laboratories and is prepared by the Office of Resource Management. The schedules in this book include a milestone at the end of each action plan which represents the initiation of the implementation process both with respect to incorporation of the technical resolution in the NRC official guidance or requirements and also the application of changes to individual operating plants. The progress and status for implementation of unresolved safety issues for which a technical resolution has been completed are reported specifically in a separate table provided in this summary

Baseline geochemistry of soil and bedrock Tshirege Member of the Bandelier Tuff at MDA-P

International Nuclear Information System (INIS)

Warren, R.G.; McDonald, E.V.; Ryti, R.T.

1997-08-01

This report provides baseline geochemistry for soils (including fill), and for bedrock within three specific areas that are planned for use in the remediation of Material Disposal Area P (MDA-P) at Technical Area 16 (TA-16). The baseline chemistry includes leachable element concentrations for both soils and bedrock and total element concentrations for all soil samples and for two selected bedrock samples. MDA-P operated from the early 1950s to 1984 as a landfill for rubble and debris generated by the burning of high explosives (HE) at the TA-16 Burning Ground, HE-contaminated equipment and material, barium nitrate sand, building materials, and trash. The aim of this report is to establish causes for recognizable chemical differences between the background and baseline data sets. In many cases, the authors conclude that recognizable differences represent natural enrichments. In other cases, differences are best attributed to analytical problems. But most importantly, the comparison of background and baseline geochemistry demonstrates significant contamination for several elements not only at the two remedial sites near the TA-16 Burning Ground, but also within the entire region of the background study. This contamination is highly localized very near to the surface in soil and fill, and probably also in bedrock; consequently, upper tolerance limits (UTLs) calculated as upper 95% confidence limits of the 95th percentile are of little value and thus are not provided. This report instead provides basic statistical summaries and graphical comparisons for background and baseline samples to guide strategies for remediation of the three sites to be used in the restoration of MDA-P

Energy from the desert. Very large scale photovoltaic systems: socio-economic, financial, technical and environmental aspects. Executive summary

Energy Technology Data Exchange (ETDEWEB)

Kurokawa, K.; Ito, M.; Komoto, K.; Vleuten, P. van der; Faiman, D. (eds.)

2009-05-15

This executive summary report for the International Energy Agency (IEA) summarises the objectives and concepts of very large scale photovoltaic power generation (VLS-PV) systems and takes a look at the socio-economic, financial and technical aspects involved as well as the environmental impact of such systems. Potential benefits for desert communities, agricultural development and desalination of water are topics that are looked at. The potential of VLS-PV, its energy payback time and CO{sub 2} emission rates are discussed. Case studies for the Sahara and the Gobi Dessert areas are discussed. A VLS-PV roadmap is proposed and scenarios are discussed. Finally, conclusions are drawn and recommendations are made.

Organic Contamination Baseline Study: In NASA JSC Astromaterials Curation Laboratories. Summary Report

Science.gov (United States)

Calaway, Michael J.

2013-01-01

In preparation for OSIRIS-REx and other future sample return missions concerned with analyzing organics, we conducted an Organic Contamination Baseline Study for JSC Curation Labsoratories in FY12. For FY12 testing, organic baseline study focused only on molecular organic contamination in JSC curation gloveboxes: presumably future collections (i.e. Lunar, Mars, asteroid missions) would use isolation containment systems over only cleanrooms for primary sample storage. This decision was made due to limit historical data on curation gloveboxes, limited IR&D funds and Genesis routinely monitors organics in their ISO class 4 cleanrooms.

Healthcare. Executive Summary

Science.gov (United States)

Carnevale, Anthony P.; Smith, Nicole; Gulish, Artem; Beach, Bennett H.

2012-01-01

This executive summary highlights several findings about healthcare. These are: (1) Healthcare is 18 percent of the U.S. economy, twice as high as in other countries; (2) There are two labor markets in healthcare: high-skill, high-wage professional and technical jobs and low-skill, low-wage support jobs; (3) Demand for postsecondary education in…

48 CFR 34.202 - Integrated Baseline Reviews.

Science.gov (United States)

2010-10-01

... or contractor, and the Government, of the— (1) Ability of the project's technical plan to achieve the... successfully achieve the project schedule objectives; (3) Ability of the Performance Measurement Baseline (PMB... SPECIAL CATEGORIES OF CONTRACTING MAJOR SYSTEM ACQUISITION Earned Value Management System 34.202...

Office of Civilian Radioactive Waste Management Program Cost and Schedule Baseline

International Nuclear Information System (INIS)

1992-09-01

The purpose of this document is to establish quantitative expressions of proposed costs and schedule to serve as a basis for measurement of program performance. It identifies the components of the Program Cost and Schedule Baseline (PCSB) that will be subject to change control by the Executive (Level 0) and Program (Level 1) Change Control Boards (CCBS) and establishes their baseline values. This document also details PCSB reporting, monitoring, and corrective action requirements. The Program technical baseline contained in the Waste Management System Description (WMSD), the Waste Management System Requirements (WMSR), and the Physical System Requirements documents provide the technical basis for the PCSB. Changes to the PCSB will be approved by the Pregrain Change Control Board (PCCB)In addition to the PCCB, the Energy System Acquisition Advisory Board Baseline CCB (ESAAB BCCB) will perform control functions relating to Total Project Cost (TPC) and major schedule milestones for the Yucca Mountain Site Characterization Project and the Monitored Retrievable Storage (MRS) Project

Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 6. Baseline rock properties-shale

International Nuclear Information System (INIS)

1978-04-01

This volume, Y/OWI/TM36/6 Baseline Rock Properties--Shale, is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-36'' which supplements a ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-44.'' The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. The report is a result of a literature survey of the rock properties of shales occurring in the United States. Firstly, data were collected from a wide variety of sources in order to obtain a feel for the range of properties encountered. Secondly, some typical shales were selected for detailed review and these are written up as separate chapters in this report. Owing to the wide variability in lithology and properties of shales occurring in the United States, it became necessary to focus the study on consolidated illite shales. Using the specific information already generated, a consistent set of intact properties for a typical, consolidated illite shale was obtained. Correction factors, largely based on geological considerations, were then applied to the intact data in order to yield typical rock mass properties for this type of shale. Lastly, excavation problems in shale formations were reviewed and three tunnel jobs were written up as case histories

Conference summaries

Energy Technology Data Exchange (ETDEWEB)

Reynolds, Tim [Inta Communication Limited for European Service Network/ DG Research, Trillium House, 32 New Street, St. Neots, Cambridge PE19 1AJ (United Kingdom)

2004-07-01

The summaries were derived from presentations, interviews and discussions at the conference. The summaries are given at two levels, overall for the conference and for specific sessions as follows: 1) Overall Conference: 'A Sound Scientific Basis for Serious Decisions; 2) Sessions on EC Policy and Socio-Political Issues: 'Promoting Safety and Protecting Society'; 3) Session on P and T: 'Partitioning and Transmutation: A Technical Fix or Technical Training?'; 4) Sessions on Geological Disposal and Research Networking: 'No Technical Barriers to Geological Disposal'. First an overall summary of Euradwaste '04 is presented. Significant progress was made on the technical and scientific basis for geological disposal of radioactive waste during the European Commission's Fifth EURATOM Framework Programme for Research (FP5). Deep geological disposal is technically feasible now and can demonstrate the guarantees of long-term isolation and protection of the public. In parallel, socio-political studies have produced methodologies for constructive dialogue with potential host communities that reflect the honesty and openness expected by a democratic society. A harmonized legislative framework for nuclear safety and waste disposal across the enlarged European Union is currently being discussed. Disposal in deep (> 300 metre) geological repositories, the favoured strategy in Europe for long-lived high-level radioactive waste, is now possible. The Sessions on EC Policy and Socio-Political Issues are summarized as follows. The opening day of Euradwaste '04 focused on European Commission policy, including the proposed Directives on disposal of radioactive waste and nuclear safety and socio-political aspects including governance and decision making, public perception/acceptance of waste disposal and its sustainability. A decision on the proposed package will now be made after Union enlargement. Public agreement on the siting of

Unresolved safety issues summary: aqua book

International Nuclear Information System (INIS)

1983-06-01

The unresolved safety issues summary is designed to provide the management of the nuclear regulatory commission with a quarterly overview of the progress and plans for completion of generic tasks addressing unresolved safety issues reported to congress pursuant to section 210 of the Energy Reorganization Act of 1974 as amended. The schedules in this book include a milestone at the end of each action plan which represents the initiation of the implementation process both with respect to incorporation of the technical resolution in the NRC official guidance or requirements and also the application of changes to individual operating plants. The schedule for implementation will not normally be included in the task action plan(s) for the resolution of a USI since the nature and extent of the activities necessary to accomplish the implementation cannot normally be reasonably determined prior to the determination of a technical resolution. The progress and status for implementation of unresolved safety issues for which a technical resolution has been completed are reported specifically in a separate table provided in this summary

The Agency's Technical Co-operation programme with Argentina, 1982-1992. Country programme summaries

International Nuclear Information System (INIS)

1992-01-01

The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $7.5 million of Agency support received, Argentina ranks 22nd among all recipients of technical assistance during the period 1958 through 1991. Forty-six per cent of the assistance received during the past ten years has been provided in the form of equipment, complemented by expert services (40%) and training (14%). The largest share of the resources was made available by UNDP (87%), and only small shares were provided through the TACF (12%) and assistance in kind (less than 1%). With regard to total disbursements - by sector - under those projects that were operational during the period 1982 through mid-December 1992, by far the largest area has been nuclear engineering and technology (91%), while only very small shares went to nuclear safety (4%), industry and hydrology (3%) and agriculture (2%). During the same period, the country has provided experts and training course lectures for a total of 601 assignments, and has hosted 153 fellowships and scientific visits as well as 42 regional and interregional training courses with a total of 568 participants

75 FR 30804 - Biomass Research and Development Technical Advisory Committee

Science.gov (United States)

2010-06-02

... DEPARTMENT OF ENERGY Biomass Research and Development Technical Advisory Committee AGENCY.... SUMMARY: This notice announces an open meeting of the Biomass Research and Development Technical Advisory... public are welcome to observe the business of the Biomass Research and Development Technical Advisory...

75 FR 11526 - Biomass Research and Development Technical Advisory Committee

Science.gov (United States)

2010-03-11

... DEPARTMENT OF ENERGY Biomass Research and Development Technical Advisory Committee AGENCY.... SUMMARY: This notice announces an open meeting of the Biomass Research and Development Technical Advisory... public are welcome to observe the business of the Biomass Research and Development Technical Advisory...

75 FR 74026 - Biomass Research and Development Technical Advisory Committee

Science.gov (United States)

2010-11-30

... DEPARTMENT OF ENERGY Biomass Research and Development Technical Advisory Committee AGENCY.... SUMMARY: This notice announces an open meeting of the Biomass Research and Development Technical Advisory... participation. This notice announces the meeting of the Biomass Research and Development Technical Advisory...

Transfer of Air Force technical procurement bid set data to small businesses, using CALS and EDI. Summary report. Revision 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-01-10

This report provides a summary of the Air Force CALS Test Network (AFCTN) Test Report Transfer of Air Force Technical Procurement Bid Set Data to Small Businesses, Using CALS and EDI (AFCTN Test Report 94-034, UCRL-ID-118619). It represents a synthesis of the results, conclusions, and recommendations, as well as a more concise presentation of the issues and strategies as viewed from AFCTN`s perspective. This report documents a test transfer of three Air Force technical procurement bid sets to one large and twelve small businesses, using the Department of Defense (DoD) Continuous Acquisition and Life-cycle Support (CALS) and ANSI ASC X12 Electronic Data Interchange (EDI) standards. The main goal of the test was to evaluate the effectiveness of using CALS technical data within the context of the DoD`s EDI-based standard approach to electronic commerce in procurement, with particular emphasis on receipt and use of the data by small contractors. Air Force procurement data was provided by the Sacramento Air Logistics Center at McClellan Air Force Base; the manufacturing participants were selected from among McClellan`s {open_quote}Blue Ribbon{close_quote} contractors, located throughout the United States. The test was sponsored by the Air Force CALS Test Network, headquartered at Wright-Patterson Air Force Base. The test successfully demonstrated the technical feasibility of including CALS MIL-R-28002 (Raster) engineering data in an EDI Specification/Technical Information transaction set (ANSI ASC X12 841) when issuing electronic requests for quotation to small businesses. In many cases, the data was complete enough for the contractor participant to feel comfortable generating a quote.

FY 1996 activity summary

International Nuclear Information System (INIS)

1997-01-01

The US Department of Energy Office of Nuclear and Facility Safety provides nuclear safety policy, independent technical evaluation, and technical support. A summary of these activities is provided in this report. These include: (1) changing the mission of the former production facilities to storage and waste management; (2) stabilizing nuclear materials not recycled due to production cessation or interruptions; (3) reformulating the authorization basis for existing facilities to convert to a standards based approach for operations consistent with modern expectations; and (4) implementing a modern regulatory framework for nuclear facilities. Enforcement of the Price-Anderson Amendments Act is also reported

75 FR 56525 - Biomass Research and Development Technical Advisory Committee

Science.gov (United States)

2010-09-16

... DEPARTMENT OF ENERGY Biomass Research and Development Technical Advisory Committee AGENCY.... SUMMARY: This notice announces an open meeting of the Biomass Research and Development Technical Advisory... business of the Biomass Research and Development Technical Advisory Committee. To attend the meeting and/or...

Technical Evaluation Summary of the In Situ Vitrification Melt Expulsion at the Oak Ridge National Laboratory on April 21, 1996, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1996-11-01

This Technical Evaluation Summary of the In Situ Vitrification Melt Expulsion at the Oak Ridge National Laboratory on April 21, 1996, was prepared at the request of the Department of Energy as a supporting reference document for the Final Unusual Occurrence Report to fully explore the probable causes that lead to the subject incident. This document provides the Environmental Restoration Program with the technical information on the performance of the in situ vitrification treatability study operations at ORNL pit 1 up to and including the time of the melt expulsion incident. This document also attempts to diagnose the causes of the melt expulsion event the consequent damages to equipment the radiological impacts of the event, and the equipment design modifications and procedural changes necessary for future safe ISV operations

Analysis of baseline gene expression levels from ...

Science.gov (United States)

The use of gene expression profiling to predict chemical mode of action would be enhanced by better characterization of variance due to individual, environmental, and technical factors. Meta-analysis of microarray data from untreated or vehicle-treated animals within the control arm of toxicogenomics studies has yielded useful information on baseline fluctuations in gene expression. A dataset of control animal microarray expression data was assembled by a working group of the Health and Environmental Sciences Institute's Technical Committee on the Application of Genomics in Mechanism Based Risk Assessment in order to provide a public resource for assessments of variability in baseline gene expression. Data from over 500 Affymetrix microarrays from control rat liver and kidney were collected from 16 different institutions. Thirty-five biological and technical factors were obtained for each animal, describing a wide range of study characteristics, and a subset were evaluated in detail for their contribution to total variability using multivariate statistical and graphical techniques. The study factors that emerged as key sources of variability included gender, organ section, strain, and fasting state. These and other study factors were identified as key descriptors that should be included in the minimal information about a toxicogenomics study needed for interpretation of results by an independent source. Genes that are the most and least variable, gender-selectiv

THE 2014 ALMA LONG BASELINE CAMPAIGN: AN OVERVIEW

Energy Technology Data Exchange (ETDEWEB)

Partnership, ALMA [Astrophysics Research Institute, Liverpool John Moores University, IC2, Liverpool Science Park, 146 Brownlow Hill, Liverpool L3 5RF (United Kingdom); Fomalont, E. B.; Vlahakis, C.; Corder, S.; Remijan, A.; Barkats, D.; Dent, W. R. F.; Phillips, N.; Cox, P.; Hales, A. S. [Joint ALMA Observatory, Alonso de Córdova 3107, Vitacura, Santiago (Chile); Lucas, R. [Institut de Planétologie et d’Astrophysique de Grenoble (UMR 5274), BP 53, F-38041 Grenoble Cedex 9 (France); Hunter, T. R.; Brogan, C. L.; Amestica, R.; Cotton, W. [National Radio Astronomy Observatory, 520 Edgemont Road, Charlottesville, VA 22903 (United States); Asaki, Y. [National Astronomical Observatory of Japan, 2-21-1 Osawa, Mitaka, Tokyo 181-8588 (Japan); Matsushita, S. [Institute of Astronomy and Astrophysics, Academia Sinica, P.O. Box 23-141, Taipei 106, Taiwan (China); Hills, R. E. [Astrophysics Group, Cavendish Laboratory, JJ Thomson Avenue, Cambridge CB3 0HE (United Kingdom); Richards, A. M. S. [Jodrell Bank Centre for Astrophysics, School of Physics and Astronomy, University of Manchester, Oxford Road, Manchester M13 9PL (United Kingdom); Broguiere, D., E-mail: efomalon@nrao.edu [Institut de Radioastronomie Millime´trique (IRAM), 300 rue de la Piscine, Domaine Universitaire, F-38406 Saint Martin d’Hères (France); and others

2015-07-20

A major goal of the Atacama Large Millimeter/submillimeter Array (ALMA) is to make accurate images with resolutions of tens of milliarcseconds, which at submillimeter (submm) wavelengths requires baselines up to ∼15 km. To develop and test this capability, a Long Baseline Campaign (LBC) was carried out from 2014 September to late November, culminating in end-to-end observations, calibrations, and imaging of selected Science Verification (SV) targets. This paper presents an overview of the campaign and its main results, including an investigation of the short-term coherence properties and systematic phase errors over the long baselines at the ALMA site, a summary of the SV targets and observations, and recommendations for science observing strategies at long baselines. Deep ALMA images of the quasar 3C 138 at 97 and 241 GHz are also compared to VLA 43 GHz results, demonstrating an agreement at a level of a few percent. As a result of the extensive program of LBC testing, the highly successful SV imaging at long baselines achieved angular resolutions as fine as 19 mas at ∼350 GHz. Observing with ALMA on baselines of up to 15 km is now possible, and opens up new parameter space for submm astronomy.

THE 2014 ALMA LONG BASELINE CAMPAIGN: AN OVERVIEW

International Nuclear Information System (INIS)

Partnership, ALMA; Fomalont, E. B.; Vlahakis, C.; Corder, S.; Remijan, A.; Barkats, D.; Dent, W. R. F.; Phillips, N.; Cox, P.; Hales, A. S.; Lucas, R.; Hunter, T. R.; Brogan, C. L.; Amestica, R.; Cotton, W.; Asaki, Y.; Matsushita, S.; Hills, R. E.; Richards, A. M. S.; Broguiere, D.

2015-01-01

A major goal of the Atacama Large Millimeter/submillimeter Array (ALMA) is to make accurate images with resolutions of tens of milliarcseconds, which at submillimeter (submm) wavelengths requires baselines up to ∼15 km. To develop and test this capability, a Long Baseline Campaign (LBC) was carried out from 2014 September to late November, culminating in end-to-end observations, calibrations, and imaging of selected Science Verification (SV) targets. This paper presents an overview of the campaign and its main results, including an investigation of the short-term coherence properties and systematic phase errors over the long baselines at the ALMA site, a summary of the SV targets and observations, and recommendations for science observing strategies at long baselines. Deep ALMA images of the quasar 3C 138 at 97 and 241 GHz are also compared to VLA 43 GHz results, demonstrating an agreement at a level of a few percent. As a result of the extensive program of LBC testing, the highly successful SV imaging at long baselines achieved angular resolutions as fine as 19 mas at ∼350 GHz. Observing with ALMA on baselines of up to 15 km is now possible, and opens up new parameter space for submm astronomy

TECHNICAL EFFICIENCY AND IMPACT EVALUATION DIFFERENTIALS BETWEEN THE ADOPTERS AND NON-ADOPTERS OF NERICA IN THE SIX BASELINE STATES IN NIGERIA

Directory of Open Access Journals (Sweden)

Abiodun Elijah OBAYELU

2017-04-01

Full Text Available The study examined the adoption rate of New Rice for Africa (NERICA, technical efficiency differentials of production of these varieties between adopters and non-adopters and the determinants. It further analysed the impact of adoption of NERICA on area cultivated, output, yield, expenditure and total income of rice farmers in the NERICA baseline states in Nigeria. To achieve the objectives, it employed the descriptive statistics, stochastic production frontier and counterfactual outcomes framework of modern evaluation technique (the Local Average Treatment Effect to analyse 621 rice farmers across the six NERICA baseline states in Nigeria in 2012. The findings show that NERICA adopters were more technically efficient than the non-adopters. In addition, adoption of NERICA was found to significantly increase the areas of land cultivated, output, yield, household expenditure, per capita household expenditure and total income among NERICA adopters by 1.2ha (p < 0.01, 1998.2kg (p< 0.01, 191.2kg/ha (p < 0.1, N13,222.63≈$66.4 (p < 0.05, N2,015.6≈$10.1 (p < 0.05 and N145,098.7 ≈$728.0 (p < 0.01 respectively despite their high level of inefficiency (39 percent by the adopters. The positive impact of NERICA adoption on rice yields, poverty status measured by the per capita household expenditure and total farm income of farmers is a clear indication that NERICA has the potential to increase rice productivity, reduce poverty and food insecurity. NERICA adoption rate will rise if more farmers are aware of the varieties in the study. Farmers who had adopted, and government at all levels should therefore intensify their efforts to encourage others rice farmers possibly through the extension agents on the need to grow NERICA varieties so as to increase rice production level, reduce rice importation and ensure a sustainable rice production.

IAEA International Database on Irradiated Nuclear Graphite Properties. Summary report of consultants' meeting. 12. meeting of the Technical Steering Committee

International Nuclear Information System (INIS)

Chung, H.K.; Wickham, A.J.

2010-02-01

The 12th Meeting of the Technical Steering Committee for the International Database on Irradiated Nuclear Graphite Properties was held on 12-13 November 2009 at the IAEA Headquarters, Vienna, Austria. All discussions, recommendations and actions of this Consultants' Meeting are recorded in this report. The purposes of the meeting were to review the matters and actions identified in the previous meeting, undertake a review of the current status of the database, and make recommendations for action over the next year. This report contains the status of the identified actions as well as a summary of the recommendations on enhancements to the database. (author)

Decontaminated salt disposal as saltcrete in a landfill. Technical data summary

International Nuclear Information System (INIS)

1982-01-01

This technical data summary presents a reference process for immobilizing decontaminated salt solution from the 200-Area waste storage tanks with cement, and disposing of the final waste material (called saltcrete) by burial in trenches. The saltcrete will be protected from leaching by clay and will be placed at least 3 meters above the historic high water table and beneath at least 5 meters of soil overburden. The decontaminated salt solution is a waste material which remains after the bulk of the radionuclides have been removed from waste tank supernate. This removal is effected by contacting the waste supernate with sodium tetraphenyl boron (Na-TPB) and sodium titanate (NaTi 2 O 5 H). These materials remove (by precipitation) most of the 137 Cs and 90 Sr as well as many other radioactive and non-radioactive elements. These precipitates, along with many other sludges which reside in the HLW tanks will be incorporated in borosilicate glass for eventual disposal in a geologic repository. An ion exchange process will also be used for removal of 99 Tc. The decontaminated salt solution has sufficiently low levels of radioactivity that it can be disposed of on-site. The scope of the curent effort is to describe a process for blending decontaminated salt solution with cement to form a saltcrete product which has dimensional stability and relatively low leachability. The process is to be capable of solidifying 10 gpm of supernate. About 100 million gallons of salt solution is to be solidified

76 FR 80735 - Corrections and Technical Amendments to 16 OSHA Standards

Science.gov (United States)

2011-12-27

... 1926 Corrections and Technical Amendments to 16 OSHA Standards AGENCY: Occupational Safety and Health Administration (OSHA), Labor. ACTION: Notice of corrections and technical amendments to standards. SUMMARY: OSHA is correcting typographical errors in, and making non- substantive technical amendments to, 16 OSHA...

324 Building Baseline Radiological Characterization

International Nuclear Information System (INIS)

Reeder, R.J.; Cooper, J.C.

2010-01-01

This report documents the analysis of radiological data collected as part of the characterization study performed in 1998. The study was performed to create a baseline of the radiological conditions in the 324 Building. A total of 85 technical (100 square centimeter (cm 2 )) smears were collected from the Room 147 hoods, the Shielded Materials Facility (SMF), and the Radiochemical Engineering Cells (REC). Exposure rate readings (window open and window closed) were taken at a distance of 2.5 centimeters (cm) and 30 cm from the surface of each smear. Gross beta-gamma and alpha counts of each smear were also performed. The smear samples were analyzed by gamma energy analysis (GEA). Alpha energy analysis (AEA) and strontium-90 analysis were also performed on selected smears. GEA results for one or more samples reported the presence of manganese-54, cobalt-60, silver-108m antimony-125, cesium-134, cesium-137, europium-154, europium-155, and americium-241. AEA results reported the presence of plutonium-239/240, plutonium-238/ 241 Am, curium-243/244, curium-242, and americium-243. Tables 5 through 9 present a summary by location of the estimated maximum removable and total contamination levels in the Room 147 hoods, the SMF, and the REC. The smear sample survey data and laboratory analytical results are presented in tabular form by sample in Appendix A. The Appendix A tables combine survey data documented in radiological survey reports found in Appendix B and laboratory analytical results reported in the 324 Building Physical and Radiological Characterization Study (Berk, Hill, and Landsman 1998), supplemented by the laboratory analytical results found in Appendix C.

Authorization Decree Application for the creation of the Flamanville-3 Basic Nuclear Installation. Executive Summary of the Technical Review

International Nuclear Information System (INIS)

2009-01-01

On 9 May 2006, Electricite de France (EDF) submitted to the Ministers for Nuclear Safety an authorization decree application for an EPR-type reactor on the site of the Flamanville Nuclear Power Plant (NPP). Article 29 of Act No. 2006-686 of 13 June 2006 on Transparency and Security in the Nuclear Field prescribes that the creation of any basic nuclear installation shall be issued by a decree taken after consultation with the Nuclear Safety Authority (Autorite de surete nucleaire - ASN). The purpose of this report is to provide ASN's Board with a summary of the technical review led by ASN services and carried out by their technical support agencies, namely the IRSN, the GPR and the Standing Nuclear Section of the CCAP between 2001 and 2006. After summing up the conclusions of the review on the safety options of the European Pressurized Reactor (EPR) Project, as carried out between 1993 and 2000, this report describes the process and modalities of the review conducted from 2001 to 2006. Besides providing the opinion of ASN's services on the creation-licence application, it also outlines the further review to be carried out, if the authorization decree is issued. (authors)

Compendium of Executive Summaries from the Maglev System Concept Definition. Final Reports.

Science.gov (United States)

1993-03-01

This report contains the Executive Summaries from the four System Concept Definition (SCD) studies awarded under the National Maglev Initiative...These summaries present the technical feasibility, performance, capital, operating and maintenance costs for a maglev system that would be available by

Corrective action baseline report for underground storage tank 2331-U Building 9201-1

International Nuclear Information System (INIS)

1994-01-01

The purpose of this report is to provide baseline geochemical and hydrogeologic data relative to corrective action for underground storage tank (UST) 2331-U at the Building 9201-1 Site. Progress in support of the Building 9201-1 Site has included monitoring well installation and baseline groundwater sampling and analysis. This document represents the baseline report for corrective action at the Building 9201-1 site and is organized into three sections. Section 1 presents introductory information relative to the site, including the regulatory initiative, site description, and progress to date. Section 2 includes the summary of additional monitoring well installation activities and the results of baseline groundwater sampling. Section 3 presents the baseline hydrogeology and planned zone of influence for groundwater remediation

Biopower Technical Strategy Workshop Summary Report

Energy Technology Data Exchange (ETDEWEB)

none,

2010-12-01

Biopower is electricity produced from a wide range of biomass (organic materials found in wood, plants, agricultural waste and other materials). Biomass is a base load renewable energy source with high availability for electricity production. To explore opportunities for biopower in the United States, the U.S. Department of Energy (DOE), Office of Energy Efficiency and Renewable Energy Biomass Program conducted the Biopower Technical Strategy Workshop in Denver, Colorado, on December 2–3, 2009. This report summarizes the results of the workshop, which focused on challenges to the expanded use of biopower and the possible solutions, including technology research, development, and demonstration (RD&D) as well as policies and other market transformation mechanisms.

Fusion Engineering Device. Volume 1. Mission and program summary

International Nuclear Information System (INIS)

1981-10-01

This volume presents, in summary form, a recommended approach to implementing the Magnetic Fusion Energy Engineering Act of 1980. These recommendations constitute the findings of the FED Technical Management Board (TMB). The TMB and the affiliated technical managers gave particular scrutiny to elucidating the role of FED in fusion development and to defining the device mission

Summaries of FY 1989 research in the chemical sciences

International Nuclear Information System (INIS)

1989-08-01

These summaries provide the scientific and technical public, as well as the legislative and executive branches of the Government, information, either generally or in some depth, about the Chemical Sciences program. Areas of research supported are indicated in the section headings, the ''Selected Topics of General Interest'' list, and the summaries themselves. Energy technologies that may be advanced by use of the basic knowledge generated in this program are included in the ''Selected Topics of General Interest'' list and are often referenced in the summaries

The international linear collider. Technical design report. Vol. 1. Executive summary

Energy Technology Data Exchange (ETDEWEB)

Behnke, Ties; Brau, James E.; Foster, Brian; Fuster, Juan; Harrison, Mike; McEwan Paterson, James; Peskin, Michael; Stanitzki, Marcel; Walker, Nicholas; Yamamoto, Hitoshi (eds.)

2013-07-01

A review is given about the planned International Linear Collider. Especially described are the technical design, the accelerator layout and design, the R and D during the technical design phase, and the detectors. (HSI)

The international linear collider. Technical design report. Vol. 1. Executive summary

International Nuclear Information System (INIS)

Behnke, Ties; Brau, James E.; Foster, Brian; Fuster, Juan; Harrison, Mike; McEwan Paterson, James; Peskin, Michael; Stanitzki, Marcel; Walker, Nicholas; Yamamoto, Hitoshi

2013-01-01

A review is given about the planned International Linear Collider. Especially described are the technical design, the accelerator layout and design, the R and D during the technical design phase, and the detectors. (HSI)

The Agency's technical co-operation activities in 1993

International Nuclear Information System (INIS)

1994-08-01

This document reviews the IAEA's Technical Cooperation activities for 1993. Apart from an overview, the report contains reviews by Agency programmes and technical divisions, by area, by component and by fund. Summaries of project implementation are also included, as well as indications of the achievements of projects completed in 1993

Continuum of eLearning: 2012 Project Summary Report

Science.gov (United States)

2012-10-01

multimedia, and Continuum of eLearning | Purpose and Vision 19 << UNCLASSIFIED>> (limited) situated learning. Future versions of the CoL self-paced...Continuum of eLearning : 2012 Project Summary Report Continuum of eLearning The Next Evolution of Joint Training on JKO October 2012 Joint...Technical Report November 2011 – August 2012 Continuum of eLearning : 2012 Project Summary Report N00140-06-D-0060 David T. Fautua, Sae Schatz, Andrea

SCOPING SUMMARY FOR THE P-AREA OPERABLE UNIT

International Nuclear Information System (INIS)

Kupar, J; Sadika Baladi, S; Mark Amidon, M

2007-01-01

This scoping summary supports development of the combined Remedial Investigation (RI)/Baseline Risk Assessment (BRA)/Feasibility Study (FS) for the P-Area Operable Unit (PAOU), or Combined document, which will be submitted on or before 09/28/2007. The objective of this Feasibility Study scoping summary meeting is to agree on the likely response actions to be evaluated and developed as alternatives in the combined document and agree on the uncertainties identified and whether they have been adequately managed

SCOPING SUMMARY FOR THE P-AREA OPERABLE UNIT

Energy Technology Data Exchange (ETDEWEB)

Kupar, J; Sadika Baladi, S; Mark Amidon, M

2007-05-22

This scoping summary supports development of the combined Remedial Investigation (RI)/Baseline Risk Assessment (BRA)/Feasibility Study (FS) for the P-Area Operable Unit (PAOU), or Combined document, which will be submitted on or before 09/28/2007. The objective of this Feasibility Study scoping summary meeting is to agree on the likely response actions to be evaluated and developed as alternatives in the combined document and agree on the uncertainties identified and whether they have been adequately managed.

Underground storage tank - Integrated Demonstration Technical Task Plan master schedule

International Nuclear Information System (INIS)

Johnson, C.M.

1994-08-01

This document provides an integrated programmatic schedule (i.e., Master Schedule) for the U.S. Department of Energy (DOE) Underground Storage Tank-Integrated Demonstration (UST-ID) Program. It includes top-level schedule and related information for the DOE Office of Technology Development (EM-50) UST-ID activities. The information is based upon the fiscal year (FY) 1994 technical task plans (TTPS) and has been prepared as a baseline information resource for program participants. The Master Schedule contains Level 0 and Level 1 program schedules for the UST-ID Program. This document is one of a number of programmatic documents developed to support and manage the UST-ID activities. It is composed of the following sections: Program Overview - provides a summary background of the UST-ID Program. This summary addresses the mission, scope, and organizational structure of the program; Activity Description - provides a programmatic description of UST-ID technology development activities and lists the key milestones for the UST-ID systems. Master Schedules - contains the Level 0 and Level 1 programmatic schedules for the UST-ID systems. References - lists the UST-ID programmatic documents used as a basis for preparing the Master Schedule. The appendixes contain additional details related to site-specific technology applications

Summary report of consultants meeting on IAEA International Database on Irradiated Nuclear Graphite Properties. 11. meeting of the Technical Steering Committee

International Nuclear Information System (INIS)

Humbert, D.; Wickham, A.J.

2009-05-01

The 11th Meeting of the Technical Steering Committee for the International Database on Irradiated Nuclear Graphite Properties was held on 25-26 March 2009 at the IAEA Headquarters, Vienna, Austria. All discussions, recommendations and actions of this Consultants' Meeting are recorded in this report. The purposes of the meeting were to review the matters and actions identified in the previous meeting, undertake a review of the current status of the database, and make recommendations for action over the next year. This report contains the status of the identified actions as well as a summary of the recommendations on enhancements to the database. (author)

Summary report of consultants' meeting - IAEA International Database on Irradiated Nuclear Graphite Properties. 8th meeting of the Technical Steering Committee

International Nuclear Information System (INIS)

Humbert, D.; Wickham, A.J.

2006-05-01

The '8th Meeting of the Technical Steering Committee for the International Database on Irradiated Nuclear Graphite Properties' was held on 15-16 March 2006 at the IAEA Headquarters, Vienna, Austria. All discussions, recommendations and actions of this Consultants' Meeting are recorded in this report. The purposes of the meeting were to review the matters and actions identified in the previous meeting, undertake a review of the current status of the database and make recommendations for actions for the next year. This report contains the current status of the identified actions as well as a summary of the recommendations on enhancements to the database. (author)

III Scientific-technical conference. Problems and outlooks for development of chemical and radiochemical control in atomic energetics (Atomenergoanalytics-2005). Summaries of reports

International Nuclear Information System (INIS)

2005-01-01

Summaries of reports of the III Scientific-technical conference: Problems and outlooks for development of chemical and radiochemical control in atomic energetics (Atomenergoanalytics-2005) are presented. The conference performed 20-22 September, 2005, in Sosnovyj Bor. Problems of methodical, instrumental and metrological supply of chemical, radiochemical and radiometric control at active NPP and NPU, modern concepts of construction of automated systems of chemical and radiometric control in the atomic energetics, directions for the decision of questions in organization and conducting of chemical and radiochemical control of water-chemical regimes of NPP and NPU are discussed [ru

Do SF-36 summary scores work as outcome measures in chronic functional disorders?

DEFF Research Database (Denmark)

Schröder, Andreas; Ørnbøl, Eva; Fink, Per

controlled trial on cognitive behavioural therapy in patients with severe and chronic functional disorders. Based on a pilot study and baseline data, we have assessed the performance of the summary scores. Aim To demonstrate problems in the orthogonal factor solution for PCS and MCS and to assess other...... based on an oblique factor solution and the summary components from the RAND-36 HSI. Results Pilot study: Improvement on subscales of physical health was not reflected by the original PCS. The three methods showed different results with regard to individual changes over time. Baseline data: Surprisingly...

System for technical innovation support

International Nuclear Information System (INIS)

2011-08-01

This book lists field of support system, which includes tax, development work, basic research project, industrial technology, information and communications field, energy field, part and materials field, local industry, the small and medium business such as technical development field, and industry-university collaboration like summary of investment and financing support and guarantee, support of manpower such as brain pool and contact Korea, support of technique like development technology and strategy for patent, support on certification such as company and technical goods, purchase support.

IAEA technical meeting on 'Technical aspects of atomic and molecular data processing and exchange'. Summary report

International Nuclear Information System (INIS)

Humbert, Denis

2004-03-01

The proceedings of the IAEA Advisory Group Meeting on 'Technical Aspects of Atomic and Molecular Data Processing and Exchange' (17th Meeting of A+M Data Centres and ALADDIN Network), held on 6-7 October, 2003 in Vienna, Austria are briefly described. The meeting conclusions and recommendations on the priorities in A+M data compilation and evaluation, and on the technical aspects of data processing, exchange, and distribution are also presented. (author)

Livermore Big Trees Park: 1998 summary results; TOPICAL

International Nuclear Information System (INIS)

Gallegos, G; MacQueen, D; Surano, K

1999-01-01

This report summarizes work conducted in 1998 by the Lawrence Livermore National Laboratory (LLNL) to determine the extent and origin of plutonium at concentrations above background levels at Big Trees Park in the city of Livermore. This summary includes the project background and sections that explain the sampling, radiochemical and data analysis, and data interpretation. This report is a summary report only and is not intended as a rigorous technical or statistical analysis of the data

Utilities and offsites design baseline. Outside Battery Limits Facility 6000 tpd SRC-I Demonstration Plant. Volume 1

Energy Technology Data Exchange (ETDEWEB)

None

1984-05-25

As part of the overall Solvent Refined Coal (SRC-1) project baseline being prepared by International Coal Refining Company (ICRC), the RUST Engineering Company is providing necessary input for the Outside Battery Limits (OSBL) Facilities. The project baseline is comprised of: design baseline - technical definition of work; schedule baseline - detailed and management level 1 schedules; and cost baseline - estimates and cost/manpower plan. The design baseline (technical definition) for the OSBL Facilities has been completed and is presented in Volumes I, II, III, IV, V and VI. The OSBL technical definition is based on, and compatible with, the ICRC defined statement of work, design basis memorandum, master project procedures, process and mechanical design criteria, and baseline guidance documents. The design basis memorandum is included in Paragraph 1.3 of Volume I. The baseline design data is presented in 6 volumes. Volume I contains the introduction section and utility systems data through steam and feedwater. Volume II continues with utility systems data through fuel system, and contains the interconnecting systems and utility system integration information. Volume III contains the offsites data through water and waste treatment. Volume IV continues with offsites data, including site development and buildings, and contains raw materials and product handling and storage information. Volume V contains wastewater treatment and solid wastes landfill systems developed by Catalytic, Inc. to supplement the information contained in Volume III. Volume VI contains proprietary information of Resources Conservation Company related to the evaporator/crystallizer system of the wastewater treatment area.

77 FR 50488 - Hydrogen and Fuel Cell Technical Advisory Committee

Science.gov (United States)

2012-08-21

... DEPARTMENT OF ENERGY Hydrogen and Fuel Cell Technical Advisory Committee AGENCY: Department of...). SUMMARY: This notice announces an open meeting (Webinar) of the Hydrogen and Fuel Cell Technical Advisory... Avenue, Washington, DC 20585. SUPPLEMENTARY INFORMATION: Purpose of the Committee: The Hydrogen and Fuel...

Minutes of the IFMIF technical meeting

International Nuclear Information System (INIS)

Nakamura, H.; Takeda, M.; Ida, M.; Maebara, S.; Yutani, T.; Sugimoto, M.

2004-03-01

The IFMIF Technical Meeting was held on December 4-5, 2003 at Shiran-kaikan, Kyoto University. The main objectives are 1) to finalize the Comprehensive Design Report (CDR), 2) to discuss IFMIF cost and organization, 3) to review technical status of major systems, transition phase activities and EVEDA plan. This report presents a brief summary of the results of the meeting. Agenda, participants list and presentation materials are attached as Appendix. (author)

Safety evaluation of the ESP sludge washing baselines runs. Revision 2

International Nuclear Information System (INIS)

Gupta, M.K.

1993-01-01

Purpose is to provide the technical basis for evaluation of unreviewed safety question for the Extended Sludge Processing (ESP) Sludge Washing Baseline Runs, which are necessary to resolve technical questions associated with process control (sludge suspension, sludge settling, heat transfer, temperature control). The sludge is currently stored in below-ground tanks and will be prepared for processing at the Defense Waste Processing Facility as part of the Integrated Waste Removal Program for Savannah River Site

NHTSA's Office of Defects Investigation (ODI) - Technical Service Bulletins System (TSBS) - Downloadable file

Data.gov (United States)

Department of Transportation — The Technical Service Bulletins data contains summaries of the Manufacturers' Technical Service Bulletins by single year, make and model. An optional item of Vehicle...

75 FR 62509 - Technical Advisory Committees; Notice of Recruitment of Private-Sector Members

Science.gov (United States)

2010-10-12

... DEPARTMENT OF COMMERCE Bureau of Industry and Security Technical Advisory Committees; Notice of Recruitment of Private- Sector Members SUMMARY: Seven Technical Advisory Committees (TACs) advise the Department of Commerce on the technical parameters for export controls applicable to dual-use commodities and...

77 FR 2271 - Technical Advisory Committees; Notice of Recruitment of Private-Sector Members

Science.gov (United States)

2012-01-17

... DEPARTMENT OF COMMERCE Bureau of Industry and Security Technical Advisory Committees; Notice of Recruitment of Private- Sector Members SUMMARY: Seven Technical Advisory Committees (TACs) advise the Department of Commerce on the technical parameters for export controls applicable to dual-use commodities and...

78 FR 5774 - Technical Advisory Committees; Notice of Recruitment of Private-Sector Members

Science.gov (United States)

2013-01-28

... DEPARTMENT OF COMMERCE Bureau of Industry and Security Technical Advisory Committees; Notice of Recruitment of Private- Sector Members SUMMARY: Seven Technical Advisory Committees (TACs) advise the Department of Commerce on the technical parameters for export controls applicable to dual-use commodities and...

77 FR 32712 - Technical Report: Evaluation of the Enhancing Vehicle-to-Vehicle Crash Compatibility Agreement...

Science.gov (United States)

2012-06-01

...-0070] Technical Report: Evaluation of the Enhancing Vehicle-to-Vehicle Crash Compatibility Agreement... comments on technical report. SUMMARY: This notice announces NHTSA's publication of a Technical Report... be received no later than October 1, 2012. ADDRESSES: Report: The technical report is available on...

Summary Report of Second Research Coordination Meeting on Prompt Fission Neutron Spectra of Major Actinides

International Nuclear Information System (INIS)

Capote Noy, R.

2013-09-01

A summary is given of the Second Research Coordination Meeting on Prompt Fission Neutron Spectra of Actinides. Experimental data and modelling methods on prompt fission neutron spectra were reviewed. Extensive technical discussions held on theoretical methods to calculate prompt fission spectra. Detailed coordinated research proposals have been agreed. Summary reports of selected technical presentations at the meeting are given. The resulting work plan of the Coordinated Research Programme is summarized, along with actions and deadlines. (author)

Separations innovative concepts: Project summary

Energy Technology Data Exchange (ETDEWEB)

Lee, V.E. (ed.)

1988-05-01

This project summary includes the results of 10 innovations that were funded under the US Department's Innovative Concept Programs. The concepts address innovations that can substantially reduce the energy used in industrial separations. Each paper describes the proposed concept, and discusses the concept's potential energy savings, market applications, technical feasibility, prior work and state of the art, and future development needs.

Summary of IAEA technical committee meeting on impurity control

International Nuclear Information System (INIS)

Itoh, Kimitaka.

1989-03-01

Presentations given in the IAEA technical committee meeting on impurity control (held in JAERI from 13 to 15 February, 1989) are summarized, putting the emphasis on the physics modelling of the plasma related to the impurity production and confinement. (author)

Independent Technical Review of In-Tank Precipitation (ITP) at the Savannah River Site

International Nuclear Information System (INIS)

1993-06-01

An Independent Technical Review of In-Tank Precipitation (ITP) and Extended Sludge Processing (ESP) at the Savannah River Site (SRS) was carried out in March, 1993. The review focused on ITP/ESP equipment and chemical processes, integration of ITP/ESP within the High Level Waste (HLW) and Defense Waste Processing Facility (DWPF) systems, and management and regulatory concerns. Following the ITR executive summary, this report includes: Chapter I--summary assessment; Chapter II--recommendations; and Chapter III--technical evaluations

F/H effluent treatment facility. Technical data summary

International Nuclear Information System (INIS)

Ryan, J.P.; Stimson, R.E.

1984-12-01

This document provides the technical basis for the design of the facility. Some of the sections are described with options to permit simplification of the process, depending on the effluent quality criteria that the facility will have to meet. Each part of the F/HETF process is reviewed with respect to decontamination and concentration efficiency, operability, additional waste generation, energy efficiency, and compatability with the rest of the process

Unresolved safety issues summary. Volume 3, Number 3. Aqua book

International Nuclear Information System (INIS)

1981-01-01

The 'Unresolved Safety Issues' summary is designed to provide the management of the Nuclear Regulatory Commission with a quarterly overview of the progress and plans for completion of generic tasks addressing Unresolved Safety Issues reported to Congress pursuant to section 210 of The Energy Reorganization Act of 1974 as amended. This summary utilizes data collected from the Office of Nuclear Reactor Regulation, Office of Nuclear Regulatory Research, and the National Laboratories and is prepared by the office of Management and Program Analysis. The definition of what constitutes completion of an unresolved safety issue (USI) has recently been expanded to include the implementation of the technical resolution. This is in acknowledgement of the fact that real safety benefits occur only after the implementation has taken place. The schedules in this book include a milestone at the end of each action plan which represents the initiation of the implementation process both with respect to incorporation of the technical resolution in the NRC official guidance or requirements and also the application of changes to individual operating plants. The schedule for implementation will not normally be included in the task action plan(s) for the resolution of a USI since the nature and extent of the activities necessary to accomplish the implementation cannot normally be reasonably determined prior to the determination of a technical resolution. The progress and status for implementation of unresolved safety issues for which a technical resolution has been completed are reported specifically in a separate table provided in this summary

Alternative technical summary report for immobilized disposition in deep boreholes: Immobilized disposal of plutonium in coated ceramic pellets in grout without canisters, Version 4.0. Fissile materials disposition program

International Nuclear Information System (INIS)

Wijesinghe, A.M.

1996-01-01

This paper summarizes and compares the immobilized and direct borehole disposition alternatives previously presented in the alternative technical summary. The important design concepts, facility features and operational procedures are first briefly described. This is followed by a discussion of the issues that affect the evaluation of each alternative against the programmatic assessment criteria that have been established for selecting the preferred alternatives for plutonium disposition

Alternative technical summary report for immobilized disposition in deep boreholes: Immobilized disposal of plutonium in coated ceramic pellets in grout without canisters, Version 4.0. Fissile materials disposition program

Energy Technology Data Exchange (ETDEWEB)

Wijesinghe, A.M.

1996-08-23

This paper summarizes and compares the immobilized and direct borehole disposition alternatives previously presented in the alternative technical summary. The important design concepts, facility features and operational procedures are first briefly described. This is followed by a discussion of the issues that affect the evaluation of each alternative against the programmatic assessment criteria that have been established for selecting the preferred alternatives for plutonium disposition.

Accelerated Best Basis Inventory Baselining Task

International Nuclear Information System (INIS)

SASAKI, L.M.

2001-01-01

The baselining effort was recently proposed to bring the Best-Basis Inventory (BBI) and Question No.8 of the Tank Interpretive Report (TIR) for all 177 tanks to the current standards and protocols and to prepare a TIR Question No.8 if one is not already available. This plan outlines the objectives and methodology of the accelerated BBI baselining task. BBI baselining meetings held during December 2000 resulted in a revised BBI methodology and an initial set of BBI creation rules to be used in the baselining effort. The objectives of the BBI baselining effort are to: (1) Provide inventories that are consistent with the revised BBI methodology and new BBI creation rules. (2) Split the total tank waste in each tank into six waste phases, as appropriate (Supernatant, saltcake solids, saltcake liquid, sludge solids, sludge liquid, and retained gas). In some tanks, the solids and liquid portions of the sludge and/or saltcake may be combined into a single sludge or saltcake phase. (3) Identify sampling events that are to be used for calculating the BBIs. (4) Update waste volumes for subsequent reconciliation with the Hanlon (2001) waste tank summary. (5) Implement new waste type templates. (6) Include any sample data that might have been unintentionally omitted in the previous BBI and remove any sample data that should not have been included. Sample data to be used in the BBI must be available on TWINS. (7) Ensure that an inventory value for each standard BBI analyte is provided for each waste component. Sample based inventories for supplemental BBI analytes will be included when available. (8) Provide new means and confidence interval reports if one is not already available and include uncertainties in reporting inventory values

Software configuration management plan for the Hanford site technical database

International Nuclear Information System (INIS)

GRAVES, N.J.

1999-01-01

The Hanford Site Technical Database (HSTD) is used as the repository/source for the technical requirements baseline and programmatic data input via the Hanford Site and major Hanford Project Systems Engineering (SE) activities. The Hanford Site SE effort has created an integrated technical baseline for the Hanford Site that supports SE processes at the Site and project levels which is captured in the HSTD. The HSTD has been implemented in Ascent Logic Corporation (ALC) Commercial Off-The-Shelf (COTS) package referred to as the Requirements Driven Design (RDD) software. This Software Configuration Management Plan (SCMP) provides a process and means to control and manage software upgrades to the HSTD system

Baseline radiological monitoring at proposed uranium prospecting site at Rohil Sikar, Rajasthan

International Nuclear Information System (INIS)

Kumar, Rajesh; Jha, V.N.; Sahoo, N.K.; Jha, S.K.; Tripathi, R.M.

2018-01-01

Once economically viable grades of uranium deposits are proposed for mining and processing by the industry radiological baseline studies are required for future comparison during operational phases. The information collected during such studies serve as connecting feature between regulatory compliance and technical information. Present paper summarizes the results of baseline monitoring of atmospheric 222 Rn and gamma level in the area at prospecting mining, milling and waste disposal sites of Rohil Rajasthan

Summary status of K Basins sludge characterization

International Nuclear Information System (INIS)

Baker, R.B.

1995-01-01

A number of activities are underway as part of the Spent Nuclear Fuels Project (SNFP) related to the processing and disposing of sludge in the 105-K Basins (K Basins). Efforts to rigorously define data requirements for these activities are being made using the Data Quality Objectives (DQO) process. Summaries of current sludge characterization data are required to both help support this DQO process and to allow continued progress with on-going engineering activities (e.g., evaluations of disposal alternatives). This document provides the status of K Basins sludge characterization data currently available to the Nuclear Fuel Evaluations group. This group is tasked by the SNFP to help develop and maintain the characterization baseline for the K Basins. The specific objectives of this document are to: (1) provide a current summary (and set of references) of sludge characterization data for use by SNFP initiatives, to avoid unnecessary duplication of effort and to support on-going initiatives; (2) submit these data to an open forum for review and comment, and identify additional sources of significant data that may be available; (3) provide a summary of current data to use as part of the basis to develop requirements for additional sludge characterization data through the DQO process; (4) provide an overview of the intended activities that will be used to develop and maintain the sludge characterization baseline

78 FR 6086 - Hydrogen and Fuel Cell Technical Advisory Committee (HTAC)

Science.gov (United States)

2013-01-29

... DEPARTMENT OF ENERGY Hydrogen and Fuel Cell Technical Advisory Committee (HTAC) AGENCY: Office of...). SUMMARY: This notice announces an open meeting (Webinar) of the Hydrogen and Fuel Cell Technical Advisory... Avenue, Washington, DC 20585. SUPPLEMENTARY INFORMATION: Purpose of the Committee: The Hydrogen and Fuel...

77 FR 2714 - Hydrogen and Fuel Cell Technical Advisory Committee (HTAC)

Science.gov (United States)

2012-01-19

... DEPARTMENT OF ENERGY Hydrogen and Fuel Cell Technical Advisory Committee (HTAC) AGENCY: Department.... SUMMARY: This notice announces an open meeting of the Hydrogen and Fuel Cell Technical Advisory Committee... posted on http://hydrogen.energy.gov ). Public Comment (10 minutes) Discussion of HTAC's draft annual...

Technical summary of groundwater quality protection program at Savannah River Plant. Volume 1. Site geohydrology, and solid and hazardous wastes

International Nuclear Information System (INIS)

Christensen, E.J.; Gordon, D.E.

1983-12-01

The program for protecting the quality of groundwater underlying the Savannah River Plant (SRP) is described in this technical summary report. The report is divided into two volumes. Volume I contains a discussion of the general site geohydrology and of both active and inactive sites used for disposal of solid and hazardous wastes. Volume II includes a discussion of radioactive waste disposal. Most information contained in these two volumes is current as of December 1983. The groundwater quality protection program has several elements which, taken collectively, are designed to achieve three major goals. These goals are to evaluate the impact on groundwater quality as a result of SRP operations, to restore or protect groundwater quality by taking corrective action as necessary, and to ensure disposal of waste materials in accordance with regulatory guidelines

Guam Initial Technical Assessment Report

Energy Technology Data Exchange (ETDEWEB)

Baring-Gould, I.; Conrad, M.; Haase, S.; Hotchkiss, E.; McNutt, P.

2011-04-01

Under an interagency agreement, funded by the Department of Interior's (DOI) Office of Insular Affairs (OIA), the National Renewable Energy Laboratory (NREL) was tasked to deliver technical assistance to the island of Guam by conducting an island initial technical assessment that would lay out energy consumption and production data and establish a baseline. This assessment will be used to conduct future analysis and studies by NREL that will estimate energy efficiency and renewable energy potential for the island of Guam.

OCRWM baseline management procedure for document identifiers

International Nuclear Information System (INIS)

1993-03-01

This procedure establishes a uniform numbering system (document identifier) for all Program and project technical, cost, and schedule baselines, and selected management and procurement documents developed for and controlled by the Office of Civilian Radioactive Waste Management (OCRWM) for the Civilian Radioactive Waste Management System (CRWMS). The document identifier defined in this procedure is structured to ensure that the relational integrity between configuration items (CIs) and their associated documentation and software is maintained, traceable, categorical, and retrievable for the life of the program

77 FR 18243 - Hydrogen and Fuel Cell Technical Advisory Committee (HTAC); Notice of Open Meeting

Science.gov (United States)

2012-03-27

... DEPARTMENT OF ENERGY Hydrogen and Fuel Cell Technical Advisory Committee (HTAC); Notice of Open... open meeting. SUMMARY: This notice announces a meeting of the Hydrogen and Fuel Cell Technical Advisory... Committee: The Hydrogen and Fuel Cell Technical Advisory Committee (HTAC) was established under Section 807...

2011 Residential Energy Efficiency Technical Update Meeting Summary Report

Energy Technology Data Exchange (ETDEWEB)

none,

2011-11-01

This report provides an overview of the U.S. Department of Energy Building America program's Summer 2011 Residential Energy Efficiency Technical Update Meeting. This meeting was held on August 9-11, 2011, in Denver, Colorado, and brought together more than 290 professionals representing organizations with a vested interest in energy efficiency improvements in residential buildings.

Site systems engineering fiscal year 1999 multi-year work plan (MYWP) update for WBS 1.8.2.2; TOPICAL

International Nuclear Information System (INIS)

GRYGIEL, M.L.

1998-01-01

Manage the Site Systems Engineering process to provide a traceable integrated requirements-driven, and technically defensible baseline. Through the Site Integration Group(SIG), Systems Engineering ensures integration of technical activities across all site projects. Systems Engineering's primary interfaces are with the RL Project Managers, the Project Direction Office and with the Project Major Subcontractors, as well as with the Site Planning organization. Systems Implementation: (1) Develops, maintains, and controls the site integrated technical baseline, ensures the Systems Engineering interfaces between projects are documented, and maintain the Site Environmental Management Specification. (2) Develops and uses dynamic simulation models for verification of the baseline and analysis of alternatives. (3) Performs and documents fictional and requirements analyses. (4) Works with projects, technology management, and the SIG to identify and resolve technical issues. (5) Supports technical baseline information for the planning and budgeting of the Accelerated Cleanup Plan, Multi-Year Work Plans, Project Baseline Summaries as well as performance measure reporting. (6) Works with projects to ensure the quality of data in the technical baseline. (7) Develops, maintains and implements the site configuration management system

Technical Basis for PNNL Beryllium Inventory

Energy Technology Data Exchange (ETDEWEB)

Johnson, Michelle Lynn

2014-07-09

The Department of Energy (DOE) issued Title 10 of the Code of Federal Regulations Part 850, “Chronic Beryllium Disease Prevention Program” (the Beryllium Rule) in 1999 and required full compliance by no later than January 7, 2002. The Beryllium Rule requires the development of a baseline beryllium inventory of the locations of beryllium operations and other locations of potential beryllium contamination at DOE facilities. The baseline beryllium inventory is also required to identify workers exposed or potentially exposed to beryllium at those locations. Prior to DOE issuing 10 CFR 850, Pacific Northwest Nuclear Laboratory (PNNL) had documented the beryllium characterization and worker exposure potential for multiple facilities in compliance with DOE’s 1997 Notice 440.1, “Interim Chronic Beryllium Disease.” After DOE’s issuance of 10 CFR 850, PNNL developed an implementation plan to be compliant by 2002. In 2014, an internal self-assessment (ITS #E-00748) of PNNL’s Chronic Beryllium Disease Prevention Program (CBDPP) identified several deficiencies. One deficiency is that the technical basis for establishing the baseline beryllium inventory when the Beryllium Rule was implemented was either not documented or not retrievable. In addition, the beryllium inventory itself had not been adequately documented and maintained since PNNL established its own CBDPP, separate from Hanford Site’s program. This document reconstructs PNNL’s baseline beryllium inventory as it would have existed when it achieved compliance with the Beryllium Rule in 2001 and provides the technical basis for the baseline beryllium inventory.

78 FR 64146 - 30-Day Notice of Proposed Information Collection: Technical Processing Requirements for...

Science.gov (United States)

2013-10-25

... Information Collection: Technical Processing Requirements for Multifamily Project Mortgage Insurance AGENCY: Office of the Chief Information Officer, HUD. ACTION: Notice. SUMMARY: HUD has submitted the proposed... Information Collection Title of Information Collection: Technical Processing Requirements for Multifamily...

Study of tunnelling through water-bearing fracture zones. Baseline study on technical issues with NE-1 as reference

International Nuclear Information System (INIS)

Yanting Chang; Swindell, Robert; Bogdanoff, Ingvar; Lindstroem, Beatrice; Termen, Jens; Starsec, Peter

2005-04-01

The Swedish Nuclear Fuel and Waste Management Co (SKB) is responsible for the management of Sweden's nuclear waste. SKB is investigating various designs for the construction of an underground deep repository for spent nuclear fuel at 500-600 m depths. For the construction of an access tunnel for such a deep repository, the possibility of encountering a water-bearing fracture zone cannot be discounted. Such a zone named NE-1 (deformation zone in accordance to SKB's terminology) was encountered during the construction of the Aespoe Hard Rock Laboratory (HRL) and difficulties with large water inflows were reported. With the aim to assess the feasibility of different technical solutions, SKB commissioned a baseline study into the passage of an access tunnel through a water-bearing fracture zone at three different depths (200 m, 400 m and 600 m). The objectives of this baseline study are to: Increase the knowledge of possible technical solutions for tunnelling through water-bearing fractures zones with the characteristics of the brittle deformation zone NE-1 at different depths, namely 200, 400 and 600 metres; Form a reference document to assist the engineering design and construction work for the passage through such a water-bearing fracture zone; To highlight the engineering parameters that should be obtained to facilitate design for the passage through water-bearing fracture zones.The study has been carried out in the following five stages: A. Compilation of the relevant data for deformation zone NE-1; B. Problem identification and proposal of technical solutions; C. Identification of hazards to be involved in the tunnel excavation; D. Recommendations and conclusions for further investigations; E. Documentation of the results in a final report. The analyses will be expressed in statistical/probabilistic terms where appropriate. In order to specify the precondition that will be valid for this study, a descriptive model of the water-bearing fracture zone is established

Study of tunnelling through water-bearing fracture zones. Baseline study on technical issues with NE-1 as reference

Energy Technology Data Exchange (ETDEWEB)

Yanting Chang; Swindell, Robert; Bogdanoff, Ingvar; Lindstroem, Beatrice; Termen, Jens [WSP Sweden, Stockholm (Sweden) ; Starsec, Peter [SGI, Linkoeping (Sweden)

2005-04-01

The Swedish Nuclear Fuel and Waste Management Co (SKB) is responsible for the management of Sweden's nuclear waste. SKB is investigating various designs for the construction of an underground deep repository for spent nuclear fuel at 500-600 m depths. For the construction of an access tunnel for such a deep repository, the possibility of encountering a water-bearing fracture zone cannot be discounted. Such a zone named NE-1 (deformation zone in accordance to SKB's terminology) was encountered during the construction of the Aespoe Hard Rock Laboratory (HRL) and difficulties with large water inflows were reported. With the aim to assess the feasibility of different technical solutions, SKB commissioned a baseline study into the passage of an access tunnel through a water-bearing fracture zone at three different depths (200 m, 400 m and 600 m). The objectives of this baseline study are to: Increase the knowledge of possible technical solutions for tunnelling through water-bearing fractures zones with the characteristics of the brittle deformation zone NE-1 at different depths, namely 200, 400 and 600 metres; Form a reference document to assist the engineering design and construction work for the passage through such a water-bearing fracture zone; To highlight the engineering parameters that should be obtained to facilitate design for the passage through water-bearing fracture zones.The study has been carried out in the following five stages: A. Compilation of the relevant data for deformation zone NE-1; B. Problem identification and proposal of technical solutions; C. Identification of hazards to be involved in the tunnel excavation; D. Recommendations and conclusions for further investigations; E. Documentation of the results in a final report. The analyses will be expressed in statistical/probabilistic terms where appropriate. In order to specify the precondition that will be valid for this study, a descriptive model of the water-bearing fracture zone is

How the NDA Provides Transparency and Visibility of the Technical Deliverability of the R and D Programme - 13303

International Nuclear Information System (INIS)

Seed, Ian; James, Paula; Brownridge, Melanie; McMinn, Mervin

2013-01-01

The Nuclear Decommissioning Authority (NDA) was created under the UK Energy Act 2004 to ensure the UK historic civil public sector nuclear legacy sites are decommissioned safely, securely, cost effectively and in ways that protect the environment. The delivery will involve carrying out many unique projects within a high hazard environment requiring the very highest standards in safety, security and environmental management. Unique problems require unique solutions and there is a substantial amount of research and development required for each project. The NDA's R and D strategic objective is to ensure that delivery of the NDA's mission is technically underpinned by sufficient and appropriate research and development. This drives a requirement to provide transparency and visibility of the technical deliverability of the programme through the technical baseline and accompanying research and development requirements. The NDA need to have confidence in the technical deliverability of the Site License Companies (SLCs) plans, provide overall visibility of R and D across the NDA Estate and ensure that appropriate R and D is being carried out in a timely manner. They need to identify where coordinated R and D programmes may be advantageous as a result of common needs, risks and opportunities and ensure key R and D needs across NDA are identified, prioritised and work programmes are costed and scheduled in the Lifetime Plans for individual sites and SLCs. Evidence of the Site License Company's approach and their corresponding technical underpinning programmes is achieved through submission of a number of outputs collectively known as TBuRDs (Technical Baseline and Underpinning Research and Development Requirements). This paper is a summary of the information generated by an independent review of those TBuRDs. It highlights some of the key messages, synergies and common R and D activities across the estate. It demonstrates the value of a consistent approach to collecting R

Technical and Management Information System (TMIS)

Science.gov (United States)

Rau, Timothy R.

1987-01-01

The TMIS goals developed to support the Space Station Program (SSP) mission requirements are outlined. The TMIS will provide common capabilities to all SSP centers and facilitate the flow of technical and management information throughout the program as well as SSP decision-making processes. A summary is presented of the various TMIS phases.

78 FR 65695 - 30-Day Notice of Proposed Information Collection: Technical Processing Requirements for...

Science.gov (United States)

2013-11-01

... Information Collection: Technical Processing Requirements for Multifamily Project Mortgage Insurance AGENCY: Office of the Chief Information Officer, HUD. ACTION: Correction, notice. SUMMARY: On October 25, 2013 at... Collection Title of Information Collection: Technical Processing Requirements for Multifamily Project...

A comparison of baseline methodologies for 'Reducing Emissions from Deforestation and Degradation'

Directory of Open Access Journals (Sweden)

Kok Kasper

2009-07-01

Full Text Available Abstract Background A mechanism for emission reductions from deforestation and degradation (REDD is very likely to be included in a future climate agreement. The choice of REDD baseline methodologies will crucially influence the environmental and economic effectiveness of the climate regime. We compare three different historical baseline methods and one innovative dynamic model baseline approach to appraise their applicability under a future REDD policy framework using a weighted multi-criteria analysis. Results The results show that each baseline method has its specific strengths and weaknesses. Although the dynamic model allows for the best environmental and for comparatively good economic performance, its high demand for data and technical capacity limit the current applicability in many developing countries. Conclusion The adoption of a multi-tier approach will allow countries to select the baseline method best suiting their specific capabilities and data availability while simultaneously ensuring scientific transparency, environmental effectiveness and broad political support.

Nuclear Energy Innovation Workshops. Executive Summary

Energy Technology Data Exchange (ETDEWEB)

Allen, Todd [Idaho National Lab. (INL), Idaho Falls, ID (United States); Jackson, John [Idaho National Lab. (INL), Idaho Falls, ID (United States); Hildebrandt, Phil [Idaho National Lab. (INL), Idaho Falls, ID (United States); Baker, Suzy [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2015-06-01

The nuclear energy innovation workshops were organized and conducted by INL on March 2-4, 2015 at the five NUC universities and Boise State University. The output from these workshops is summarized with particular attention to final summaries that were provided by technical leads at each of the workshops. The current revision includes 3-4 punctuation corrections and a correction of the month of release from May to June.

Hepatitis C treatment response kinetics and impact of baseline predictors

DEFF Research Database (Denmark)

Lindh, M; Arnholm, B; Eilard, A

2011-01-01

Summary. The optimal duration of treatment for hepatitis C virus (HCV) infections is highly variable but critical for achieving cure (sustained virological response, SVR). We prospectively investigated the impact of age, fibrosis, baseline viraemia and genotype on the early viral kinetics...... above 400 000 IU/mL were strongly associated with slower second phase declines of HCV RNA. Genotype 2/3 infections responded more rapidly than genotype 1, reaching week 4 negativity (RVR) in 59%vs 22%. We conclude that baseline response predictors such as age, fibrosis and viral load were well reflected...... by the early viral kinetics as assessed by repeated HCV RNA quantifications. The kinetic patterns and the high relapse rate in genotype 2/3 patients without RVR suggest that this group might benefit from treatment durations longer than 24 weeks....

National greenhouse gas emissions baseline scenarios. Learning from experiences in developing countries

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-04-15

This report reviews national approaches to preparing baseline scenarios of greenhouse-gas (GHG) emissions. It does so by describing and comparing in non-technical language existing practices and choices made by ten developing countries - Brazil, China, Ethiopia, India, Indonesia, Kenya, Mexico, South Africa, Thailand and Vietnam. The review focuses on a number of key elements, including model choices, transparency considerations, choices about underlying assumptions and challenges associated with data management. The aim is to improve overall understanding of baseline scenarios and facilitate their use for policy-making in developing countries more broadly. The findings are based on the results of a collaborative project involving a number of activities undertaken by the Danish Energy Agency, the Organisation for Economic Co-operation and Development (OECD) and the UNEP Risoe Centre (URC), including a series of workshops on the subject. The ten contributing countries account for approximately 40% of current global GHG emissions - a share that is expected to increase in the future. The breakdown of emissions by sector varies widely among these countries. In some countries, the energy sector is the leading source of emissions; for others, the land-use sector and/or agricultural sector dominate emissions. The report underscores some common technical and financial capacity gaps faced by developing countries when preparing baseline scenarios. It does not endeavour to propose guidelines for preparing baseline scenarios. Rather, it is hoped that the report will inform any future attempts at preparing such kind of guidelines. (Author)

Compendium of Executive Summaries from the Maglev System Concept Definition. Final Reports

National Research Council Canada - National Science Library

1993-01-01

...) studies awarded under the National Maglev Initiative. These summaries present the technical feasibility, performance, capital, operating and maintenance costs for a maglev system that would be available by the year 2000...

Performance evaluation of the technical capabilities of DOE sites for disposal of mixed low-level waste. Volume 1: Executive summary

International Nuclear Information System (INIS)

1996-03-01

A team of analysts designed and conducted a performance evaluation (PE) to estimate the technical capabilities of fifteen Department of Energy sites for disposal of mixed low-level waste (i.e., waste that contains both low-level radioactive materials and hazardous constituents). Volume 1 summarizes the process for selecting the fifteen sites, the methodology used in the evaluation, and the conclusions derived from the evaluation. Volume 1 is an executive summary both of the PE methodology and of the results obtained from the PEs. While this volume briefly reviews the scope and method of analyses, its main objective is to emphasize the important insights and conclusions derived from the conduct of the PEs. Volume 2 provides details about the site-selection process, the performance-evaluation methodology, and the overall results of the analysis. Volume 3 contains detailed evaluations of the fifteen sites and discussions of the results for each site

Final report of the UMTRA independent technical review of TAC audit programs

International Nuclear Information System (INIS)

1994-10-01

This report details the findings of an Independent Technical Review (ITR) of practices and procedures for the Uranium Mill Tailings Remedial Action (UMTRA) Project audit program. The audit program is conducted by Jacobs Engineering Group Inc., the Technical Assistance Contractor (TAC) for the UMTRA Project. The purpose of the ITR was to ensure that the TAC audit program is effective and is conducted efficiently. The ITR was conducted from May 16-20, 1994. A review team observed audit practices in the field, reviewed the TAC audit program's documentation, and discussed the program with TAC staff and management. The format of this report has been developed around EPA guidelines; they comprise most of the major section headings. Each section begins by identifying the criteria that the TAC program is measured against, then describing the approach used by the ITR team to measure each TAC audit program against the criteria. An assessment of each type of audit is then summarized for each component in the following order: Radiological audit summary; Health and safety audit summary; Environmental audit summary; Quality assurance audit summary

Summary of the ITER final design report. July 2001

International Nuclear Information System (INIS)

2001-01-01

This document is a summary of the ITER final design report foreseen during the current, Engineering Design Activities (EDA), phase of the ITER project. The report presents the results of collaborative design and supporting technical work undertaken by the ITER Joint Central team (JCT) and the Home Teams (HT) of the parties to the agreement on co-operation in the Engineering Design Activities for ITER (the ITER EDA Agreement). This report marks the achievement of the full technical scope of activities indicated in the ITER EDA Agreement, with a final design which meets the programmatic objective defined in the Agreement and satisfies detailed scientific, technical and costing objectives set by ITER Council in 1998

CALS Baseline Architecture Analysis of Weapons System. Technical Information: Army, Draft. Volume 8

Science.gov (United States)

1989-09-01

This effort was performed to provide a common framework for analysis and planning of CALS initiatives across the military services, leading eventually to the development of a common DoD-wide architecture for CALS. This study addresses Army technical ...

Summaries of studies carried out in the NKS/BOK-2 project. Technical report

International Nuclear Information System (INIS)

Palsson, S.E.

2002-12-01

Summaries of studies carried out in the NKSBOK-2 project, Radiological and Environmental Consequences. The structure of the project as such is described in NKS-64, Radiological and Environmental Consequences - Final Report of the Nordic Nuclear Safety Research Project BOK-2. That report also includes compilations based on the summaries presented in this report. The project was carried out 1998-2001 with participants from all the Nordic countries. Representatives from the Baltic States were also invited to some of the meetings and seminars. The project consisted of work on terrestrial and marine radioecology and had a broad scope in order to enable participation of research groups with various fields of interest. The topics included improving assessment of old and recent fallout, use of radionuclides as tracers in Nordic marine areas, improving assessment of internal doses and use of mass spectrometry in radioecology. This report is a compilation of summaries from each research group, 32 papers in all, and gives references to papers published in scientific journals. Some of the studies have been described previously, at least to some degree, in NKS-70, Proceedings of the 8 th Nordic Seminar on Radioecology, 25-28 February 2001, Rovaniemi, Finland. (au)

Summaries of FY 1980 research in the nuclear sciences

International Nuclear Information System (INIS)

1980-06-01

A compilation and index of the projects funded in fiscal year 1980 by the DOE Division of Nuclear Sciences/Office of Basic Energy Sciences is provided. These summaries constitute the basic document by which the DOE nuclear sciences program can be made known in some technical detail to interested persons

Summaries of FY 1980 research in the nuclear sciences

Energy Technology Data Exchange (ETDEWEB)

1980-06-01

A compilation and index of the projects funded in fiscal year 1980 by the DOE Division of Nuclear Sciences/Office of Basic Energy Sciences is provided. These summaries constitute the basic document by which the DOE nuclear sciences program can be made known in some technical detail to interested persons. (RWR)

Executive Summary

International Nuclear Information System (INIS)

2014-01-01

Each session of the workshop consisted of a number of presentations followed by a panel discussion moderated by the session Chairs. A summary of each session and subsequent discussion that ensued are provided. Session 1: National approaches for long term interim storage facilities. Seven papers were presented during this session by representatives of research institutes in USA (EPRI) and in Norway (IFE), governmental authorities for the nuclear industry in Finland (STUK) and Slovak Republic (UJD), technical support organizations in Germany (GRS) and France (IRSN) and the public company in charge of waste management in Spain (ENRESA). The papers discussed the national policy, the regulatory framework and the current situation for storage of SF and HLW in various European countries (Germany, Spain, Finland, Norway and Slovak Republic). The main activities the EPRI is undertaking to establish the technical bases for extended (long-term) storage and the IRSN's definition of the safety principles and objectives for new storage facilities regarding long-term storage are also discussed. Session 2: Safety requirements, regulatory framework and implementation issues. Eleven papers were presented during this session by representatives from international groups (the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency (NEA)), representatives of regulatory bodies from the United States (Nuclear Regulatory Commission) and Germany (Bundesamt fuer Strahlenschutz (BfS)), German Federal Institute for Materials Research and Testing (BAM), operators from the United Kingdom (Sellafield Limited, UK) and France (EDF), vendors (AREVA), and representatives of TSOs in Germany (TUV and Oko-Institut). Session 3: Technical issues and operational experience, needs for R and D. This session was chaired by Karl Wasinger (AREVA, Germany) and Fumihisa Nagase (JAEA, Japan). Ten papers were presented during this session by representatives of research institutes of Japan (CRIEPI

Integrating risk management into the baselining process

International Nuclear Information System (INIS)

Jennett, N.; Tonkinson, A.

1994-01-01

These processes work together in building the project (comprised of the technical, schedule, and cost baselines) against which performance is measured and changes to the scope, schedule and cost of a project are managed and controlled. Risk analysis is often performed as the final element of the scheduling or estimating processes, a precursor to establishing cost and schedule contingency. However, best business practices dictate that information that may be crucial to the success of a project be analyzed and incorporated into project planning as soon as it is available and usable. The purpose or risk management is not to eliminate risk. Neither is it intended to suggest wholesale re-estimating and re-scheduling of a project. Rather, the intent is to make provisions to reduce and control the schedule and/or cost ramifications of risk by anticipating events and conditions that cannot be reliably planned for and which have the potential to negatively impact accomplishment of the technical objectives and requirements of the project

75 FR 33761 - Notice of Proposed Change to Section IV of the Virginia State Technical Guide

Science.gov (United States)

2010-06-15

... revisions made after enactment of the law to NRCS State technical guides used to carry out highly erodible... Section IV of the Virginia State Technical Guide AGENCY: Natural Resources Conservation Service (NRCS), U... NRCS State Technical Guide for review and comment. SUMMARY: It has been determined by the NRCS State...

75 FR 34974 - Notice of Proposed Change to Section IV of the Virginia State Technical Guide

Science.gov (United States)

2010-06-21

... revisions made after enactment of the law to NRCS State technical guides used to carry out highly erodible... Section IV of the Virginia State Technical Guide AGENCY: Natural Resources Conservation Service (NRCS), U... NRCS State Technical Guide for review and comment. SUMMARY: It has been determined by the NRCS State...

75 FR 62759 - Notice of Proposed Change to Section IV of the Virginia State Technical Guide

Science.gov (United States)

2010-10-13

... revisions made after enactment of the law to NRCS State technical guides used to carry out highly erodible... Section IV of the Virginia State Technical Guide AGENCY: Natural Resources Conservation Service (NRCS), U... NRCS State Technical Guide for review and comment. SUMMARY: It has been determined by the NRCS State...

78 FR 12042 - Electric Grid Integration Technical Workshops

Science.gov (United States)

2013-02-21

... DEPARTMENT OF ENERGY Electric Grid Integration Technical Workshops AGENCY: Grid Tech Team, U.S. Department of Energy. ACTION: Notice of availability; request for comments. SUMMARY: Notice is hereby given that two documents are publicly available and the Department of Energy is requesting public comments...

77 FR 8095 - Technical Corrections to Commission Regulations

Science.gov (United States)

2012-02-14

... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission 18 CFR Part 2 [Docket No. RM11-30-000; Order No. 756] Technical Corrections to Commission Regulations Issued February 8, 2012. AGENCY: Federal Energy Regulatory Commission, DOE. ACTION: Final rule: correcting amendment. SUMMARY: This document adds...

76 FR 16235 - Corporate Credit Unions, Technical Corrections

Science.gov (United States)

2011-03-23

... inadvertently included particular investments that did not--when subject to the other credit risk and asset... NATIONAL CREDIT UNION ADMINISTRATION 12 CFR Part 707 RIN 3133-AD58 Corporate Credit Unions, Technical Corrections AGENCY: National Credit Union Administration (NCUA). ACTION: Final rule. SUMMARY: In...

Text Structuration Leading to an Automatic Summary System: RAFI.

Science.gov (United States)

Lehman, Abderrafih

1999-01-01

Describes the design and construction of Resume Automatique a Fragments Indicateurs (RAFI), a system of automatic text summary which sums up scientific and technical texts. The RAFI system transforms a long source text into several versions of more condensed texts, using discourse analysis, to make searching easier; it could be adapted to the…

Analysis of Waste Isolation Pilot Plant Samples: Integrated Summary Report

Energy Technology Data Exchange (ETDEWEB)

Britt, Phillip F [ORNL

2015-03-01

Analysis of Waste Isolation Pilot Plant Samples: Integrated Summary Report. Summaries of conclusions, analytical processes, and analytical results. Analysis of samples taken from the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico in support of the WIPP Technical Assessment Team (TAT) activities to determine to the extent feasible the mechanisms and chemical reactions that may have resulted in the breach of at least one waste drum and release of waste material in WIPP Panel 7 Room 7 on February 14, 2014. This report integrates and summarizes the results contained in three separate reports, described below, and draws conclusions based on those results. Chemical and Radiochemical Analyses of WIPP Samples R-15 C5 SWB and R16 C-4 Lip; PNNL-24003, Pacific Northwest National Laboratory, December 2014 Analysis of Waste Isolation Pilot Plant (WIPP) Underground and MgO Samples by the Savannah River National Laboratory (SRNL); SRNL-STI-2014-00617; Savannah River National Laboratory, December 2014 Report for WIPP UG Sample #3, R15C5 (9/3/14); LLNL-TR-667015; Lawrence Livermore National Laboratory, January 2015 This report is also contained in the Waste Isolation Pilot Plant Technical Assessment Team Report; SRNL-RP-2015-01198; Savannah River National Laboratory, March 17, 2015, as Appendix C: Analysis Integrated Summary Report.

Department of Defense Base Structure Report (A Summary of DOD's Real Property Inventory), Fiscal year 2005 Baseline

National Research Council Canada - National Science Library

2005-01-01

The Base Structure Report represents a consolidated summary of the Services native real property inventories to provide an overall look at the physical infrastructure that makes up the Department of Defense...

McKenzie River Subbasin Assessment, Technical Report 2000.

Energy Technology Data Exchange (ETDEWEB)

Alsea Geospatial, Inc.

2000-02-01

This document details the findings of the McKenzie River Subbasin Assessment team. The goal of the subbasin assessment is to provide an ecological assessment of the McKenzie River Floodplain, identification of conservation and restoration opportunities, and discussion of the influence of some upstream actions and processes. This Technical Report can be viewed in conjunction with the McKenzie River Subbasin Summary or as a stand-alone document. The purpose of the technical report is to detail the methodology and findings of the consulting team that the observations and recommendations in the summary document are based on. This part, Part I, provides an introduction to the subbasin and a general overview. Part II details the specific findings of the science team. Part III provides an explanation and examples of how to use the data that has been developed through this assessment to aid in prioritizing restoration activities. Part III also includes the literature cited and appendices.

Summary of Research 1998, Department of Physics

OpenAIRE

Faculty of the Department of Physics, Naval Postgraduate School

1998-01-01

The views expressed in this report are those of the authors and do not reflect the official policy or position of the Department of Defense or the U.S. Government. This report contains summaries of research projects in the Department of Physics. A list of recent publications is also included which consists of conference presentations and publications, books, contributions to books, published journal papers, technical reports, and thesis abstracts.

Summary record of the 33. Meeting of NEA committee on reactor physics

International Nuclear Information System (INIS)

Martinelli, R.

1991-01-01

This paper is the summary record of the thirty-third meeting (Technical session) of the Nuclear Energy Agency Committee on Reactor Physics. A complete list of all the papers presented at this meeting is given in annex 4

78 FR 1823 - Cable Television Technical and Operational Requirements

Science.gov (United States)

2013-01-09

... FEDERAL COMMUNICATIONS COMMISSION 47 CFR Part 79 [MB Docket No. 12-217; DA 12-2081] Cable Television Technical and Operational Requirements AGENCY: Federal Communications Commission. ACTION: Proposed rule; extension of reply comment period. SUMMARY: In this document, the Commission extends the deadline...

Technical Working Group on Career and Technical Education Meeting. Meeting Summary (Washington, DC, September 22, 2017)

Science.gov (United States)

Ahn, Judie

2017-01-01

On September 22, 2017, the National Center for Special Education Research (NCSER) and the National Center for Education Research (NCER) at the Institute of Education Sciences (IES) convened a group of experts in policy, practice, and research related to Career and Technical Education (CTE). The goal of the meeting was to seek input from…

Mechanical Engineering Department technical abstracts

International Nuclear Information System (INIS)

1984-01-01

The Mechanical Engineering Department publishes abstracts twice a year to inform readers of the broad range of technical activities in the Department, and to promote an exchange of ideas. Details of the work covered by an abstract may be obtained by contacting the author(s). General information about the current role and activities of each of the Department's seven divisions precedes the technical abstracts. Further information about a division's work may be obtained from the division leader, whose name is given at the end of each divisional summary. The Department's seven divisions are as follows: Nuclear Test Engineering Division, Nuclear Explosives Engineering Division, Weapons Engineering Division, Energy Systems Engineering Division, Engineering Sciences Division, Magnetic Fusion Engineering Division and Materials Fabrication Division

TECHNICAL COORDINATION

CERN Multimedia

Austin Ball

Summary of progress since last CMS week. Ten years of construction work have been completed. CMS is closed, in very close to the ideal low luminosity configuration, and performed well in the first tests with LHC beam. Behind this encouraging news is the story of a summer of intense commitment by many teams (from the collaboration and 3 CERN departments) working together, against the clock and despite many minor setbacks, to ensure that the experiment was ready to play a leading role in the excitement of September 10. Following beampipe bakeout and refill with pure neon, a magnificent effort by the ECAL group and the pt 5 technical crew made it possible to install and commission all 4 ECAL endcap Dees before the end of August. In the shadow of this activity, the barrel and forward pixel trackers and part of the beam monitoring were installed within the vac tank. The pt 5 technical teams then succeeded in safely removing the 20t installation tables and their support blocks from beneath the already installed ...

Distributed Mission Operations Within-Simulator Training Effectiveness Baseline Study. Volume 5. Using the Pathfinder Methodology to Assess Pilot Knowledge Structure Changes

National Research Council Canada - National Science Library

Schreiber, Brian T; DiSalvo, Pam; Stock, William A; Bennett, Jr., Winston

2006-01-01

...) Within Simulator Training Effectiveness Baseline Study as described in Volume I, Summary Report, of AFRL-HE-AZ-TR-2006-0015, the current work examined pilots who participated in a Pathfinder data...

Executive summary

International Nuclear Information System (INIS)

2002-01-01

On 18 May 2001, the Finnish Parliament ratified the Decision in Principle on the final disposal facility for spent nuclear fuel at Olkiluoto, within the municipality of Eurajoki. The Municipality Council and the government has made positive decisions earlier, at the end of 2000, and in compliance with the Nuclear Energy Act, Parliament's ratification was then required. The decision is valid for the spent fuel generated by the existing Finnish nuclear power plants and means that the construction of the final disposal facility is considered to be in line with the overall good of society. Earlier steps included, amongst others, the approval of the technical project by the Safety Authority. Future steps include construction of an underground rock characterisation facility, ONKALO (2003-2004), and application for separate construction and operating licences for the final disposal facility (from about 2010). How did this political and societal decision come about? The FSC Workshop provided the opportunity to present the history leading up to the Decision in Principle (DiP), and to examine future perspectives with an emphasis on stakeholder involvement. This Executive Summary gives an overview of the presentations and discussions that took place at the workshop. It presents, for the most part, a factual account of the individual presentations and of the discussions that took place. It relies importantly on the notes that were taken at the meeting. Most materials are elaborated upon in a fuller way in the texts that the various speakers and session moderators contributed for these proceedings. The structure of the Executive Summary follows the structure of the workshop itself. Complementary to this Summary and also provided with this document, is a NEA Secretariat's perspective aiming to place the results of all discussions, feedback and site visit into an international perspective. (authors)

Technical Cooperation Report for 2014. Report by the Director General. Suppl

International Nuclear Information System (INIS)

2015-06-01

This document contains financial and statistical data that supplement the Technical Cooperation (TC) Report for 2014. The information is grouped under three headings, Resources and Contributions, Actuals and Implementation Summaries, and Non-financial Indicators

Yucca Mountain Climate Technical Support Representative

International Nuclear Information System (INIS)

Sharpe, Saxon E

2007-01-01

The primary objective of Project Activity ORD-FY04-012, 'Yucca Mountain Climate Technical Support Representative', was to provide the Office of Civilian Radioactive Waste Management (OCRWM) with expertise on past, present, and future climate scenarios and to support the technical elements of the Yucca Mountain Project (YMP) climate program. The Climate Technical Support Representative was to explain, defend, and interpret the YMP climate program to the various audiences during Site Recommendation and License Application. This technical support representative was to support DOE management in the preparation and review of documents, and to participate in comment response for the Final Environmental Impact Statement, the Site Recommendation Hearings, the NRC Sufficiency Comments, and other forums as designated by DOE management. Because the activity was terminated 12 months early and experience a 27% reduction in budget, it was not possible to complete all components of the tasks as originally envisioned. Activities not completed include the qualification of climate datasets and the production of a qualified technical report. The following final report is an unqualified summary of the activities that were completed given the reduced time and funding

Logistics Operations Management Center: Maintenance Support Baseline (LOMC-MSB)

Science.gov (United States)

Kurrus, R.; Stump, F.

1995-01-01

The Logistics Operations Management Center Maintenance Support Baseline is defined. A historical record of systems, applied to and deleted from, designs in support of future management and/or technical analysis is provided. All Flight elements, Ground Support Equipment, Facility Systems and Equipment and Test Support Equipment for which LOMC has responsibilities at Kennedy Space Center and other locations are listed. International Space Station Alpha Program documentation is supplemented. The responsibility of the Space Station Launch Site Support Office is established.

76 FR 22091 - Biomass Research and Development Technical Advisory Committee

Science.gov (United States)

2011-04-20

... DEPARTMENT OF ENERGY Energy Efficiency and Renewable Energy Biomass Research and Development Technical Advisory Committee AGENCY: Energy Efficiency and Renewable Energy, Department of Energy. ACTION: Notice of Open Meeting. SUMMARY: This notice announces an open meeting of the Biomass Research and...

Minutes of the IFMIF technical meetings, May 17-20, 2005, Tokyo, Japan

International Nuclear Information System (INIS)

Ida, Mizuho; Nakamura, Hiroo; Yutani, Toshiaki; Maebara, Sunao; Umetsu, Tomotake; Sugimoto, Masayoshi

2005-08-01

The International Fusion Materials Irradiation Facility (IFMIF) Technical Meetings were held on May 17-20, 2005 at Japan Atomic Energy Research Institute (JAERI) Tokyo. The main objectives were 1) to review technical status of the subsystems; accelerator, target and test facilities, 2) to technically discuss interface issues between target and test facilities, 3) to review results of peer-reviews performed in the EU and Japan, 4) to harmonize design/experimental activities among the subsystems, 5) to review and discuss the Engineering Validation and Engineering Design Activity (EVEDA) tasks, and 6) to make a report of 1) - 5) to the IFMIF Executive Subcommittee. This report presents a brief summary of the Target Technical, Meeting, Test Facilities Technical Meeting, Target/Test Facilities Interface Meeting, Accelerator Technical Meeting and the Technical Integration Meeting. (author)

RE/SPEC Inc. technical support to the Repository Technology Program

International Nuclear Information System (INIS)

Wagner, R.A.

1992-06-01

This report presents a summary of all RE/SPEC Inc. technical support activities to the Repository Technology Program (RTP) from September 1, 1988, through June 30, 1992. The RE/SPEC Inc. activities are grouped into the following categories: project management, project quality assurance (QA), performance assessment (PA), support of the Office of Civilian Radioactive Waste Management (OCRWM) through technical reviews and general assistance, participation in the Department of Energy (DOE) International Program, and code evaluation and documentation

Technical activities, 1990: Surface Science Division

International Nuclear Information System (INIS)

Powell, C.J.

1991-05-01

The report summarizes technical activities and accomplishments of the NIST Surface Science Division during Fiscal Year 1990. Overviews are presented of the Division and of its three constituent groups: Surface Dynamical Processes, Thin Films and Interfaces, and Surface Spectroscopies and Standards. These overviews are followed by reports of selected technical accomplishments during the year. A summary is given of Division outputs and interactions that includes lists of publications, talks, committee assignments, seminars (including both Division seminars and Interface Science seminars arranged through the Division), conferences organized, and a standard reference material certified. Finally, lists are given of Division staff and of guest scientists who have worked in the Division during the past year

Nuclear thermal rocket clustering: 1, A summary of previous work and relevant issues

International Nuclear Information System (INIS)

Buksa, J.J.; Houts, M.G.

1991-01-01

A general review of the technical merits of nuclear thermal rocket clustering is presented. A summary of previous analyses performed during the Rover program is presented and used to assess clustering in the context of projected Space Exploration Initiative missions. A number of technical issues are discussed including cluster reliability, engine-out operation, neutronic coupling, shutdown core power generation, shutdown reactivity requirements, reactor kinetics, and radiation shielding. 7 refs., 3 figs., 2 tabs

Summary of the workshop: towards 4π physics

International Nuclear Information System (INIS)

Ngo, C.

1985-12-01

This summary is not intended to give an extensive review of all what has been said during the three days about technics, experiments and theories. It will be rather a brief and simple overview of what I felt during the meeting while listening to the different talks, discussions and participating to the round tables which were also a very important part of the workshop and contributed a lot to its success. This summary will be organized as follows: in a first part I shall briefly describe the basic problems that one is faced with ''exclusive'' measurements. Finally, we shall briefly review some of the theoretical problems existing at intermediate bombarding energies since any experiment would initially rely heavily on theoretical considerations

40 CFR 74.20 - Data for baseline and alternative baseline.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 16 2010-07-01 2010-07-01 false Data for baseline and alternative baseline. 74.20 Section 74.20 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR... baseline and alternative baseline. (a) Acceptable data. (1) The designated representative of a combustion...

Quantification of baseline pupillary response and task-evoked pupillary response during constant and incremental task load.

Science.gov (United States)

Mosaly, Prithima R; Mazur, Lukasz M; Marks, Lawrence B

2017-10-01

The methods employed to quantify the baseline pupil size and task-evoked pupillary response (TEPR) may affect the overall study results. To test this hypothesis, the objective of this study was to assess variability in baseline pupil size and TEPR during two basic working memory tasks: constant load of 3-letters memorisation-recall (10 trials), and incremental load memorisation-recall (two trials of each load level), using two commonly used methods (1) change from trail/load specific baseline, (2) change from constant baseline. Results indicated that there was a significant shift in baseline between the trails for constant load, and between the load levels for incremental load. The TEPR was independent of shifts in baseline using method 1 only for constant load, and method 2 only for higher levels of incremental load condition. These important findings suggest that the assessment of both the baseline and methods to quantify TEPR are critical in ergonomics application, especially in studies with small number of trials per subject per condition. Practitioner Summary: Quantification of TEPR can be affected by shifts in baseline pupil size that are most likely affected by non-cognitive factors when other external factors are kept constant. Therefore, quantification methods employed to compute both baseline and TEPR are critical in understanding the information processing of humans in practical ergonomics settings.

World Energy Data System (WENDS). Volume XI. Nuclear fission program summaries

International Nuclear Information System (INIS)

1979-06-01

Brief management and technical summaries of nuclear fission power programs are presented for nineteen countries. The programs include the following: fuel supply, resource recovery, enrichment, fuel fabrication, light water reactors, heavy water reactors, gas cooled reactors, breeder reactors, research and test reactors, spent fuel processing, waste management, and safety and environment

Biological and chemical technologies research. FY 1995 annual summary report

Energy Technology Data Exchange (ETDEWEB)

None

1996-03-01

The annual summary report presents the fiscal year (FY) 1995 research activities and accomplishments for the United States Department of Energy (DOE) Biological and Chemical Technologies Research (BCTR) Program. This BCTR program resides within the Office of Industrial Technologies (OIT) of the Office of Energy Efficiency and Renewable Energy (EE). The annual summary report for 1995 (ASR 95) contains the following: program description (including BCTR program mission statement, historical background, relevance, goals and objectives); program structure and organization, selected technical and programmatic highlights for 1995; detailed descriptions of individual projects; a listing of program output, including a bibliography of published work; patents; and awards arising from work supported by the BCTR.

Plutonium focus area. Technology summary

International Nuclear Information System (INIS)

1997-09-01

The Assistant Secretary for the Office of Environmental Management (EM) at the U.S. Department of Energy (DOE) chartered the Plutonium Focus Area (PFA) in October 1995. The PFA open-quotes...provides for peer and technical reviews of research and development in plutonium stabilization activities...close quotes In addition, the PFA identifies and develops relevant research and technology. The purpose of this document is to focus attention on the requirements used to develop research and technology for stabilization, storage, and preparation for disposition of nuclear materials. The PFA Technology Summary presents the approach the PFA uses to identify, recommend, and review research. It lists research requirements, research being conducted, and gaps where research is needed. It also summarizes research performed by the PFA in the traditional research summary format. This document encourages researchers and commercial enterprises to do business with PFA by submitting research proposals or open-quotes white papers.close quotes In addition, it suggests ways to increase the likelihood that PFA will recommend proposed research to the Nuclear Materials Stabilization Task Group (NMSTG) of DOE

World Energy Data System (WENDS). Volume XI. Nuclear fission program summaries

Energy Technology Data Exchange (ETDEWEB)

1979-06-01

Brief management and technical summaries of nuclear fission power programs are presented for nineteen countries. The programs include the following: fuel supply, resource recovery, enrichment, fuel fabrication, light water reactors, heavy water reactors, gas cooled reactors, breeder reactors, research and test reactors, spent fuel processing, waste management, and safety and environment. (JWR)

Utilization of a technical review group during a BWR owners group technical specification improvement study

International Nuclear Information System (INIS)

Hansell, H.F.; Moyer, D.P.

1986-01-01

A BWR Owners' Group Technical Specification Improvement (TSI) Committee was formed in late 1983. A primary goal of this Committee was to encourage the development of a probabilistic methodology for technical specification improvements which could be readily applied by utilities. The TSI Committee elected to hire a Contractor to develop and demonstrate a method. After the Contractor was selected and has started work, the committee decided to establish a Technical Review Group (TRG) to efficiently and effectively review the Contractor's analyses. The TRG met frequently with the Contractor as the analyses were being performed. These meetings were held at the Contractor's facility in order to allow direct contact between reviewers and individuals performing the work. The TRG was also involved with all major interactions with the NRC. The significance and merit of using a peer review group in this manner is the theme of this paper. In order to present a discussion of the significance and merit of the TRG, the activities are described. The summary of the analytical approach is provided to more full understand the TRG activities

Preliminary data summary for the hospitals point-source category

International Nuclear Information System (INIS)

Strassler, E.; Hund, F.H.

1989-09-01

The summaries were prepared in order to allow EPA to respond to the mandate of Section 304(m) of the Clean Water Act. Summaries for categories already subject to rulemaking were developed for comparison purposes, and contain only the minimum amount of data needed to provide some perspective on the relative magnitude of the pollution problems created across the categories. The document summarizes the most current information available regarding the discharge of wastewater and solid wastes containing priority and hazardous non-priority pollutants by hospitals. The document provides a technical basis for determining whether additional national regulations should be developed pursuant to the Clean Water Act (CWA), and makes available preliminary information regarding the discharge of priority and hazardous non-priority pollutants by the hospital industry

The planning of decommissioning activities within nuclear facilities - Generating a Baseline Decommissioning Plan

International Nuclear Information System (INIS)

Meek, N.C.; Ingram, S.; Page, J.

2003-01-01

BNFL Environmental Services has developed planning tools to meet the emerging need for nuclear liabilities management and decommissioning engineering both in the UK and globally. It can provide a comprehensive baseline planning service primarily aimed at nuclear power stations and nuclear plant. The paper develops the following issues: Decommissioning planning; The baseline decommissioning plan;The process; Work package; Compiling the information; Deliverables summary; Customer Benefits; - Planning tool for nuclear liability life-cycle management; - Robust and reliable plans based upon 'real' experience; - Advanced financial planning; - Ascertaining risk; - Strategy and business planning. The following Deliverables are mentioned:1. Site Work Breakdown Structure; 2. Development of site implementation strategy from the high level decommissioning strategy; 3. An end point definition for the site; 4. Buildings, operational systems and plant surveys; 5. A schedule of condition for the site; 6. Development of technical approach for decommissioning for each work package; 7. Cost estimate to WBS level 5 for each work package; 8. Estimate of decommissioning waste arisings for each work package; 9. Preparation of complete decommissioning programme in planning software to suit client; 10. Risk modelling of work package and overall project levels; 11. Roll up of costs into an overall cost model; 12. Cash flow, waste profiling and resource profiling against the decommissioning programme; 13. Preparation and issue of Final Report. Finally The BDP process is represented by a flowchart listing the following stages: [Power Station project assigned] → [Review project and conduct Characterisation review of power station] → [Identify work packages] → [Set up WBS to level 3] → [Assign work packages] → [Update WBS to level 4] →[Develop cost model] → [Develop logic network] → [Develop risk management procedure] ] → [Develop project strategy document]→ [Work package

The second iteration of the Systems Prioritization Method: A systems prioritization and decision-aiding tool for the Waste Isolation Pilot Plant: Volume 2, Summary of technical input and model implementation

Energy Technology Data Exchange (ETDEWEB)

Prindle, N.H.; Mendenhall, F.T.; Trauth, K.; Boak, D.M. [Sandia National Labs., Albuquerque, NM (United States); Beyeler, W. [Science Applications International Corp., Albuquerque, NM (United States); Hora, S. [Hawaii Univ., Hilo, HI (United States); Rudeen, D. [New Mexico Engineering Research Inst., Albuquerque, NM (United States)

1996-05-01

The Systems Prioritization Method (SPM) is a decision-aiding tool developed by Sandia National Laboratories (SNL). SPM provides an analytical basis for supporting programmatic decisions for the Waste Isolation Pilot Plant (WIPP) to meet selected portions of the applicable US EPA long-term performance regulations. The first iteration of SPM (SPM-1), the prototype for SPM< was completed in 1994. It served as a benchmark and a test bed for developing the tools needed for the second iteration of SPM (SPM-2). SPM-2, completed in 1995, is intended for programmatic decision making. This is Volume II of the three-volume final report of the second iteration of the SPM. It describes the technical input and model implementation for SPM-2, and presents the SPM-2 technical baseline and the activities, activity outcomes, outcome probabilities, and the input parameters for SPM-2 analysis.

The second iteration of the Systems Prioritization Method: A systems prioritization and decision-aiding tool for the Waste Isolation Pilot Plant: Volume 2, Summary of technical input and model implementation

International Nuclear Information System (INIS)

Prindle, N.H.; Mendenhall, F.T.; Trauth, K.; Boak, D.M.; Beyeler, W.; Hora, S.; Rudeen, D.

1996-05-01

The Systems Prioritization Method (SPM) is a decision-aiding tool developed by Sandia National Laboratories (SNL). SPM provides an analytical basis for supporting programmatic decisions for the Waste Isolation Pilot Plant (WIPP) to meet selected portions of the applicable US EPA long-term performance regulations. The first iteration of SPM (SPM-1), the prototype for SPM< was completed in 1994. It served as a benchmark and a test bed for developing the tools needed for the second iteration of SPM (SPM-2). SPM-2, completed in 1995, is intended for programmatic decision making. This is Volume II of the three-volume final report of the second iteration of the SPM. It describes the technical input and model implementation for SPM-2, and presents the SPM-2 technical baseline and the activities, activity outcomes, outcome probabilities, and the input parameters for SPM-2 analysis

Report format preferences of technical managers and nonmanagers

Science.gov (United States)

Pinelli, T. E.; Cordle, V. M.; Glassman, M.; Vondran, R. F., Jr.

1984-01-01

A survey of engineers and scientists concerning the format of NASA technical reports indicates that a summary as well as an abstract should be included, that the definitions of symbols and glossary of terms should be located in the front of the report, and that the illustrative material should be integrated with the text rather than grouped at the end of the report. Citation of references by number, one-column, ragged-right-margin layout, and third-person writing style are also preferred by a majority of the respondents. The preferences of managers and nonmanagers are very similar for all aspects of technical report format covered by the survey.

Survey of reader preferences concerning the format of NASA technical reports

Science.gov (United States)

Pinelli, T. E.; Glassman, M.; Cordle, V. M.

1982-01-01

A survey was conducted to determine the opinions of readers concerning the format (organization) of NASA technical reports and usage of technical report components. A survey questionnaire was sent to 513 LaRC engineers and scientists and 600 engineers and scientists from three (3) professional/technical societies. The response rates were 74 and 85 percent, respectively. The questionnaire included the order in which users read report components, the components reviewed or read to determine whether to read a report, report components which could be deleted, the desirability of a table of contents, the desirability of both a summary and abstract, the location of the symbols list and glossary, the integration of illustrative material, the preferred format for reference citations, column layout and right margin treatment, and person/voice. The results of the reader preference survey indicated that the conclusion was the component most often ready by survey respondents. The summary, conclusion, abstract, title page, and introduction were the components used most frequently to determine if a report would actually be read. Respondents indicated that a summary as well as an abstract should be included, that the definition of symbols and glossary of terms should be located in the front of the report, and that illustrative material should be integrated with the text rather than grouped at the end of the report. Citation by number was the preferred format for references. A one-column, ragged right margin was preferred. Third person, passive voice was the style of writing preferred by the respondents.

A Formal Theory of Perception. Technical Report No. 161.

Science.gov (United States)

Rottmayer, William Arthur

An attempt to build a mathematical model of a device that could learn geometry is discussed. The report discusses the background and motivation of the study, the coding problem, the derivation of Suppes "Stimulus-Response Theory of Finite Automata" used in the work in learning theory, and a summary of the technical work. (DB)

A long baseline global stereo matching based upon short baseline estimation

Science.gov (United States)

Li, Jing; Zhao, Hong; Li, Zigang; Gu, Feifei; Zhao, Zixin; Ma, Yueyang; Fang, Meiqi

2018-05-01

In global stereo vision, balancing the matching efficiency and computing accuracy seems to be impossible because they contradict each other. In the case of a long baseline, this contradiction becomes more prominent. In order to solve this difficult problem, this paper proposes a novel idea to improve both the efficiency and accuracy in global stereo matching for a long baseline. In this way, the reference images located between the long baseline image pairs are firstly chosen to form the new image pairs with short baselines. The relationship between the disparities of pixels in the image pairs with different baselines is revealed by considering the quantized error so that the disparity search range under the long baseline can be reduced by guidance of the short baseline to gain matching efficiency. Then, the novel idea is integrated into the graph cuts (GCs) to form a multi-step GC algorithm based on the short baseline estimation, by which the disparity map under the long baseline can be calculated iteratively on the basis of the previous matching. Furthermore, the image information from the pixels that are non-occluded under the short baseline but are occluded for the long baseline can be employed to improve the matching accuracy. Although the time complexity of the proposed method depends on the locations of the chosen reference images, it is usually much lower for a long baseline stereo matching than when using the traditional GC algorithm. Finally, the validity of the proposed method is examined by experiments based on benchmark datasets. The results show that the proposed method is superior to the traditional GC method in terms of efficiency and accuracy, and thus it is suitable for long baseline stereo matching.

BASELINE DEVELOPMENT USING THE CRITICAL DECISION AND DOE ORDER 413.3 FRAMEWORKS: A CASE STUDY

International Nuclear Information System (INIS)

Darnell, M.L.; Duffy, M.A.; Gantos, N.J.; Zadeh, B.

2003-01-01

From 1943 through 1986, Battelle Memorial Institute performed nuclear research and development on behalf of various Federal government agencies, primarily for the U.S. Department of Energy (DOE) and its predecessor agencies. This work was performed in Battelle's privately owned facilities in Columbus, Ohio, and a research park located at an 11-acre facility 16 miles west of Columbus, in a rural area near the village of West Jefferson, Ohio. Under the Battelle Columbus Laboratories Decommissioning Project (BCLDP), Battelle is now engaged in cleaning up the West Jefferson site on a cost-sharing basis with the DOE. The BCLDP mission is to decontaminate Battelle facilities in a safe, environmentally sound, and cost-effective manner, returning the facilities to a condition suitable for use without radiological restriction. The Columbus Environmental Management Project (CEMP), reporting to the DOE Ohio Field Office, is the DOE organization that is responsible for overseeing the BCLDP. CEMP requested preparation of a technical baseline, suitable for independent validation, establishing the scope, cost, and schedule for completing the project. Concurrent with this request, the DOE Office of Environmental Management issued DOE Order 413.3, Program and Project Management for the Acquisition of Capital Assets, for review and, shortly thereafter, published the first drafts of companion documents titled Program and Project Management Manual and Project Management Practices. These two documents suggest or require the use of a variety of techniques and tools for planning and executing DOE cleanup programs. Accordingly, Battelle successfully developed a project baseline for obtaining approval of Critical Decision 2/3 (CD-2/3) in compliance with the requirements of DOE Order 413.3 and the technical approaches described in the companion documents. This paper addresses three fundamental questions:(1) What were the planned baseline development methodology and its implementation

Summary list of CEA notes published by the French Atomic Energy Commission (April 1953 - September 1957)

International Nuclear Information System (INIS)

1957-09-01

This document is a summary list of the bibliographic references of all technical notes (CEA-N) published by the French Atomic Energy Commission between April 1953 and September 1957 (note number, authors, title)

Summary list of CEA notes published by the French Atomic Energy Commission (October 1957 - January 1958)

International Nuclear Information System (INIS)

1959-01-01

This document is a summary list of the bibliographic references of all technical notes (CEA-N) published by the French Atomic Energy Commission between October 1957 and January 1958 (note number, authors, title)

Summaries of foreign government environmental reports, Number 37

International Nuclear Information System (INIS)

1975-09-01

Under a series of document exchange agreements with environmental agencies in other countries, EPA is building a collection of environmental reports issued by foreign governments and international organizations. This is a monthly announcement listing of foreign documents received through the exchange agreements. This series, devoted to summaries of government reports and other pertinent literature and focusing on the legislative, organizational, economic, and social aspects of environmental protection, supplements foreign scientific and technical literature abstracted by other EPA information services

Large Hospital 50% Energy Savings: Technical Support Document

Energy Technology Data Exchange (ETDEWEB)

Bonnema, E.; Studer, D.; Parker, A.; Pless, S.; Torcellini, P.

2010-09-01

This Technical Support Document documents the technical analysis and design guidance for large hospitals to achieve whole-building energy savings of at least 50% over ANSI/ASHRAE/IESNA Standard 90.1-2004 and represents a step toward determining how to provide design guidance for aggressive energy savings targets. This report documents the modeling methods used to demonstrate that the design recommendations meet or exceed the 50% goal. EnergyPlus was used to model the predicted energy performance of the baseline and low-energy buildings to verify that 50% energy savings are achievable. Percent energy savings are based on a nominal minimally code-compliant building and whole-building, net site energy use intensity. The report defines architectural-program characteristics for typical large hospitals, thereby defining a prototype model; creates baseline energy models for each climate zone that are elaborations of the prototype models and are minimally compliant with Standard 90.1-2004; creates a list of energy design measures that can be applied to the prototype model to create low-energy models; uses industry feedback to strengthen inputs for baseline energy models and energy design measures; and simulates low-energy models for each climate zone to show that when the energy design measures are applied to the prototype model, 50% energy savings (or more) are achieved.

The Agency's technical co-operation activities in 1992

International Nuclear Information System (INIS)

1993-08-01

This report on the International Atomic Energy Agency's Technical Co-operation Activities in 1992 contains an overview of the general issues involved, including both in-house and external developments, resources and delivery, and evaluation of programs; an overview by field of activity and by division within the Agency; an overview by geographic area, distinguishing (i) Africa, (ii) Asia and the Pacific, (iii) Latin America, (iv) and the Middle East and Europe; an overview by component (i.e., experts, equipment, fellowships, training courses, sub-contracts and miscellaneous); and an overview by fund technical assistance and co-operation fund, extrabudgetary resources, United Nations Development Program (UNDP), assistance in kind. It also contains a profile on technical co-operation activities in Latin America. Projects concluded during 1992 are listed together with a description of their achievements. It concludes with implementation summaries. 10 figs, 9 tabs

Case studies: Risk-based analysis of technical specifications

International Nuclear Information System (INIS)

Wagner, D.P.; Minton, L.A.; Gaertner, J.P.

1987-01-01

The SOCRATES computer program uses the results of a Probabilistic Risk Assessment (PRA) or a system level risk analysis to calculate changes in risk due to changes in the surveillance test interval and/or the allowed outage time stated in the technical specification. The computer program can accommodate various testing strategies (such as staggered or simultaneous testing) to allow modeling of component testing as it is carried out at a plant. The methods and computer program are an integral part of a larger decision process aimed at determining benefits from technical specification changes. These benefits can include cost savings to the utilities by reducing forced shutdowns with no adverse impacts on risk. Three summaries of case study applications are included to demonstrate the types of results that can be achieved through risk-based evaluation of technical specifications. (orig.)

[Fuel substitution of vehicles by natural gas: Summaries of four final technical reports

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-05-01

This report contains summary information on three meetings and highlights of a fourth meeting held by the Society of Automotive Engineers on natural gas fueled vehicles. The meetings covered the following: Natural gas engine and vehicle technology; Safety aspects of alternately fueled vehicles; Catalysts and emission control--Meeting the legislative standards; and LNG--Strengthening the links.

Three Mile Island technical information and examination program instrumentation and electrical summary report

International Nuclear Information System (INIS)

Meininger, R.D.

1985-07-01

This report summarizes the investigations on instrumentation and electrical systems that were subjected to a loss-of-coolant accident environment during and following the accident at Three Mile Island Unit-2 (TMI-2) on March 28, 1979. The report is a summary of information previously published in GEND-INF reports, plus current knowledge of the investigators

American Samoa Initial Technical Assessment Report

Energy Technology Data Exchange (ETDEWEB)

Busche, S.; Conrad, M.; Funk, K.; Kandt, A.; McNutt, P.

2011-09-01

This document is an initial energy assessment for American Samoa, the first of many steps in developing a comprehensive energy strategy. On March 1, 2010, Assistant Secretary of the Interior Tony Babauta invited governors and their staff from the Interior Insular Areas to meet with senior principals at the National Renewable Energy Laboratory (NREL). Meeting discussions focused on ways to improve energy efficiency and increase the deployment of renewable energy technologies in the U.S. Pacific Territories. In attendance were Governors Felix Camacho (Guam), Benigno Fitial (Commonwealth of the Northern Mariana Islands), and Togiola Tulafono, (American Samoa). This meeting brought together major stakeholders to learn and understand the importance of developing a comprehensive strategic plan for implementing energy efficiency measures and renewable energy technologies. For several decades, dependence on fossil fuels and the burden of high oil prices have been a major concern but never more at the forefront as today. With unstable oil prices, the volatility of fuel supply and the economic instability in American Samoa, energy issues are a high priority. In short, energy security is critical to American Samoa's future economic development and sustainability. Under an interagency agreement, funded by the Department of Interior's Office of Insular Affairs, NREL was tasked to deliver technical assistance to the islands of American Samoa. Technical assistance included conducting an initial technical assessment to define energy consumption and production data, establish an energy consumption baseline, and assist with the development of a strategic plan. The assessment and strategic plan will be used to assist with the transition to a cleaner energy economy. NREL provided an interdisciplinary team to cover each relevant technical area for the initial energy assessments. Experts in the following disciplines traveled to American Samoa for on-island site assessments: (1

Technical review of the Sandia Laboratories' Particle Beam Fusion Program

International Nuclear Information System (INIS)

1979-01-01

This report considers the technical aspects of Sandia Laboratories' Particle Beam Fusion Program and examines the program's initial goals, the progress made to date towards reaching those goals, and the future plans or methods of reaching those original or modified goals. A summary of Sandia Laboratories' effort, which seeks to demonstrate that high voltage pulsed power generated high-current electron or light ion beams can be used to ignite a deuterium or tritium pellet, is provided. A brief review and assessment of the Sandia Pulse Power Program is given. Several critical issues and summaries of the committee members' opinions are discussed

Progress summary of the Chernobyl accident

International Nuclear Information System (INIS)

Iddekinge, F.W. van

1986-01-01

Based on two IAEA documents (the report of the USSR State Committee on the Utilization of Atomic Energy named 'The accident at the Chernobyl nuclear power plant and its consequences' prepared for the IAEA Experts Meeting held in Vienna on 25-29 August, 1986 and the INSAG (International Nuclear Safety Advisory Group) summary report on the Post-accident review meeting on the Chernobyl accident, drawn up in Vienna from August 30 until September 5, 1986, this publication tries to present a logic relation between the special features of the RMBK-1000 LWGR, the cause of the accident, and the technical countermeasures. (Auth.)

Integrated Baseline System (IBS) Version 2.0: Models guide

Energy Technology Data Exchange (ETDEWEB)

1994-03-01

The Integrated Baseline System (IBS) is an emergency management planning and analysis tool being developed under the direction of the US Army Nuclear and Chemical Agency. This Models Guide summarizes the IBS use of several computer models for predicting the results of emergency situations. These include models for predicting dispersion/doses of airborne contaminants, traffic evacuation, explosion effects, heat radiation from a fire, and siren sound transmission. The guide references additional technical documentation on the models when such documentation is available from other sources. The audience for this manual is chiefly emergency management planners and analysts, but also data managers and system managers.

77 FR 65542 - Hydrogen and Fuel Cell Technical Advisory Committee (HTAC)

Science.gov (United States)

2012-10-29

... DEPARTMENT OF ENERGY Office of Energy Efficiency and Renewable Energy Hydrogen and Fuel Cell... Energy. ACTION: Notice of Open Meeting. SUMMARY: The Hydrogen and Fuel Cell Technical Advisory Committee... Agenda: (updates will be posted on the web at: http://hydrogen.energy.gov ). Public Comment DOE Program...

75 FR 2860 - Hydrogen and Fuel Cell Technical Advisory Committee (HTAC)

Science.gov (United States)

2010-01-19

... DEPARTMENT OF ENERGY Office of Energy Efficiency and Renewable Energy Hydrogen and Fuel Cell... Energy. ACTION: Notice of Open Meeting. SUMMARY: The Hydrogen and Fuel Cell Technical Advisory Committee... change; updates will be posted on http://hydrogen.energy.gov and copies of the final agenda will...

Technical co-operation report for 2000. Report by the Director General

International Nuclear Information System (INIS)

2001-01-01

This report covers three separate topics. Part one fulfills the Agency's obligation under the General Conference resolution GC(44)/RES/18 to report on the Strengthening of Technical Co-operation. It covers the period from 1 April 2000 to 31 March 2001. The report examines the finalization of the 2001-2002 technical co-operation programme and several key concepts of the Technical Co-operation Strategy such as Partners in Development, Technical Co-operation among Developing Countries, and the continuing evolution of Regional Resource Centres. Reflecting an important trend in the technical co-operation programme, which was mandated by the General Conference, the report describes the results achieved in several programmes in least developed countries. Part two reports on the major achievements of the technical co-operation programme in 2000 in the different regions of the world. Part three presents a summary of the financial and non-financial parameters of the technical co-operation programme. The supplement to the report provides a more detailed review of resources and contributions, disbursements and non-financial indicators

Technical co-operation report for 2000. Report by the Director General

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

This report covers three separate topics. Part one fulfills the Agency's obligation under the General Conference resolution GC(44)/RES/18 to report on the Strengthening of Technical Co-operation. It covers the period from 1 April 2000 to 31 March 2001. The report examines the finalization of the 2001-2002 technical co-operation programme and several key concepts of the Technical Co-operation Strategy such as Partners in Development, Technical Co-operation among Developing Countries, and the continuing evolution of Regional Resource Centres. Reflecting an important trend in the technical co-operation programme, which was mandated by the General Conference, the report describes the results achieved in several programmes in least developed countries. Part two reports on the major achievements of the technical co-operation programme in 2000 in the different regions of the world. Part three presents a summary of the financial and non-financial parameters of the technical co-operation programme. The supplement to the report provides a more detailed review of resources and contributions, disbursements and non-financial indicators.

The optimized baseline project: Reinventing environmental restoration at Hanford

International Nuclear Information System (INIS)

Goodenough, J.D.; Janaskie, M.T.; Kleinen, P.J.

1994-01-01

The U.S. Department of Energy Richland Operations Office (DOE-RL) is using a strategic planning effort (termed the Optimized Baseline Project) to develop a new approach to the Hanford Environmental Restoration program. This effort seeks to achieve a quantum leap improvement in performance through results oriented prioritization of activities. This effort was conducted in parallel with the renegotiation of the Tri-Party Agreement and provided DOE with an opportunity to propose innovative initiatives to promote cost effectiveness, accelerate progress in the Hanford Environmental Restoration Program and involve stakeholders in the decision-making process. The Optimized Baseline project is an innovative approach to program planning and decision-making in several respects. First, the process is a top down, value driven effort that responds to values held by DOE, the regulatory community and the public. Second, planning is conducted in a way that reinforces the technical management process at Richland, involves the regulatory community in substantive decisions, and includes the public. Third, the Optimized Baseline Project is being conducted as part of a sitewide Hanford initiative to reinvent Government. The planning process used for the Optimized Baseline Project has many potential applications at other sites and in other programs where there is a need to build consensus among diverse, independent groups of stakeholders and decisionmakers. The project has successfully developed and demonstrated an innovative approach to program planning that accelerates the pace of cleanup, involves the regulators as partners with DOE in priority setting, and builds public understanding and support for the program through meaningful opportunities for involvement

The WITCH Model. Structure, Baseline, Solutions.

Energy Technology Data Exchange (ETDEWEB)

Bosetti, V.; Massetti, E.; Tavoni, M.

2007-07-01

WITCH - World Induced Technical Change Hybrid - is a regionally disaggregated hard link hybrid global model with a neoclassical optimal growth structure (top down) and an energy input detail (bottom up). The model endogenously accounts for technological change, both through learning curves affecting prices of new vintages of capital and through R and D investments. The model features the main economic and environmental policies in each world region as the outcome of a dynamic game. WITCH belongs to the class of Integrated Assessment Models as it possesses a climate module that feeds climate changes back into the economy. In this paper we provide a thorough discussion of the model structure and baseline projections. We report detailed information on the evolution of energy demand, technology and CO2 emissions. Finally, we explicitly quantifiy the role of free riding in determining the emissions scenarios. (auth)

Draft 1992 Resource Program : Technical Report.

Energy Technology Data Exchange (ETDEWEB)

United States. Bonneville Power Administration.

1992-01-01

The 1992 Resource Program will propose actions to meet future loads placed on the Bonneville Power Administration (BPA). It will also discuss and attempt to resolve resource-related policy issues. The Resource Program assesses resource availability and costs, and analyzes resource requirements and alternative ways of meeting those requirements through both conservation and generation resources. These general resource conclusions are then translated to actions for both conservation and generation. The Resource Program recommends budgets for the Office of Energy Resources for Fiscal Years (FY) 1994 and 1995. BPA's Resource Program bears directly on an important BPA responsibility: the obligation under the Northwest Power Act{sup 3} to meet the power requirements of public and private utility and direct service industrial (DSI) customers according to their contractual agreements. BPA's Draft 1992 Resource Program is contained in four documents: (1) 1992 Resource Program Summary; (2) Technical Report; (3) Technical Assumptions Appendix; and, (4) Conservation Implementation Plan. This volume is the Draft 1992 Resource Program Technical Report, a comprehensive document that provides supporting data and analyses for Resource Program recommendations.

Draft 1992 Resource Program : Technical Report.

Energy Technology Data Exchange (ETDEWEB)

United States. Bonneville Power Administration.

1992-01-01

The 1992 Resource Program will propose actions to meet future loads placed on the Bonneville Power Administration (BPA). It will also discuss and attempt to resolve resource-related policy issues. The Resource Program assesses resource availability and costs, and analyzes resource requirements and alternative ways of meeting those requirements through both conservation and generation resources. These general resource conclusions are then translated to actions for both conservation and generation. The Resource Program recommends budgets for the Office of Energy Resources for Fiscal Years (FY) 1994 and 1995. BPA`s Resource Program bears directly on an important BPA responsibility: the obligation under the Northwest Power Act{sup 3} to meet the power requirements of public and private utility and direct service industrial (DSI) customers according to their contractual agreements. BPA`s Draft 1992 Resource Program is contained in four documents: (1) 1992 Resource Program Summary; (2) Technical Report; (3) Technical Assumptions Appendix; and, (4) Conservation Implementation Plan. This volume is the Draft 1992 Resource Program Technical Report, a comprehensive document that provides supporting data and analyses for Resource Program recommendations.

75 FR 82241 - Technical Correction: Completion of Entry and Entry Summary-Declaration of Value

Science.gov (United States)

2010-12-30

... Entry Summary-- Declaration of Value AGENCY: Customs and Border Protection, Department of Homeland... manner by which the declared transaction value on imported merchandise was determined. This requirement... whether the transaction value of imported merchandise is determined on the basis of the price paid by the...

Summary of Expansions, Updates, and Results in GREET 2017 Suite of Models

Energy Technology Data Exchange (ETDEWEB)

Wang, Michael [Argonne National Lab. (ANL), Argonne, IL (United States); Elgowainy, Amgad [Argonne National Lab. (ANL), Argonne, IL (United States); Han, Jeongwoo [Argonne National Lab. (ANL), Argonne, IL (United States); Benavides, Pahola Thathiana [Argonne National Lab. (ANL), Argonne, IL (United States); Burnham, Andrew [Argonne National Lab. (ANL), Argonne, IL (United States); Cai, Hao [Argonne National Lab. (ANL), Argonne, IL (United States); Canter, Christina [Argonne National Lab. (ANL), Argonne, IL (United States); Chen, Rui [Argonne National Lab. (ANL), Argonne, IL (United States); Dai, Qiang [Argonne National Lab. (ANL), Argonne, IL (United States); Kelly, Jarod [Argonne National Lab. (ANL), Argonne, IL (United States); Lee, Dong-Yeon [Argonne National Lab. (ANL), Argonne, IL (United States); Lee, Uisung [Argonne National Lab. (ANL), Argonne, IL (United States); Li, Qianfeng [Argonne National Lab. (ANL), Argonne, IL (United States); Lu, Zifeng [Argonne National Lab. (ANL), Argonne, IL (United States); Qin, Zhangcai [Argonne National Lab. (ANL), Argonne, IL (United States); Sun, Pingping [Argonne National Lab. (ANL), Argonne, IL (United States); Supekar, Sarang D. [Argonne National Lab. (ANL), Argonne, IL (United States)

2017-11-01

This report provides a technical summary of the expansions and updates to the 2017 release of Argonne National Laboratory’s Greenhouse Gases, Regulated Emissions, and Energy Use in Transportation (GREET®) model, including references and links to key technical documents related to these expansions and updates. The GREET 2017 release includes an updated version of the GREET1 (the fuel-cycle GREET model) and GREET2 (the vehicle-cycle GREET model), both in the Microsoft Excel platform and in the GREET.net modeling platform. Figure 1 shows the structure of the GREET Excel modeling platform. The .net platform integrates all GREET modules together seamlessly.

Technical co-operation report for 1998. Report by the Director General

International Nuclear Information System (INIS)

1999-01-01

This report presents the IAEA Technical Co-operation (TC) activities during 1998 and highlights most significant accomplishments. Part I of this report reviews the strengthening of TC, both in financial aspects and through implementation of the TC strategy. Part II reviews extensively the actual output of the TC programme; it looks at each geographic region, and reports on the results of national, regional and, where applicable, interregional activities in those regions. Part III presents a technical discussion of the financial parameters of the TC programme and ends with financial implementation summaries

Technical co-operation report for 1998. Report by the Director General

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-07-01

This report presents the IAEA Technical Co-operation (TC) activities during 1998 and highlights most significant accomplishments. Part I of this report reviews the strengthening of TC, both in financial aspects and through implementation of the TC strategy. Part II reviews extensively the actual output of the TC programme; it looks at each geographic region, and reports on the results of national, regional and, where applicable, interregional activities in those regions. Part III presents a technical discussion of the financial parameters of the TC programme and ends with financial implementation summaries.

Technical advisory panel for the large acceptance spectrometer: Final report

International Nuclear Information System (INIS)

1989-01-01

The Technical Advisory Panel for the Large Acceptance Spectrometer met on November 17--19, 1988, at CEBAF to perform a second review of the status of this project. The charge to the Panel was ''to provide technical advice to the CEBAF directorate on the design, construction, cost, schedule, and implementation of the Large Acceptance Spectrometer.'' In this written report, an overview of the entire project is given. Specific comments on the major components, data handling and analysis, assembly and installation, and management are presented. The Panel's conclusions are contained in the Executive Summary at the beginning of the report

Developing RESRAD-BASELINE for environmental baseline risk assessment

International Nuclear Information System (INIS)

Cheng, Jing-Jy.

1995-01-01

RESRAD-BASELINE is a computer code developed at Argonne developed at Argonne National Laboratory for the US Department of Energy (DOE) to perform both radiological and chemical risk assessments. The code implements the baseline risk assessment guidance of the US Environmental Protection Agency (EPA 1989). The computer code calculates (1) radiation doses and cancer risks from exposure to radioactive materials, and (2) hazard indexes and cancer risks from exposure to noncarcinogenic and carcinogenic chemicals, respectively. The user can enter measured or predicted environmental media concentrations from the graphic interface and can simulate different exposure scenarios by selecting the appropriate pathways and modifying the exposure parameters. The database used by PESRAD-BASELINE includes dose conversion factors and slope factors for radionuclides and toxicity information and properties for chemicals. The user can modify the database for use in the calculation. Sensitivity analysis can be performed while running the computer code to examine the influence of the input parameters. Use of RESRAD-BASELINE for risk analysis is easy, fast, and cost-saving. Furthermore, it ensures in consistency in methodology for both radiological and chemical risk analyses

Technical Summary

NARCIS (Netherlands)

Arvizu, D.; Faaij, A.P.C.

2011-01-01

All societies requir e energy services to meet basic human needs (e.g., lighting, cooking, space comfort, mobility, communication) and to serve productive processes. For development to be sustainable, delivery of energy services needs to be secure and have low environmental impacts. Sustainable

Improving the accuracy of operation coding in surgical discharge summaries

Science.gov (United States)

Martinou, Eirini; Shouls, Genevieve; Betambeau, Nadine

2014-01-01

Procedural coding in surgical discharge summaries is extremely important; as well as communicating to healthcare staff which procedures have been performed, it also provides information that is used by the hospital's coding department. The OPCS code (Office of Population, Censuses and Surveys Classification of Surgical Operations and Procedures) is used to generate the tariff that allows the hospital to be reimbursed for the procedure. We felt that the OPCS coding on discharge summaries was often incorrect within our breast and endocrine surgery department. A baseline measurement over two months demonstrated that 32% of operations had been incorrectly coded, resulting in an incorrect tariff being applied and an estimated loss to the Trust of £17,000. We developed a simple but specific OPCS coding table in collaboration with the clinical coding team and breast surgeons that summarised all operations performed within our department. This table was disseminated across the team, specifically to the junior doctors who most frequently complete the discharge summaries. Re-audit showed 100% of operations were accurately coded, demonstrating the effectiveness of the coding table. We suggest that specifically designed coding tables be introduced across each surgical department to ensure accurate OPCS codes are used to produce better quality surgical discharge summaries and to ensure correct reimbursement to the Trust. PMID:26734286

A synoptic summary approach to better understanding groundwater contamination problems and evaluating long-term environmental consequences

International Nuclear Information System (INIS)

Nelson, R.W.

1990-09-01

A summary approach has been developed within groundwater hydrology to communicate with a broad audience and more completely evaluate the long-term impacts of subsurface contamination problems. This synoptic approach both highlights the dominant features occurring in subsurface contamination problems and emphasizes the information required to determine the long-term environmental impacts. The special merit of a summary approach is in providing a better understanding of subsurface contamination problems to adjoining technical disciplines, public decision makers, and private citizens. 14 refs

Executive Summary High-Yield Scenario Workshop Series Report

Energy Technology Data Exchange (ETDEWEB)

Leslie Park Ovard; Thomas H. Ulrich; David J. Muth Jr.; J. Richard Hess; Steven Thomas; Bryce Stokes

2009-12-01

To get a collective sense of the impact of research and development (R&D) on biomass resource availability, and to determine the feasibility that yields higher than baseline assumptions used for past assessments could be achieved to support U.S. energy independence, an alternate “High-Yield Scenario” (HYS) concept was presented to industry experts at a series of workshops held in December 2009. The workshops explored future production of corn/agricultural crop residues, herbaceous energy crops (HECs), and woody energy crops (WECs). This executive summary reports the findings of that workshop.

Effective summary evaluators for deep nuclear waste repositories: geohydrologic response function

International Nuclear Information System (INIS)

Nelson, R.W.; Dove, F.H.

1981-03-01

Useful insight has been gained over the past four years as hydrologic system modeling has been applied to evaluate hypothetical, waste-repository sites in various geologic media. The Geohydrologic Response Functions, described in this paper, are shown to: blend extensive results of technical analysis into simple summary relationships, and to potentially help the public and decision makers to evaluate the magnitude of any loss in repository integrity

Western Canada study of animal health effects associated with exposure to emissions from oil and gas field facilities : technical summary

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-01-15

The impact of exposure to emissions from oil and gas field facilities on animal and human health has been a long-standing concern in western Canada. This technical summary presented highlights of the 17 major research appendices of a study examining associations between emissions and important reproductive parameters in beef cattle, including pregnancy rates, frequencies of abortions and stillbirths, and the risk of death among young calves. The effect of exposure to emissions on the respiratory, immune and nervous systems of calves and yearlings was also evaluated. The study was an epidemiological investigation that drew on large blocks of data collected from privately owned cow-calf operations, laboratory analyses of biological samples and samplers from air monitors. Mixed effect regression models were used to investigate whether measures of reproductive, immunological, and pathology outcomes were associated with emissions from the petroleum industry. Appropriate statistical adjustments were made to correct for multiple comparisons following standard statistical practice. An overview of the methods used to analyze the data was presented, as well as an examination of the methods of epidemiology in determining a causal effect, and the limitations of a single study in determining causation with certainty. Information on water quality testing and feeding management and forage testing was provided. 15 tabs., 26 figs.

Western Canada study of animal health effects associated with exposure to emissions from oil and gas field facilities : technical summary

International Nuclear Information System (INIS)

2006-01-01

The impact of exposure to emissions from oil and gas field facilities on animal and human health has been a long-standing concern in western Canada. This technical summary presented highlights of the 17 major research appendices of a study examining associations between emissions and important reproductive parameters in beef cattle, including pregnancy rates, frequencies of abortions and stillbirths, and the risk of death among young calves. The effect of exposure to emissions on the respiratory, immune and nervous systems of calves and yearlings was also evaluated. The study was an epidemiological investigation that drew on large blocks of data collected from privately owned cow-calf operations, laboratory analyses of biological samples and samplers from air monitors. Mixed effect regression models were used to investigate whether measures of reproductive, immunological, and pathology outcomes were associated with emissions from the petroleum industry. Appropriate statistical adjustments were made to correct for multiple comparisons following standard statistical practice. An overview of the methods used to analyze the data was presented, as well as an examination of the methods of epidemiology in determining a causal effect, and the limitations of a single study in determining causation with certainty. Information on water quality testing and feeding management and forage testing was provided. 15 tabs., 26 figs

Technology status in support of refined technical baseline for the Spent Nuclear Fuel project. Revision 1

Energy Technology Data Exchange (ETDEWEB)

Puigh, R.J.; Toffer, H.; Heard, F.J.; Irvin, J.J.; Cooper, T.D.

1995-10-20

The Spent Nuclear Fuel Project (SNFP) has undertaken technology acquisition activities focused on supporting the technical basis for the removal of the N Reactor fuel from the K Basins to an interim storage facility. The purpose of these technology acquisition activities has been to identify technology issues impacting design or safety approval, to establish the strategy for obtaining the necessary information through either existing project activities, or the assignment of new work. A set of specific path options has been identified for each major action proposed for placing the N Reactor fuel into a ``stabilized`` form for interim storage as part of this refined technical basis. This report summarizes the status of technology information acquisition as it relates to key decisions impacting the selection of specific path options. The following specific categories were chosen to characterize and partition the technology information status: hydride issues and ignition, corrosion, hydrogen generation, drying and conditioning, thermal performance, criticality and materials accountability, canister/fuel particulate behavior, and MCO integrity. This report represents a preliminary assessment of the technology information supporting the SNFP. As our understanding of the N Reactor fuel performance develops the technology information supporting the SNFP will be updated and documented in later revisions to this report. Revision 1 represents the incorporation of peer review comments into the original document. The substantive evolution in our understanding of the technical status for the SNFP (except section 3) since July 1995 have not been incorporated into this revision.

Technology status in support of refined technical baseline for the Spent Nuclear Fuel project. Revision 1

International Nuclear Information System (INIS)

Puigh, R.J.; Toffer, H.; Heard, F.J.; Irvin, J.J.; Cooper, T.D.

1995-01-01

The Spent Nuclear Fuel Project (SNFP) has undertaken technology acquisition activities focused on supporting the technical basis for the removal of the N Reactor fuel from the K Basins to an interim storage facility. The purpose of these technology acquisition activities has been to identify technology issues impacting design or safety approval, to establish the strategy for obtaining the necessary information through either existing project activities, or the assignment of new work. A set of specific path options has been identified for each major action proposed for placing the N Reactor fuel into a ''stabilized'' form for interim storage as part of this refined technical basis. This report summarizes the status of technology information acquisition as it relates to key decisions impacting the selection of specific path options. The following specific categories were chosen to characterize and partition the technology information status: hydride issues and ignition, corrosion, hydrogen generation, drying and conditioning, thermal performance, criticality and materials accountability, canister/fuel particulate behavior, and MCO integrity. This report represents a preliminary assessment of the technology information supporting the SNFP. As our understanding of the N Reactor fuel performance develops the technology information supporting the SNFP will be updated and documented in later revisions to this report. Revision 1 represents the incorporation of peer review comments into the original document. The substantive evolution in our understanding of the technical status for the SNFP (except section 3) since July 1995 have not been incorporated into this revision

International Code Centres Network. Summary Report of the Technical Meeting

International Nuclear Information System (INIS)

Chung, H-K.

2011-01-01

Fifteen international experts on computational aspects of atomic, molecular and particle surface interaction data for fusion energy research participated in the 2nd technical meeting of the International Code Centres Network. Participants reported their research on data production and computational capabilities at their institutions. Experts in the field of plasma modeling of magnetic fusion research joined this meeting to present the data needs and bring the perspective of data users. The interaction and discussion among data producers and data users in this two-day meeting led to an agreement that the scope and function of Code Centres Network should be reformulated to serve the needs of fusion community in more effective way. (author)

ITER technical basis

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-01-01

Following on from the Final Report of the EDA(DS/21), and the summary of the ITER Final Design report(DS/22), the technical basis gives further details of the design of ITER. It is in two parts. The first, the Plant Design specification, summarises the main constraints on the plant design and operation from the viewpoint of engineering and physics assumptions, compliance with safety regulations, and siting requirements and assumptions. The second, the Plant Description Document, describes the physics performance and engineering characteristics of the plant design, illustrates the potential operational consequences foe the locality of a generic site, gives the construction, commissioning, exploitation and decommissioning schedule, and reports the estimated lifetime costing based on data from the industry of the EDA parties.

ITER technical basis

International Nuclear Information System (INIS)

2002-01-01

Following on from the Final Report of the EDA(DS/21), and the summary of the ITER Final Design report(DS/22), the technical basis gives further details of the design of ITER. It is in two parts. The first, the Plant Design specification, summarises the main constraints on the plant design and operation from the viewpoint of engineering and physics assumptions, compliance with safety regulations, and siting requirements and assumptions. The second, the Plant Description Document, describes the physics performance and engineering characteristics of the plant design, illustrates the potential operational consequences foe the locality of a generic site, gives the construction, commissioning, exploitation and decommissioning schedule, and reports the estimated lifetime costing based on data from the industry of the EDA parties

Next Generation Nuclear Plant Project Technology Development Roadmaps: The Technical Path Forward

Energy Technology Data Exchange (ETDEWEB)

John Collins

2009-01-01

This document presents the Next Generation Nuclear Plant (NGNP) Systems, Subsystems, and Components, establishes a baseline for the current technology readiness status, and provides a path forward to achieve increasing levels of technical maturity.

Technical Support Document: Strategies for 50% Energy Savings in Large Office Buildings

Energy Technology Data Exchange (ETDEWEB)

Leach, M.; Lobato, C.; Hirsch, A.; Pless, S.; Torcellini, P.

2010-09-01

This Technical Support Document (TSD) documents technical analysis that informs design guidance for designing and constructing large office buildings that achieve 50% net site energy savings over baseline buildings defined by minimal compliance with respect to ANSI/ASHRAE/IESNA Standard 90.1-2004. This report also represents a step toward developing a methodology for using energy modeling in the design process to achieve aggressive energy savings targets. This report documents the modeling and analysis methods used to identify design recommendations for six climate zones that capture the range of U.S. climate variability; demonstrates how energy savings change between ASHRAE Standard 90.1-2007 and Standard 90.1-2004 to determine baseline energy use; uses a four-story 'low-rise' prototype to analyze the effect of building aspect ratio on energy use intensity; explores comparisons between baseline and low-energy building energy use for alternate energy metrics (net source energy, energy emissions, and energy cost); and examines the extent to which glass curtain construction limits achieve energy savings by using a 12-story 'high-rise' prototype.

Summary of fuel safety research meeting 2004

International Nuclear Information System (INIS)

Fuketa, Toyoshi; Hidaka, Akihide; Nakamura, Jinichi; Suzuki, Motoe; Nagase, Fumihisa; Sasajima, Hideo; Fujita, Misao; Otomo, Takashi; Kudo, Tamotsu; Amaya, Masaki; Sugiyama, Tomoyuki; Ikehata, Hisashi; Iwasaki, Ryo; Ozawa, Masaaki; Kida, Mitsuko

2004-10-01

Fuel Safety Research Meeting 2004, which was organized by the Japan Atomic Energy Research Institute, was held on March 1-2, 2004 at Toranomon Pastoral, Tokyo. The purposes of the meeting are to present and discuss the results of experiments and analyses on reactor fuel safety and to exchange views and experiences among the participants. The technical topics of the meeting covered the status of fuel safety research activities, fuel behavior under RIA and LOCA conditions, high burnup fuel behavior, and radionuclides release under severe accident conditions. This summary contains all the abstracts and OHP sheets presented in the meeting. (author)

Division of Biological and Medical Research research summary 1984-1985

Energy Technology Data Exchange (ETDEWEB)

Barr, S.H. (ed.)

1985-08-01

The Division of Biological and Medical Research at Argonne National Laboratory conducts multidisciplinary research aimed at defining the biological and medical hazards to man from energy technologies and new energy options. These technically oriented studies have a strong base in fundamental research in a variety of scientific disciplines, including molecular and cellular biology, biophysics, genetics, radiobiology, pharmacology, biochemistry, chemistry, environmental toxicology, and epidemiology. This research summary is organized into six parts. The first five parts reflect the Divisional structure and contain the scientific program chapters, which summarize the activities of the individual groups during the calendar year 1984 and the first half of 1985. To provide better continuity and perspective, previous work is sometimes briefly described. Although the summaries are short, efforts have been made to indicate the range of research activities for each group.

Division of Biological and Medical Research research summary 1984-1985

International Nuclear Information System (INIS)

Barr, S.H.

1985-08-01

The Division of Biological and Medical Research at Argonne National Laboratory conducts multidisciplinary research aimed at defining the biological and medical hazards to man from energy technologies and new energy options. These technically oriented studies have a strong base in fundamental research in a variety of scientific disciplines, including molecular and cellular biology, biophysics, genetics, radiobiology, pharmacology, biochemistry, chemistry, environmental toxicology, and epidemiology. This research summary is organized into six parts. The first five parts reflect the Divisional structure and contain the scientific program chapters, which summarize the activities of the individual groups during the calendar year 1984 and the first half of 1985. To provide better continuity and perspective, previous work is sometimes briefly described. Although the summaries are short, efforts have been made to indicate the range of research activities for each group

Baseline assessment of benthic communities of the Flower Garden Banks (2010 - 2013) using technical diving operations: 2011

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — The work developed baseline information on fish and benthic communities within the Flower Garden Banks National Marine Sanctuary (FGBNMS). Surveys employed diving,...

78 FR 41304 - Navigation and Navigable Waters; Technical, Organizational, and Conforming Amendments; Correction

Science.gov (United States)

2013-07-10

... DEPARTMENT OF HOMELAND SECURITY Coast Guard 33 CFR Part 105 [Docket No. USCG-2013-0397] RIN 1625-AC06 Navigation and Navigable Waters; Technical, Organizational, and Conforming Amendments; Correction AGENCY: Coast Guard, DHS. ACTION: Final rule; correction. SUMMARY: The Coast Guard published a final rule...

77 FR 23117 - Rigging Equipment for Material Handling Construction Standard; Correction and Technical Amendment

Science.gov (United States)

2012-04-18

... Equipment for Material Handling Construction Standard; Correction and Technical Amendment AGENCY... AND HEALTH REGULATIONS FOR CONSTRUCTION Subpart H--Materials Handling, Storage, Use, and Disposal 0 1... amendment. SUMMARY: OSHA is correcting its sling standard for construction titled ``Rigging Equipment for...

Mergeable summaries

DEFF Research Database (Denmark)

Agarwal, Pankaj K.; Graham, Graham; Huang, Zengfeng

2013-01-01

We study the mergeability of data summaries. Informally speaking, mergeability requires that, given two summaries on two datasets, there is a way to merge the two summaries into a single summary on the two datasets combined together, while preserving the error and size guarantees. This property m...

Baseline assessment of benthic communities of the Flower Garden Banks (2010 - 2013) using technical diving operations: 2011

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — The proposed work develop baseline information on fish and benthic communities within the Flower Garden Banks National Marine Sanctuary (FGBNMS). Surveys will employ...

Baseline assessment of fish communities of the Flower Garden Banks (2010 - 2013) using technical diving operations: 2011

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — The proposed work develop baseline information on fish and benthic communities within the Flower Garden Banks National Marine Sanctuary (FGBNMS). Surveys will employ...

Clinical Trial Results Summary for Laypersons: A User Testing Study.

Science.gov (United States)

Raynor, D K; Myers, L; Blackwell, K; Kress, B; Dubost, A; Joos, A

2018-01-01

To apply "user testing" to maximize readability and acceptability of a Clinical Trial Results Laypersons Summary-a new European requirement. "User testing" (using questionnaire and semistructured interview) assessed whether people could find and understand key points. Findings were used to improve content and design, prior to retesting. Participants had a range of levels of health literacy and there was a higher education group. Participants accessed the summary on screen. In round 1 we tested 12 points of information. In round 2 a revised summary addressing round 1 findings was tested, leading to a third final version. In round 1, 2 of 12 points of information did not reach the target and interviews raised further format and content issues (some distracting technical explanations and inability to find or understand the 2 main study purposes). These findings informed revisions for the version tested in round 2, with 2 different points not reaching the target (inclusion criteria relating to duration of seasonal allergies and how researchers found out about participants' symptoms). Identified problems in both rounds were addressed and reflected in the final version. Despite improvements, participants did not consistently understand that summaries were intended for the public, or to only interpret results of single trials in the context of additional trials. All readers, including those with higher education, found the clear and straightforward language acceptable. Applying "user testing" resulted in a largely health-literate summary suitable for people across a range of backgrounds.

Proceedings of the 18th technical meeting on nuclear reactor and radiation for KURRI engineers and the 9th technical official group section 5 meeting in Kyoto University

International Nuclear Information System (INIS)

2010-03-01

This report is a summary of 18th Technical Meeting on Nuclear Reactor and Radiation for KURRI Engineers in Kyoto University. This was also the 9th meeting for technical official group section 5 (nuclear and radiation) in Kyoto University. In the workshop, three special lectures held were: (1) 'On Border Between Subcritical and Supercritical', (2) 'Memories of Nuclear Power Plant Management for 40 Years', and (3) 'Introduction of Technical Office in Faculty of Engineering, Kyoto University'. The technical presentations held were: (1) 'Radiation Background Study of Specialty Products in Senshu Region', (2) 'Introduction of Radioactivation Analysis at KUR', (3) 'Consideration of Critical Approach Method for KUR Low-Enrichment Fuel Reactor Core Using SRAC', (4) 'Evaluation of Temperature Coefficient of KUR Low-Enrichment Fuel Reactor Core Using SRAC'. As training for technical staffs in Technical Office, we visited the facility in Ashiu Research Forest. An introduction of this facility and the comments from the participants were included in this report. (S.K.)

Biological and Chemical Technologies Research at OIT: Annual Summary Report, FY 1997

Energy Technology Data Exchange (ETDEWEB)

Peterson, G. [National Renewable Energy Lab. (NREL), Golden, CO (United States)

1998-03-01

The annual summary report presents the fiscal year (FY) 1 997 research activities and accomplishments for the United States Department of Energy (DOE) Biological and Chemical Technologies Research (BCTR) Program. This BCTR program resides within the Office of Industrial Technologies (OIT) of the Office of Energy Efficiency and Renewable Energy (EE). The annual summary report for 1997 (ASR 97) contains the following: program description (including BCTR program mission statement, historical background, relevance, goals and objectives); program structure and organization; selected technical and programmatic highlights for 1 997; detailed descriptions of individual projects; and a listing of program output, including a bibliography of published work, patents, and awards arising from work supported by the program.

Preferences on technical report format - Results of a survey

Science.gov (United States)

Pinelli, T. E.; Cordle, V. M.; Glassman, M.; Vondran, R. F.

1984-01-01

A survey of 513 engineers and scientists employed at the National Aeronautics and Space Administration Langley Research Center and 600 engineers and scientists from three professional/technical societies solicited the opinions of report users concerning the format of NASA technical reports. The results indicate that a summary as well as an abstract should be included, that the definitions of symbols and glossary of terms should be located in the front of the report, and that the illustrative material should be integrated with the text rather than grouped at the end of the report. Citation of references by number, one-column, ragged-right-margin layout, and third-person writing style are also preferred by a majority of the respondents.

Summary of breakout Session F1: F1, decision support systems - technical databases

International Nuclear Information System (INIS)

Anon.

1992-01-01

The discussions in breakout session F1 are summarized. The topics discussed include oil properties database, case histories database, technical experts database, sorbents database, dispersants database, equipment inventories, and response information. General comments and concerns were discussed and major research issues outlines

Summary report of the technical meeting on 'International Reactor Dosimetry File: IRDF-2002'

International Nuclear Information System (INIS)

Greenwood, L.R.; Paviotti-Corcuera, R.

2002-09-01

This report summarizes the presentations, recommendations and conclusions of the Technical Meeting on 'International Reactor Dosimetry File: IRDF-2002.' The purpose of this meeting was to discuss scientific and technical matters related to the subject and coordinate related tasks. Discussions were held and recommendations were given for the preparation of the files on topics related to: reactions to be included, need for new evaluations or revisions, decay data, radiation damage data, integral testing in benchmark fields, and computer codes to be included. Tasks were assigned and deadlines were set. The participants emphasized that accurate and complete knowledge of nuclear data for reactor dosimetry are essential for improving the accuracy of the reactor pressure vessel service life assessment of nuclear power plants as well as in other neutron metrology applications such as boron neutron capture therapy, therapeutic use of medical isotopes, nuclear physics measurements, and reactor safety applications. (author)

Executive Summary

International Nuclear Information System (INIS)

2013-01-01

countries (MC) and concerned both initial safety assessment of new facilities and reassessment of existing ones (periodic safety review). It also considered trends of future improvement of safety assessment techniques. The workshop was organised in an opening session, four technical sessions, one special session and a conclusion session. The technical sessions were focussed on: - General approach including human aspects (9 papers); - Front end facilities (5 papers); - Chemical hazards - release limits (6 papers); and - Back end facilities (6 papers). In addition, a special session (4 presentations) was held to discuss the lessons learnt for FCFs from the Fukushima accident in Japan. The workshop ended with an organized site visit to Cameco Corporation's Port Hope Conversion Facility in Port Hope, Ontario on the last day of the workshop. This paper presents the Summary of the technical and special sessions, the General Conclusions and Recommendation of the workshop and some future directions

Report on the IAEA technical meeting on network of nuclear reaction data centres

Energy Technology Data Exchange (ETDEWEB)

Schwerer, O [International Atomic Energy Agency, Nuclear Data Section, Vienna (Austria); Henriksson, H [NEA Data Bank, Issy-les-Moulineaux (France)

2005-01-15

This report summarizes the IAEA Technical Meeting on the Network of Nuclear Reaction Data Centres (biennial Data Centre Heads Meeting), held at the Brookhaven National Laboratory, Upton, NY, USA from 4-7 October 2004. The meeting was attended by 20 participants from 11 co-operating data centres of six Member States and two International Organizations. The report contains a summary of the meeting, the conclusions and actions, status reports of the participating data centres, and a revised technical protocol for the cooperation of the network. (author)

Report on the IAEA technical meeting on network of nuclear reaction data centres

International Nuclear Information System (INIS)

Schwerer, O.; Henriksson, H.

2005-01-01

This report summarizes the IAEA Technical Meeting on the Network of Nuclear Reaction Data Centres (biennial Data Centre Heads Meeting), held at the Brookhaven National Laboratory, Upton, NY, USA from 4-7 October 2004. The meeting was attended by 20 participants from 11 co-operating data centres of six Member States and two International Organizations. The report contains a summary of the meeting, the conclusions and actions, status reports of the participating data centres, and a revised technical protocol for the cooperation of the network. (author)

75 FR 48564 - Navigation and Navigable Waters; Technical, Organizational, and Conforming Amendments, Sector...

Science.gov (United States)

2010-08-11

... DEPARTMENT OF HOMELAND SECURITY Coast Guard 33 CFR Parts 3 and 165 [Docket No. USCG-2010-0351] RIN 1625-ZA25 Navigation and Navigable Waters; Technical, Organizational, and Conforming Amendments, Sector Columbia River, WA AGENCY: Coast Guard, DHS. ACTION: Final rule. SUMMARY: This rule makes non-substantive...

Global Nuclear Energy Partnership Waste Treatment Baseline

International Nuclear Information System (INIS)

Gombert, Dirk; Ebert, William; Marra, James; Jubin, Robert; Vienna, John

2008-01-01

The Global Nuclear Energy Partnership (GNEP) program is designed to demonstrate that a proliferation-resistant and sustainable integrated nuclear fuel cycle can be commercialized and used internationally. Alternative stabilization concepts for byproducts and waste streams generated by fuel recycling processes were evaluated and a baseline set of waste forms was recommended for the safe disposition of waste streams. Specific waste forms are recommended based on the demonstrated or expected commercial practicability and technical maturity of the processes needed to make the waste forms, and expected performance of the waste form materials when disposed. Significant issues remain in developing technologies to process some of the wastes into the recommended waste forms, and a detailed analysis of technology readiness may lead to the choice of a different waste form than what is recommended herein. Evolving regulations could also affect the selection of waste forms. (authors)

Global Nuclear Energy Partnership Waste Treatment Baseline

Energy Technology Data Exchange (ETDEWEB)

Gombert, Dirk; Ebert, William; Marra, James; Jubin, Robert; Vienna, John [Idaho National laboratory, 2525 Fremont Ave., Idaho Falls, ID 83402 (United States)

2008-07-01

The Global Nuclear Energy Partnership (GNEP) program is designed to demonstrate that a proliferation-resistant and sustainable integrated nuclear fuel cycle can be commercialized and used internationally. Alternative stabilization concepts for byproducts and waste streams generated by fuel recycling processes were evaluated and a baseline set of waste forms was recommended for the safe disposition of waste streams. Specific waste forms are recommended based on the demonstrated or expected commercial practicability and technical maturity of the processes needed to make the waste forms, and expected performance of the waste form materials when disposed. Significant issues remain in developing technologies to process some of the wastes into the recommended waste forms, and a detailed analysis of technology readiness may lead to the choice of a different waste form than what is recommended herein. Evolving regulations could also affect the selection of waste forms. (authors)

Global Nuclear Energy Partnership Waste Treatment Baseline

Energy Technology Data Exchange (ETDEWEB)

Dirk Gombert; William Ebert; James Marra; Robert Jubin; John Vienna

2008-05-01

The Global Nuclear Energy Partnership program (GNEP) is designed to demonstrate a proliferation-resistant and sustainable integrated nuclear fuel cycle that can be commercialized and used internationally. Alternative stabilization concepts for byproducts and waste streams generated by fuel recycling processes were evaluated and a baseline of waste forms was recommended for the safe disposition of waste streams. Waste forms are recommended based on the demonstrated or expected commercial practicability and technical maturity of the processes needed to make the waste forms, and performance of the waste form materials when disposed. Significant issues remain in developing technologies to process some of the wastes into the recommended waste forms, and a detailed analysis of technology readiness and availability may lead to the choice of a different waste form than what is recommended herein. Evolving regulations could also affect the selection of waste forms.

Technical committee meeting on aerosol formation, vapour deposits and sodium vapour trapping. Summary report

Energy Technology Data Exchange (ETDEWEB)

NONE

1977-01-01

The papers presented at the LMFBR meeting on aerosol formation covered the following four main topics: theoretical studies on aerosol behaviour and comparison with experimental results; techniques for measurement of aerosols; techniques for trapping sodium vapour and aerosols in gas circuits; design of components having to cope with aerosol deposits. The resulting summaries, conclusions and recommendations which were were agreed upon are presented.

Technical committee meeting on aerosol formation, vapour deposits and sodium vapour trapping. Summary report

International Nuclear Information System (INIS)

1977-01-01

The papers presented at the LMFBR meeting on aerosol formation covered the following four main topics: theoretical studies on aerosol behaviour and comparison with experimental results; techniques for measurement of aerosols; techniques for trapping sodium vapour and aerosols in gas circuits; design of components having to cope with aerosol deposits. The resulting summaries, conclusions and recommendations which were were agreed upon are presented

National briefing summaries: Nuclear fuel cycle and waste management

International Nuclear Information System (INIS)

Schneider, K.J.; Lakey, L.T.; Silviera, D.J.

1988-12-01

The National Briefing Summaries is a compilation of publicly available information concerning the nuclear fuel cycle and radioactive waste management strategies and programs of 21 nations, including the United States and three international agencies that have publicized their activities in this field. It presents available highlight information with references that may be used by the reader for additional information. The information in this document is compiled primarily for use by the US Department of Energy and other US federal agencies and their contractors to provide summary information on radioactive waste management activities in other countries. This document provides an awareness to managers and technical staff of what is occurring in other countries with regard to strategies, activities, and facilities. The information may be useful in program planning to improve and benefit United States' programs through foreign information exchange. Benefits to foreign exchange may be derived through a number of exchange activities

Nuclear data for the production of therapeutic radionuclides. Summary report of third research coordination meeting

International Nuclear Information System (INIS)

Sublet, J.-Ch.; Capote Noy, R.

2006-08-01

A summary is given of the Third Research Coordination Meeting on Nuclear Data for the Production of Therapeutic Radionuclides. The new library of evaluated cross-section will cover reactor and accelerator production of therapeutic radionuclides to appropriate specific activities and purity, along with the relevant decay data. A few new reactions were added at this meeting. Technical discussions and the resulting work plan to conclude the data evaluation activities are summarized for every reaction path. Timescales and agreed actions to deliver the database and Technical Report are also given. (author)

Co-Chairs’ Summary of Technical Session 3B. Nuclear Forensic Science: Synergies with Other Disciplines I

International Nuclear Information System (INIS)

Nizamska, M.; Roger, I.

2015-01-01

Scientific disciplines, including radiochemistry, provide a technical foundation for the science of nuclear forensics. In addition, analytical chemistry, pathology and nuclear material measurements all contribute to the technical spectrum encompassing a nuclear forensic capability. Subject matter experts versed in the former production of nuclear material may contribute to improved understanding of process streams of interest to a nuclear forensic examination

Methodology for teaching technical pattern of lying, sport shooting. Mistakes often.

Directory of Open Access Journals (Sweden)

Yaydel Avila Gómez

2011-09-01

Full Text Available The next album we set out a summary of the key technical elements for a good development of the prone position, bearing in mind that sometimes violate some methodological steps for teaching the same in athletes who play sports Shooting sports Rifle mode, which creates bad habits in the teaching of the position are difficult to eradicate later. We proceeded to perform the following steps. Criteria for experts to determine methodological steps to be taken into account in the teaching of technical pattern prone position; query bibliographic elements of the sport, the explanation of the basic technical elements; survey a group of coaches in the form of Rifle for the determination of the most common mistakes in the process of teaching the technical pattern of the prone position. It came to the conclusion that teaching the correct technical pattern that position must be taken into account methodological steps which do not allow making any error that would create a dynamic stereotype wrong in athletes who subsequently would be difficult to resolve.

Automatic generation of natural language nursing shift summaries in neonatal intensive care: BT-Nurse.

Science.gov (United States)

Hunter, James; Freer, Yvonne; Gatt, Albert; Reiter, Ehud; Sripada, Somayajulu; Sykes, Cindy

2012-11-01

Our objective was to determine whether and how a computer system could automatically generate helpful natural language nursing shift summaries solely from an electronic patient record system, in a neonatal intensive care unit (NICU). A system was developed which automatically generates partial NICU shift summaries (for the respiratory and cardiovascular systems), using data-to-text technology. It was evaluated for 2 months in the NICU at the Royal Infirmary of Edinburgh, under supervision. In an on-ward evaluation, a substantial majority of the summaries was found by outgoing and incoming nurses to be understandable (90%), and a majority was found to be accurate (70%), and helpful (59%). The evaluation also served to identify some outstanding issues, especially with regard to extra content the nurses wanted to see in the computer-generated summaries. It is technically possible automatically to generate limited natural language NICU shift summaries from an electronic patient record. However, it proved difficult to handle electronic data that was intended primarily for display to the medical staff, and considerable engineering effort would be required to create a deployable system from our proof-of-concept software. Copyright © 2012 Elsevier B.V. All rights reserved.

NEXT-100 Technical Design Report (TDR). Executive summary

International Nuclear Information System (INIS)

Álvarez, V; Cárcel, S; Cervera, A; Díaz, J; Ferrario, P; Borges, F I G M; Conde, C A N; Dias, T H V T; Fernandes, L M P; Carmona, J M; Castel, J; Cebrián, S; Dafni, T; Catalá, J M; Esteve, R; Chan, D; Egorov, M; Evtoukhovitch, P; Ferreira, A L; Ferrer-Ribas, E

2012-01-01

In this Technical Design Report (TDR) we describe the NEXT-100 detector that will search for neutrinoless double beta decay (ββ0ν) in 136 XE at the Laboratorio Subterráneo de Canfranc (LSC), in Spain. The document formalizes the design presented in our Conceptual Design Report (CDR): an electroluminescence time projection chamber, with separate readout planes for calorimetry and tracking, located, respectively, behind cathode and anode. The detector is designed to hold a maximum of about 150 kg of xenon at 15 bar, or 100 kg at 10 bar. This option builds in the capability to increase the total isotope mass by 50% while keeping the operating pressure at a manageable level. The readout plane performing the energy measurement is composed of Hamamatsu R11410-10 photomultipliers, specially designed for operation in low-background, xenon-based detectors. Each individual PMT will be isolated from the gas by an individual, pressure resistant enclosure and will be coupled to the sensitive volume through a sapphire window. The tracking plane consists in an array of Hamamatsu S10362-11-050P MPPCs used as tracking pixels. They will be arranged in square boards holding 64 sensors (8 × 8) with a 1-cm pitch. The inner walls of the TPC, the sapphire windows and the boards holding the MPPCs will be coated with tetraphenyl butadiene (TPB), a wavelength shifter, to improve the light collection.

NEXT-100 Technical Design Report (TDR). Executive summary

Science.gov (United States)

Álvarez, V.; Borges, F. I. G. M.; Cárcel, S.; Carmona, J. M.; Castel, J.; Catalá, J. M.; Cebrián, S.; Cervera, A.; Chan, D.; Conde, C. A. N.; Dafni, T.; Dias, T. H. V. T.; Díaz, J.; Egorov, M.; Esteve, R.; Evtoukhovitch, P.; Fernandes, L. M. P.; Ferrario, P.; Ferreira, A. L.; Ferrer-Ribas, E.; Freitas, E. D. C.; Gehman, V. M.; Gil, A.; Giomataris, I.; Goldschmidt, A.; Gómez, H.; Gómez-Cadenas, J. J.; González, K.; González-Díaz, D.; Gutiérrez, R. M.; Hauptman, J.; Hernando Morata, J. A.; Herrera, D. C.; Herrero, V.; Iguaz, F. J.; Irastorza, I. G.; Kalinnikov, V.; Kiang, D.; Labarga, L.; Liubarsky, I.; Lopes, J. A. M.; Lorca, D.; Losada, M.; Luzón, G.; Marí, A.; Martín-Albo, J.; Martínez, A.; Miller, T.; Moiseenko, A.; Monrabal, F.; Monteiro, C. M. B.; Monzó, J. M.; Mora, F. J.; Moutinho, L. M.; Muñoz Vidal, J.; Natal da Luz, H.; Navarro, G.; Nebot, M.; Nygren, D.; Oliveira, C. A. B.; Palma, R.; Pérez, J.; Pérez Aparicio, J. L.; Renner, J.; Ripoll, L.; Rodríguez, A.; Rodríguez, J.; Santos, F. P.; dos Santos, J. M. F.; Segui, L.; Serra, L.; Shuman, D.; Sofka, C.; Sorel, M.; Toledo, J. F.; Tomás, A.; Torrent, J.; Tsamalaidze, Z.; Vázquez, D.; Velicheva, E.; Veloso, J. F. C. A.; Villar, J. A.; Webb, R. C.; Weber, T.; White, J.; Yahlali, N.

2012-06-01

In this Technical Design Report (TDR) we describe the NEXT-100 detector that will search for neutrinoless double beta decay (ββ0ν) in 136XE at the Laboratorio Subterráneo de Canfranc (LSC), in Spain. The document formalizes the design presented in our Conceptual Design Report (CDR): an electroluminescence time projection chamber, with separate readout planes for calorimetry and tracking, located, respectively, behind cathode and anode. The detector is designed to hold a maximum of about 150 kg of xenon at 15 bar, or 100 kg at 10 bar. This option builds in the capability to increase the total isotope mass by 50% while keeping the operating pressure at a manageable level. The readout plane performing the energy measurement is composed of Hamamatsu R11410-10 photomultipliers, specially designed for operation in low-background, xenon-based detectors. Each individual PMT will be isolated from the gas by an individual, pressure resistant enclosure and will be coupled to the sensitive volume through a sapphire window. The tracking plane consists in an array of Hamamatsu S10362-11-050P MPPCs used as tracking pixels. They will be arranged in square boards holding 64 sensors (8 × 8) with a 1-cm pitch. The inner walls of the TPC, the sapphire windows and the boards holding the MPPCs will be coated with tetraphenyl butadiene (TPB), a wavelength shifter, to improve the light collection.

High-Level software requirements specification for the TWRS controlled baseline database system

International Nuclear Information System (INIS)

Spencer, S.G.

1998-01-01

This Software Requirements Specification (SRS) is an as-built document that presents the Tank Waste Remediation System (TWRS) Controlled Baseline Database (TCBD) in its current state. It was originally known as the Performance Measurement Control System (PMCS). Conversion to the new system name has not occurred within the current production system. Therefore, for simplicity, all references to TCBD are equivalent to PMCS references. This SRS will reference the PMCS designator from this point forward to capture the as-built SRS. This SRS is written at a high-level and is intended to provide the design basis for the PMCS. The PMCS was first released as the electronic data repository for cost, schedule, and technical administrative baseline information for the TAAS Program. During its initial development, the PMCS was accepted by the customer, TARS Business Management, with no formal documentation to capture the initial requirements

Summary report of the final technical meeting on 'International Reactor Dosimetry File: IRDF-2002'

International Nuclear Information System (INIS)

Griffin, Patrick J.; Paviotti-Corcuera, R.

2003-10-01

Presentations, recommendations and conclusions of the Final Technical Meeting on 'International Reactor Dosimetry File: IRDF-2002' are summarized in this report. The main aims of this meeting were to discuss scientific and technical matters related to reactor dosimetry and to assign responsibilities for the preparation of the final version of the IRDF- 2002 library and the associated TECDOC. Tasks were assigned and deadlines were agreed. Participants emphasized that accurate and complete nuclear data for reactor dosimetry are essential to improve the assessment accuracies for reactor pressure vessel service lifetimes in nuclear power plants, as well as for other neutron metrology applications such as boron neutron capture therapy, therapeutic use of medical isotopes, nuclear physics measurements, and reactor safety applications. (author)

BCTR: Biological and Chemical Technologies Research 1994 annual summary report

Energy Technology Data Exchange (ETDEWEB)

Petersen, G.

1995-02-01

The annual summary report presents the fiscal year (FY) 1994 research activities and accomplishments for the United States Department of Energy (DOE) Biological and Chemical Technologies Research (BCTR) Program of the Advanced Industrial Concepts Division (AICD). This AICD program resides within the Office of Industrial Technologies (OIT) of the Office of Energy Efficiency and Renewable Energy (EE). Although the OIT was reorganized in 1991 and AICD no longer exists, this document reports on efforts conducted under the former structure. The annual summary report for 1994 (ASR 94) contains the following: program description (including BCTR program mission statement, historical background, relevance, goals and objectives); program structure and organization, selected technical and programmatic highlights for 1994; detailed descriptions of individual projects; a listing of program output, including a bibliography of published work; patents, and awards arising from work supported by BCTR.

77 FR 37390 - Notice Inviting Informal Public Comment on Training and Technical Assistance and Disability...

Science.gov (United States)

2012-06-21

... and Technical Assistance and Disability Inclusion Programming AGENCY: Corporation for National and... Disability Inclusion Programming; correction. SUMMARY: The Corporation for National and Community Service... Disability Inclusion Programming that appeared in the Federal Register of June 11, 2012 (75 FR 34354). That...

School-to-Work Transition of Career and Technical Education Graduates

Science.gov (United States)

Packard, Becky Wai-Ling; Leach, Miki; Ruiz, Yedalis; Nelson, Consuelo; DiCocco, Hannah

2012-01-01

This study analyzed the career development of career and technical education (CTE) high school graduates during their school-to-work transition, specifically their adaptability in the face of barriers. Forty graduates (22 men, 18 women) from working-class backgrounds participated in baseline surveys at graduation and phenomenological interviews 1…

Summaries of studies carried out in the NKS/BOK-2 project. Technical report[Radiological and environmental consequences

Energy Technology Data Exchange (ETDEWEB)

Palsson, S E [Icelandic Radiation Protection Inst., Reykjavik (Iceland)

2002-12-01

Summaries of studies carried out in the NKSBOK-2 project, Radiological and Environmental Consequences. The structure of the project as such is described in NKS-64, Radiological and Environmental Consequences - Final Report of the Nordic Nuclear Safety Research Project BOK-2. That report also includes compilations based on the summaries presented in this report. The project was carried out 1998-2001 with participants from all the Nordic countries. Representatives from the Baltic States were also invited to some of the meetings and seminars. The project consisted of work on terrestrial and marine radioecology and had a broad scope in order to enable participation of research groups with various fields of interest. The topics included improving assessment of old and recent fallout, use of radionuclides as tracers in Nordic marine areas, improving assessment of internal doses and use of mass spectrometry in radioecology. This report is a compilation of summaries from each research group, 32 papers in all, and gives references to papers published in scientific journals. Some of the studies have been described previously, at least to some degree, in NKS-70, Proceedings of the 8{sup th} Nordic Seminar on Radioecology, 25-28 February 2001, Rovaniemi, Finland. (au)

Energy Materials Coordinating Committee (EMaCC): Annual technical report, fiscal year 1993

Energy Technology Data Exchange (ETDEWEB)

1994-07-01

The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department`s materials programs and to further effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. In addition, EMaCC assists in obtaining materials-related inputs for both intra- and interagency compilations. This report summarizes EMaCC activities for FY 1993 and describes the materials research programs of various offices and divisions within the Department. The program descriptions consist of a funding summary for each Assistant Secretary office and the Office of Energy Research, and detailed project summaries with project goals and accomplishments. The FY 1993 budget summary table for DOE Materials Activities in each of the programs is presented.

Fuel Assembly Damping Summary

Energy Technology Data Exchange (ETDEWEB)

Lee, Kanghee; Kang, Heungseok; Oh, Dongseok; Yoon, Kyungho; Kim, Hyungkyu; Kim, Jaeyong [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2013-10-15

This paper summary the fuel assembly damping data in air/in still water/under flow, released from foreign fuel vendors, compared our data with the published data. Some technical issues in fuel assembly damping measurement testing are also briefly discussed. Understanding of each fuel assembly damping mechanisms according to the surrounding medium and flow velocity can support the fuel design improvement in fuel assembly dynamics and structural integrity aspect. Because the upgraded requirements of the newly-developed advanced reactor system will demands to minimize fuel design margin in integrity evaluation, reduction in conservatism of fuel assembly damping can contribute to alleviate the fuel design margin for sure. Damping is an energy dissipation mechanism in a vibrating mechanical structure and prevents a resonant structure from having infinite vibration amplitudes. The sources of fuel assembly damping are various from support friction to flow contribution, and it can be increased by the viscosity or drag of surrounding fluid medium or the average velocity of water flowing. Fuel licensing requires fuel design evaluation in transient or accidental condition. Dynamic response analysis of fuel assembly is to show fuel integrity and requires information on assembly-wise damping in dry condition and under wet or water flowing condition. However, damping measurement test for the full-scale fuel assembly prototype is not easy to carry out because of the scale (fuel prototype, test facility), unsteadiness of test data (scattering, random sampling and processing), instrumentation under water flowing (water-proof response measurement), and noise. LWR fuel technology division in KAERI is preparing the infra structure for damping measurement test of full-scale fuel assembly, to support fuel industries and related research activities. Here is a preliminary summary of fuel assembly damping, published in the literature. Some technical issues in fuel assembly damping

Project summary plan for HTGR recycle reference facility

International Nuclear Information System (INIS)

Baxter, B.J.

1979-11-01

A summary plan is introduced for completing conceptual definition of an HTGR Recycle Reference Facility (HRRF). The plan describes a generic project management concept, often referred to as the requirements approach to systems engineering. The plan begins with reference flow sheets and provides for the progressive evolution of HRRF requirements and definition through feasibility, preconceptual, and conceptual phases. The plan lays end-to-end all the important activities and elements to be treated during each phase of design. Identified activities and elements are further supported by technical guideline documents, which describe methodology, needed terminology, and where relevant a worked example

National briefing summaries: Nuclear fuel cycle and waste management

Energy Technology Data Exchange (ETDEWEB)

Schneider, K.J.; Lakey, L.T.; Silviera, D.J.

1988-12-01

The National Briefing Summaries is a compilation of publicly available information concerning the nuclear fuel cycle and radioactive waste management strategies and programs of 21 nations, including the United States and three international agencies that have publicized their activities in this field. It presents available highlight information with references that may be used by the reader for additional information. The information in this document is compiled primarily for use by the US Department of Energy and other US federal agencies and their contractors to provide summary information on radioactive waste management activities in other countries. This document provides an awareness to managers and technical staff of what is occurring in other countries with regard to strategies, activities, and facilities. The information may be useful in program planning to improve and benefit United States' programs through foreign information exchange. Benefits to foreign exchange may be derived through a number of exchange activities.

Use of computational fluid dynamics codes for safety analysis of nuclear reactor systems, including containment. Summary report of a technical meeting

International Nuclear Information System (INIS)

2003-11-01

Safety analysis is an important tool for justifying the safety of nuclear power plants. Typically, this type of analysis is performed by means of system computer codes with one dimensional approximation for modelling real plant systems. However, in the nuclear area there are issues for which traditional treatment using one dimensional system codes is considered inadequate for modelling local flow and heat transfer phenomena. There is therefore increasing interest in the application of three dimensional computational fluid dynamics (CFD) codes as a supplement to or in combination with system codes. There are a number of both commercial (general purpose) CFD codes as well as special codes for nuclear safety applications available. With further progress in safety analysis techniques, the increasing use of CFD codes for nuclear applications is expected. At present, the main objective with respect to CFD codes is generally to improve confidence in the available analysis tools and to achieve a more reliable approach to safety relevant issues. An exchange of views and experience can facilitate and speed up progress in the implementation of this objective. Both the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency of the Organisation for Economic Co-operation and Development (OECD/NEA) believed that it would be advantageous to provide a forum for such an exchange. Therefore, within the framework of the Working Group on the Analysis and Management of Accidents of the NEA's Committee on the Safety of Nuclear Installations, the IAEA and the NEA agreed to jointly organize the Technical Meeting on the Use of Computational Fluid Dynamics Codes for Safety Analysis of Reactor Systems, including Containment. The meeting was held in Pisa, Italy, from 11 to 14 November 2002. The publication constitutes the report of the Technical Meeting. It includes short summaries of the presentations that were made and of the discussions as well as conclusions and

Plutonium focus area: Technology summary

International Nuclear Information System (INIS)

1996-03-01

To ensure research and development programs focus on the most pressing environmental restoration and waste management problems at the U.S. Department of Energy (DOE), the Assistant Secretary for the Office of Environmental Management (EM) established a working group in August 1993 to implement a new approach to research and technology development. As part of this approach, EM developed a management structure and principles that led to creation of specific focus areas. These organizations were designed to focus scientific and technical talent throughout DOE and the national scientific community on major environmental restoration and waste management problems facing DOE. The focus area approach provides the framework for inter-site cooperation and leveraging of resources on common problems. After the original establishment of five major focus areas within the Office of Technology Development (EM-50), the Nuclear Materials Stabilization Task Group (NMSTG, EM-66) followed EM-50's structure and chartered the Plutonium Focus Area (PFA). NMSTG's charter to the PFA, described in detail later in this book, plays a major role in meeting the EM-66 commitments to the Defense Nuclear Facilities Safety Board (DNFSB). The PFA is a new program for FY96 and as such, the primary focus of revision 0 of this Technology Summary is an introduction to the Focus Area; its history, development, and management structure, including summaries of selected technologies being developed. Revision 1 to the Plutonium Focus Area Technology Summary is slated to include details on all technologies being developed, and is currently planned for release in August 1996. The following report outlines the scope and mission of the Office of Environmental Management, EM-60, and EM-66 organizations as related to the PFA organizational structure

Using the baseline environmental management report (BEMR) to examine alternate program scenarios

International Nuclear Information System (INIS)

Kristofferson, K.

1995-01-01

The US Department of Energy's (DOE) Office of Environmental Management (EM) released the first Baseline Environmental Management Report (BEMR) in March, 1995. The Congressionally-mandated report provides life-cycle cost estimates, tentative schedules, and projected activities necessary to complete DOE's Environmental Management Program. This ''base case'' estimate is based on current program assumptions and the most likely set of activities. However, since the future course of the Environmental Management Program depends upon a number of fundamental technical and policy choices, alternate program scenarios were developed. These alternate cases show the potential cost impacts of changing assumptions in four key areas: future land use, program funding and scheduling, technology development, and waste management configurations. Several cost and program evaluation tools were developed to support the analysis of these alternate cases. The objective of this paper is to describe the analytical tool kit developed to support the development of the 1995 Baseline Report and to discuss the application of these tools to evaluate alternate program scenarios

Corrective action baseline report for underground storage tanks 0439-U, 0440-U, 2073-U, 2074-U, and 2075-U at the East End Fuel Station, Buildings 9754 and 9754-2, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee, Facility ID No. 0-010117

International Nuclear Information System (INIS)

1994-01-01

The purpose of this report is to provide baseline geochemical and hydrogeologic data relative to corrective action for underground storage tanks (USTs) 0439-U, 0440-U, 2073-U, 2074-U, and 2075-U at the East End Fuel Station, Buildings 9754 and 9754-2 at the Oak Ridge Y-12 Plant. Progress in support of corrective action at the East End Fuel Station has included monitoring well installation, tank removal, and baseline groundwater sampling and analysis. This document represents the baseline report for corrective action at the East End Fuel Station and is organized into three sections. Section 1 presents introductory information relative to the site, including the regulatory initiative, site description, and progress to date. Section 2 includes a summary of additional monitoring well installation activities, the results of baseline groundwater sampling, a summary of tank removal activities, and the results of confirmatory soil sampling performed during tank removal. Section 3 presents the baseline hydrogeology and planned zone of influence for groundwater remediation

Technical aspects of atomic and molecular data processing and exchange. 19. meeting of the A+M Data Centres and ALADDIN Network. Summary report of an IAEA technical meeting

International Nuclear Information System (INIS)

Humbert, D.

2008-05-01

The proceedings of the IAEA Technical Meeting on Technical Aspects of Atomic and Molecular Data Processing and Exchange (19th Meeting of A+M Data Centres and ALADDIN Network), held on 3-5 October, 2007 in Vienna, Austria, are briefly described. Conclusions and recommendations are presented concerning various proposed projects and their priorities involving A+M data compilation and evaluation and technical aspects of data processing, exchange, and distribution. (author)

GRI baseline projection of U.S. Energy supply and demand to 2010. 1991 edition

International Nuclear Information System (INIS)

Holtberg, P.D.; Woods, T.J.; Lihn, M.L.; McCabe, N.C.

1991-04-01

The report summarizes the 1991 Edition of the GRI Baseline Projection of U.S. Energy Supply and Demand and presents a series of summary tables, sectoral breakdowns of energy demand, and the natural gas supply and price trends. Appendixes include a discussion of the methodology and assumptions used to prepare the 1991 projection, a brief discussion of the potential for higher levels of gas demand, a description of industrial and commercial cogeneration, a description of the independent power producer (IPP) methodology and projection, a comparison of the 1991 edition with previous projections, and a discussion of additional data used in developing the projection

Patrick Air Force Base integrated resource assessment. Volume 2, Baseline detail

Energy Technology Data Exchange (ETDEWEB)

Wahlstrom, R.R.; King, D.A.; Parker, S.A.; Sandusky, W.F.

1993-08-01

The US Air Force has tasked the Pacific Northwest Laboratory (PNL), in support of the US Department of Energy (DOE) Federal Energy Management Program (FEMP), to assess energy use at Patrick Air Force Base (AFB). The information obtained from this assessment will be used in identifying energy resource opportunities to reduce overall energy consumption on the base. The primary focus of this report is to assess the current baseline energy consumption at Patrick AFB. It is a comparison report to Volume 1, the Executive Summary, and Volume 3, the Resource Assessment. This assessment requires that information be obtained and characterized for buildings, utilities, energy sources, energy uses, and load profile information to be used to improve the characterization of energy use on the base. The characteristics of electricity, natural gas, and No. 2 fuel oil are analyzed for on-base facilities and housing. The assessment examines basic regional information used to determine energy-use intensity (EUI) values for Patrick AFB facilities by building, fuel type, and energy end use. It also provides a summary of electricity consumption from Florida Power and Light Company (FPL) metered data for 1985-1991. Load profile information obtained from FPL data is presented for the north and south substations for the four seasons of the year, including weekdays and weekends.

Risk-based analysis methods applied to nuclear power plant technical specifications

International Nuclear Information System (INIS)

Wagner, D.P.; Minton, L.A.; Gaertner, J.P.

1989-01-01

A computer-aided methodology and practical applications of risk-based evaluation of technical specifications are described. The methodology, developed for use by the utility industry, is a part of the overall process of improving nuclear power plant technical specifications. The SOCRATES computer program uses the results of a probabilistic risk assessment or a system-level risk analysis to calculate changes in risk due to changes in the surveillance test interval and/or the allowed outage time stated in the technical specification. The computer program can accommodate various testing strategies (such as staggered or simultaneous testing) to allow modeling of component testing as it is carried out at the plant. The methods and computer program are an integral part of a larger decision process aimed at determining benefits from technical specification changes. These benefits can include cost savings to the utilities by reducing forced shutdowns and decreasing labor requirements for test and maintenance activities, with no adverse impacts on risk. The methodology and the SOCRATES computer program have been used extensively toe valuate several actual technical specifications in case studies demonstrating the methods. Summaries of these applications demonstrate the types of results achieved and the usefulness of the risk-based evaluation in improving the technical specifications

Co-ordination of the international network of nuclear structure and decay data evaluators. Summary report of an IAEA technical meeting

Energy Technology Data Exchange (ETDEWEB)

Pronyaev, V G; Nichols, A L; Tuli, J [eds.

2004-03-01

The IAEA Nuclear Data Section convened the 15th meeting of the Network of Nuclear Structure and Decay Data Evaluators at the IAEA Headquarters, Vienna, 10-14 November 2003. This meeting was attended by 23 scientists from 11 Member States concerned with the compilation, evaluation and dissemination of nuclear structure and decay data. A summary of the meeting, the recommendations, data centre reports and the various proposals considered, modified and agreed by the participants are contained within this document. Nuclear data are essential to the development, implementation and maintenance of all nuclear technologies. The international network of Nuclear Structure and Decay Data (NSDD) Evaluators is sponsored by the IAEA, and consists of evaluation groups and data service centers in several countries. This network has the objective of providing up-to-date nuclear structure and decay data for all known nuclides by evaluating all existing experimental data. Data resulting from this international evaluation collaboration is included in the Evaluated Nuclear Structure Data File (ENSDF) and published in the journals Nuclear Physics A and Nuclear Data Sheets. The results represent the recommended 'best values' for the various nuclear structure and decay data parameters. Recommended values are made available to users by means of various media, such as the world wide web, CD-ROMs, wall charts of the nuclides, handbooks, nuclear wallet cards and others. Participants discussed a wide range of technical matters, and the recommendations of improving the quality of NSDD evaluations. A list of actions was also prepared for implementation during the course of the next two years. NSDD members prepared many recommendations for the IAEA and the major evaluation centers, which are aimed at improving the technical support towards the network and streamlining the organization of work. These consensus conclusions include: the development and exchange of programming products; revision of

Proceedings of the IEA-technical workshop for an international fusion materials irradiation facility. IEA-implementing agreement for a programme of research and development on fusion materials

International Nuclear Information System (INIS)

Ehrlich, K.; Lindau, R.

1995-07-01

The workshop was initiated to deal with the following objectives: (1) Critical review of the requirements for IFMIF from the user's point of view; (2) Definition of a baseline concept for the CDA-study; (3) Formation of working groups for main fields of activities; (4) Identification of tasks and critical issues for main components; (5) Development of a working break-down structure, distribution of work and milestones for CDA-activities; (6) Documentation of main results. According to the enclosed agenda the mission for a Conceptual Design Study, the requirements for an intense neutron source from the user's point of view and the baseline concept for an accelerator-driven D-Li neutron source were discussed in several plenary sessions. In three subgroups (SG 1 Accelerators, SG2 Lithium Target and SG3 Users and Test Cell) technical concepts for the different components and facilities were discussed in detail, critical issues and tasks for the concept study were identified. Finally, the sharing of tasks to the different national parties, questions of organisation of the work, flow of information and definition of milestones was agreed upon. The detailled summary reports of the subgroups and the contributions of the plenary sessions are presented in the proceedings. (orig./HP)

Report on the IAEA Technical Meeting of the International Network of Nuclear Reaction Data Centres

International Nuclear Information System (INIS)

Forrest, R.; Dunaeva, S.; Otsuka, N.

2010-07-01

This report summarizes the IAEA Technical Meeting of the International Network of Nuclear Reaction Data Centres (biennial Data Centre Heads Meeting), held at the Japan Nuclear Reaction Data Centre, Hokkaido University, Sapporo, Japan, from 20 - 23 April 2010. The meeting was attended by 27 participants from 12 cooperating data centres of seven Member States and two International Organizations. The report contains a summary of the meeting, the conclusions and actions, the lists of working papers and presentations presented at the meeting. This report summarizes the IAEA Technical Meeting of the International Network of Nuclear Reaction Data Centres (biennial Data Centre Heads Meeting), held at the Japan Nuclear Reaction Data Centre, Hokkaido University, Sapporo, Japan, from 20 - 23 April 2010. The meeting was attended by 27 participants from 12 cooperating data centres of seven Member States and two International Organizations. The report contains a summary of the meeting, the conclusions and actions, the lists of working papers and presentations presented at the meeting. (author)

Strategy for the future use and disposition of uranium-233: Technical information

International Nuclear Information System (INIS)

Bereolos, P.J.; Forsberg, C.W.; Kocher, D.C.; Krichinsky, A.M.

1998-04-01

This document provides a summary of technical information on the synthetic radioisotope 233 U. It is one of a series of four reports that map out a national strategy for the future use and disposition of 233 U. The technical information on 233 U in this document falls into two main areas. First, material characteristics are presented along with the contrasts of 233 U to the more well known strategic fissile materials, 235 U and plutonium (Pu). Second, information derived from the scientific information, such as safeguards, waste classifications, material form, and packaging, is presented. Throughout, the effects of isotopically diluting 233 U with nonfissile, depleted uranium (DU) are examined

SIMS study on statistics and environmental factors in health. Final technical report to Department of Energy

International Nuclear Information System (INIS)

1982-07-01

This final technical report to DOE consists of five individual technical reports and one working paper by members of the SIMS Study at Stanford. Research topics include testing goodness-of-fit for the distribution of errors in regression models, mathematical models of cancer and their use in risk assessment, pollutant standards index (Psi), osteosarcomas among beagles exposed to 239 Plutonium, air pollution and respiratory disease, and models of human exposure to air pollution. Individual summaries of the six reports are indexed separately

Evaluation of Routine Atmospheric Sounding Measurements using Unmanned Systems (ERASMUS): Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

de Boer, Gijs [Univ. of Colorado, Boulder, CO (United States); Lawrence, Dale [Univ. of Colorado, Boulder, CO (United States); Palo, Scott [Univ. of Colorado, Boulder, CO (United States); Argrow, Brian [Univ. of Colorado, Boulder, CO (United States); LoDolce, Gabriel [Univ. of Colorado, Boulder, CO (United States); Curry, Nathan [Univ. of Colorado, Boulder, CO (United States); Weibel, Douglas [Univ. of Colorado, Boulder, CO (United States); Finamore, William [Univ. of Colorado, Boulder, CO (United States); D' Amore, Phillip [Univ. of Colorado, Boulder, CO (United States); Borenstein, Steven [Univ. of Colorado, Boulder, CO (United States); Nichols, Tevis [Univ. of Colorado, Boulder, CO (United States); Elston, Jack [Blackswift Technologies, Boulder, CO (United States); Ivey, Mark [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Bendure, Albert [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Schmid, Beat [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Long, Charles [Univ. of Colorado, Boulder, CO (United States); Telg, Hagen [Univ. of Colorado, Boulder, CO (United States); Gao, Ru-Shan [National Oceanic and Atmospheric Administration (NOAA), Boulder, CO (United States); Hock, Terry [National Center for Atmospheric Research, Boulder, CO (United States); Bland, Geoff [NASA Ames Research Center (ARC), Moffett Field, Mountain View, CA (United States)

2017-03-29

This final technical report details activities undertaken as part of the referenced project. Included is information on the preparation of aircraft for deployment to Alaska, summaries of the three deployments covered under this project, and a brief description of the dataset and science directions pursued. Additionally, we provide information on lessons learned, publications, and presentations resulting from this work.

Gradual linguistic summaries

NARCIS (Netherlands)

Wilbik, A.M.; Kaymak, U.; Laurent, A.; Strauss, O.; Bouchon-Meunier, xx

2014-01-01

In this paper we propose a new type of protoform-based linguistic summary – the gradual summary. This new type of summaries aims in capturing the change over some time span. Such summaries can be useful in many domains, for instance in economics, e.g., "prices of X are getting smaller" in eldercare,

Hydrogen Energy Coordinating Committee annual report: Summary of DOE hydrogen programs for FY 1991

International Nuclear Information System (INIS)

1991-07-01

The HECC was established over 13 years ago to ensure that the many varied aspects of hydrogen technology within the Department are coordinated. Each year the committee brings together technical representative within the Department to coordinate activities, share research results and discuss future priorities and directions. This FY 1990 summary is the thirteenth consecutive yearly report. It provides an overview of the hydrogen-related programs of the DOE offices represented in the HECC for the fiscal year. For the purposes of this report, the research projects within each division have been organized into two categories: Fuels-related Research and Non-fuels-related Research. An historical summary of the hydrogen budgets of the several divisions is given. Total DOE funding in FY 1990 was $6.8 million for fuels-related research and $32.9 million for non-fuels-related research. The individual program elements are described in the body of this report, and more specific program information can be found in the Technology Summary Forms in Appendix A

78 FR 33416 - Notification of a Public Meeting of the Science Advisory Board Environmental Justice Technical...

Science.gov (United States)

2013-06-04

... ENVIRONMENTAL PROTECTION AGENCY [FRL--9819-3] Notification of a Public Meeting of the Science... Agency (EPA). ACTION: Notice. SUMMARY: The EPA Science Advisory Board (SAB) Staff Office announces a public meeting of the SAB Environmental Justice Technical Guidance Review Panel to provide advice through...

Policy implications of the GRI baseline projection of US energy supply and demand to 2010, 1993

International Nuclear Information System (INIS)

1993-01-01

The paper summarizes the 1993 edition of the Gas Research Institute (GRI) Baseline Projection of U.S. Energy Supply and Demand, and presents the implications of the projection that are important for GRI research and development planning and the gas industry. The survey of supply and demand considerations is followed by a breakdown of energy demand by type of fuel, by consumption sector, and by service application. Gas supply and prices are analyzed in terms of two scenarios: a constrained energy demand scenario, and an optimistic scenario. Tables and charts accompany the summary

Iowa Hill Pumped Storage Project Investigations - Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

Hanson, David [Sacramento Municipal Unitlity District, Sacramento, CA (United States)

2016-07-01

This Final Technical Report is a summary of the activities and outcome of the Department of Energy (DOE) Assistance Agreement DE-EE0005414 with the Sacramento Municipal Utility District (SMUD). The Assistance Agreement was created in 2012 to support investigations into the Iowa Hill Pumped-storage Project (Project), a new development that would add an additional 400 MW of capacity to SMUD’s existing 688MW Upper American River Hydroelectric Project (UARP) in the Sierra Nevada mountains east of Sacramento, California.

A Summary of NORA Project Results Related to Reactivity Measurements

International Nuclear Information System (INIS)

Berg, J.O.; Døderlein, J-M-; Haugset, K

1969-01-01

The NORA Project has been an international undertaking within the field of reactor physics, resulting from an agreement signed by the International Atomic Energy Agency and the Norwegian Government in April 1961, and subsequently renewed for three years in 1964 and one year in 1967. A summary of the research performed in the period 1961-1964 has been published in IAEA Technical Report Series no. 67. The Project work carried out through the years 1964-1968 will be covered in a forthcoming IAEA Technical Report. The main experimental facility used in the Project has been the zero-power reactor NORA Reactor kinetics, both experimental end theoretical, has been a major item of research in the NORA Project. The present report will briefly summarize results and conclusions considered relevant to the topic discussed by this Panel. Extensive referencing will be made to the final NORA Project Report

Technical progress report, 1 April-30 June 1981

Energy Technology Data Exchange (ETDEWEB)

None

1981-01-01

This report describes the technical accomplishments during the quarter ending June 1981, on the commercial nuclear waste management programs under the direction of the Office of Nuclear Waste Isolation (ONWI). The ONWI program is organized into 8 tasks entitled: systems, waste package, site, repository, regulatory and institutional, test facilities and excavations, land acquisition, and program management. Principal investigators in each of these areas have submitted summaries of quarterly highlights for inclusion in this report. Separate abstracts have been prepared for 5 of these tasks for inclusion in the Energy Data Base. (DMC)

Eighth ITER technical meeting on safety and environment

International Nuclear Information System (INIS)

Gordon, C.; Raeder, J.

2000-01-01

From November 27 to 30, 2000 the Eighth ITER Technical Meeting on Safety and Environment was held by the ITER Joint Central Team (JCT) at the Garching Joint Work Site, which also hosts the ITER Safety, Environment and Health Group (SEHG). At this meeting, safety experts from the Home Teams (HT) worked together with the SEHG members towards the following main objectives: review of Generic Site Safety Report (GSSR) results and drafts; review of the Plant Design Description (PDD) summary of safety; update on the status of the R and D tasks contributing to GSSR

Summary report on first research coordination meeting on heavy charged-particle interaction data for radiotherapy

International Nuclear Information System (INIS)

Palmans, H.; Noy, R.C.

2008-04-01

A summary is given of the First Research Coordination Meeting on Heavy Charged-Particle Interaction Data for Radiotherapy. A programme to compile and evaluate charged-particle nuclear data for therapeutic applications was proposed. Detailed coordinated research proposals were also agreed. Technical discussions and the resulting work plan of the Coordinated Research Project are summarized, along with actions and deadlines. (author)

Baseline design/economics for advanced Fischer-Tropsch technology. Quarterly report, January--March 1992

Energy Technology Data Exchange (ETDEWEB)

1992-09-01

The objectives of the study are to: Develop a baseline design for indirect liquefaction using advanced Fischer-Tropsch (F-T) technology. Prepare the capital and operating costs for the baseline design. Develop a process flow sheet simulation (PFS) model. This report summarizes the activities completed during the period December 23, 1992 through March 15, 1992. In Task 1, Baseline Design and Alternates, the following activities related to the tradeoff studies were completed: approach and basis; oxygen purity; F-T reactor pressure; wax yield; autothermal reformer; hydrocarbons (C{sub 3}/C{sub 4}s) recovery; and hydrogenrecovery. In Task 3, Engineering Design Criteria, activities were initiated to support the process tradeoff studies in Task I and to develop the environmental strategy for the Illinois site. The work completed to date consists of the development of the F-T reactor yield correlation from the Mobil dam and a brief review of the environmental strategy prepared for the same site in the direct liquefaction baseline study.Some work has also been done in establishing site-related criteria, in establishing the maximum vessel diameter for train sizing and in coping with the low H{sub 2}/CO ratio from the Shell gasifier. In Task 7, Project Management and Administration, the following activities were completed: the subcontract agreement between Amoco and Bechtel was negotiated; a first technical progress meeting was held at the Bechtel office in February; and the final Project Management Plan was approved by PETC and issued in March 1992.

The US Department of Energy hydrogen baseline survey: assessing knowledge and opinions about hydrogen technology

International Nuclear Information System (INIS)

Christy Cooper; Tykey Truett; R L Schmoyer

2006-01-01

To design and maintain its education program, the United States Department of Energy (DOE) Hydrogen Program conducted a statistically-valid national survey to measure knowledge and opinions of hydrogen among key target audiences. The Hydrogen Baseline Knowledge Survey provides a reference for designing the DOE hydrogen education strategy and will be used in comparisons with future surveys to measure changes in knowledge and opinions over time. The survey sampled four U.S. populations: (1) public; (2) students; (3) state and local government officials; and (4) potential large-scale hydrogen end-users in three business categories. Questions measured technical understanding of hydrogen and opinions about hydrogen safety. Other questions assessed visions of the likelihood of future hydrogen applications and sources of energy information. Several important findings were discovered, including a striking lack of technical understanding across all survey groups, as well as a strong correlation between technical knowledge and opinions about safety: those who demonstrated an understanding of hydrogen technologies expressed the least fear of its safe use. (authors)

The baseline pressure of intracranial pressure (ICP) sensors can be altered by electrostatic discharges.

Science.gov (United States)

Eide, Per K; Bakken, André

2011-08-22

The monitoring of intracranial pressure (ICP) has a crucial role in the surveillance of patients with brain injury. During long-term monitoring of ICP, we have seen spontaneous shifts in baseline pressure (ICP sensor zero point), which are of technical and not physiological origin. The aim of the present study was to explore whether or not baseline pressures of ICP sensors can be affected by electrostatics discharges (ESD's), when ESD's are delivered at clinically relevant magnitudes. We performed bench-testing of a set of commercial ICP sensors. In our experimental setup, the ICP sensor was placed in a container with 0.9% NaCl solution. A test person was charged 0.5-10 kV, and then delivered ESD's to the sensor by touching a metal rod that was located in the container. The continuous pressure signals were recorded continuously before/after the ESD's, and the pressure readings were stored digitally using a computerized system A total of 57 sensors were tested, including 25 Codman ICP sensors and 32 Raumedic sensors. When charging the test person in the range 0.5-10 kV, typically ESD's in the range 0.5-5 kV peak pulse were delivered to the ICP sensor. Alterations in baseline pressure ≥ 2 mmHg was seen in 24 of 25 (96%) Codman sensors and in 17 of 32 (53%) Raumedic sensors. Lasting changes in baseline pressure > 10 mmHg that in the clinical setting would affect patient management, were seen frequently for both sensor types. The changes in baseline pressure were either characterized by sudden shifts or gradual drifts in baseline pressure. The baseline pressures of commercial solid ICP sensors can be altered by ESD's at discharge magnitudes that are clinically relevant. Shifts in baseline pressure change the ICP levels visualised to the physician on the monitor screen, and thereby reveal wrong ICP values, which likely represent a severe risk to the patient.

Argonne National Laboratory summary site environmental report for calendar year 2007.

Energy Technology Data Exchange (ETDEWEB)

Golchert, N. W.

2009-05-22

This summary of Argonne National Laboratory's Site Environmental Report for calendar year 2007 was written by 20 students at Downers Grove South High School in Downers Grove, Ill. The student authors are classmates in Mr. Howard's Bio II course. Biology II is a research-based class that teaches students the process of research by showing them how the sciences apply to daily life. For the past seven years, Argonne has worked with Biology II students to create a short document summarizing the Site Environmental Report to provide the public with an easy-to-read summary of the annual 300-page technical report on the results of Argonne's on-site environmental monitoring program. The summary is made available online and given to visitors to Argonne, researchers interested in collaborating with Argonne, future employees, and many others. In addition to providing Argonne and the public with an easily understandable short summary of a large technical document, the participating students learn about professional environmental monitoring procedures, achieve a better understanding of the time and effort put forth into summarizing and publishing research, and gain confidence in their own abilities to express themselves in writing. The Argonne Summary Site Environmental Report fits into the educational needs for 12th grade students. Illinois State Educational Goal 12 states that a student should understand the fundamental concepts, principles, and interconnections of the life, physical, and earth/space sciences. To create this summary booklet, the students had to read and understand the larger technical report, which discusses in-depth many activities and programs that have been established by Argonne to maintain a safe local environment. Creating this Summary Site Environmental Report also helps students fulfill Illinois State Learning Standard 12B5a, which requires that students be able to analyze and explain biodiversity issues, and the causes and effects of

Revised CDM baseline study on fuel use and manure management at household level

Energy Technology Data Exchange (ETDEWEB)

Buysman, E.; Bryan, S.; Pino, M.

2010-05-15

This report presents the revised study of the original CDM baseline study conducted in 2006. The original study was conducted under the authority of the National Biogas Program (NBP), to study the potential GHG mitigation resulting from the adoption of domestic biodigesters. In the beginning of June 2006, a survey amongst 300 randomly selected households with the technical potential for a biodigester was conducted in the NBP's 6-targeted provinces (Kampong Cham, Svay Rieng, Prey Veng, Kampong Speu, Takeo and Kandal) in southeast Cambodia. The revised baseline study includes two additional provinces, Kampot and Kampong Chhnang. The survey showed that a significant proportion of the households have no access to basic sanitation and often have health problems. They consume mainly wood as cooking fuel and the majority use inefficient cooking stoves. The main lighting fuel is kerosene. The GHG emissions were calculated for each type of Animal Waste Management System (AWMS) and the baseline fuel consumption. The main methodology used is the GS-VER biodigester methodology and the IPCC 2006 guidelines to ex-ante estimate baseline, project and the emission reductions. The GHG emission from wood burning is only considered when it originates from a non-renewable source. The NRB analysis determined a NRB share of 70.7% for both collected and purchased wood. Total GHG emission is calculated by combining AWMS and wood fuels emissions. The annual baseline and project emission was estimated to be respectively 5.38 tCO2eq and 0.46 tCO2eq per average household, the emission reductions (ER) are therefore 4.92 tCO2eq/household/year.

Design Study for a Future Laguna-LBNO Long-Baseline Neutrino Facility at CERN

CERN Document Server

Alabau-Gonzalvo, J; Antoniou, F; Benedikt, M; Calviani, M; Efthymiopoulos, I; Ferrari, A; Garoby, R; Gerigk, F; Gilardoni, S; Goddard, B; Kosmicki, A; Lazaridis, C; Osborne, J; Papaphillippou, Y; Parfenova, A; Shaposhnikova, E; Steerenberg, R; Velten, P; Vincke, H

2013-01-01

The Large Apparatus studying Grand Unification and Neutrino Astrophysics (LAGUNA) study [1] investigated seven pre-selected underground sites in Europe (Finland, France, Italy, Poland, Romania, Spain and UK), capable of housing large volume detectors for terrestrial, accelerator generated and astrophysical neutrino research. The study was focused on geo-technical assessment of the sites, concluding that no show-stoppers exist for the construction of the required large underground caverns in the chosen sites. The LAGUNA-LBNO FP7/EC-funded design study extends the LAGUNA study in two key aspects: the detailed engineering of detector construction and operation, and the study of a long-baseline neutrino beam from CERN, and possibly other accelerator centres in Europe. Based on the findings of the LAGUNA study, the Pyh¨asalmi mine in Finland is chosen as prime site for the far detector location. The mine offers the deepest underground location in Europe (-1400 m) and a baseline of 2’300 km from CERN (Fig. 1). ...

Summary report of IAEA technical meeting on technical aspects of atomic and molecular data processing and exchange - 18th meeting of the A+M Data Centres and ALADDIN Network

International Nuclear Information System (INIS)

Hubert, D.

2006-01-01

The IAEA Technical Meeting on 'Technical Aspects of Atomic and Molecular Data Processing and Exchange - 18th Meeting of A+M Data Centres and ALADDIN Network' was held on 10-11 October 2005, in Vienna, Austria. The discussions and presentations focused on the priorities in A+M data compilation and evaluation, and are summarized in this report. Conclusions and recommendations on the technical aspects of data processing, exchange and distribution are also presented. (author)

SKB Annual Report 1995. Including summaries of Technical Reports issued during 1995

International Nuclear Information System (INIS)

1996-05-01

The annual report covers planning, construction and operation of facilities and systems as well as research, development, demonstration work and information activities. The aim of the program is to start the permanent disposal of spent nuclear fuel around year 2008. Work is undertaken for the development of encapsulation technology on an industrial scale and for design of an encapsulation plant. The siting process for the final repository for spent fuel has started with feasibility studies in a few Swedish municipalities in order to evaluate the potential technical conditions and requirements and the influence on the region. 36 refs, figs

SKB Annual Report 1995. Including summaries of Technical Reports issued during 1995

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-05-01

The annual report covers planning, construction and operation of facilities and systems as well as research, development, demonstration work and information activities. The aim of the program is to start the permanent disposal of spent nuclear fuel around year 2008. Work is undertaken for the development of encapsulation technology on an industrial scale and for design of an encapsulation plant. The siting process for the final repository for spent fuel has started with feasibility studies in a few Swedish municipalities in order to evaluate the potential technical conditions and requirements and the influence on the region. 36 refs, figs.

Technical writing versus technical writing

Science.gov (United States)

Dillingham, J. W.

1981-01-01

Two terms, two job categories, 'technical writer' and 'technical author' are discussed in terms of industrial and business requirements and standards. A distinction between 'technical writing' and technical 'writing' is made. The term 'technical editor' is also considered. Problems inherent in the design of programs to prepare and train students for these jobs are discussed. A closer alliance between industry and academia is suggested as a means of preparing students with competent technical communication skills (especially writing and editing skills) and good technical skills.

Forum on orthophotography: Summary Report

Science.gov (United States)

,

1990-01-01

A Forum on Orthophotography was held on May 15, 1990, at the National Aeronautics and Space Administration's Goddard Space Flight Center in Greenbelt, Maryland. The forum was sponsored jointly by the U.S. Soil Conservation Service, the U.S. Geological Survey, the National Governors' Association, and the National Association of Counties. The purpose of the forum was to expand the understanding and use of orthophoto products among the user community, as well as among those currently considering, or as yet unfamiliar with, the use of these products. It was also intended to provide a forum for assessing requirements for, and interest in, orthophoto products and for the identification and discussion of issues and future needs concerning orthophoto use and coordination. The 1-day forum was organized into three major sessions that focussed on technical aspects, user applications, and management issues. The first session presented a brief background and overview of the technical characteristics of standard and digital orthophotos. The second session included formal presentations by Federal, State, and county government agencies on their current and planned applications of orthophoto products, with particular emphasis on their use within geographic information systems. In the third session, private industry addressed their community's interest, capabilities, and potential role. This session also included a proposal by the U.S. Soil Conservation Service for a national cooperative program for the production of l:12,000-scale orthophotoquad products. In addition to the formal presentations, the forum provided a time for open discussion in which attendees had an opportunity to exchange information and make statements about their needs or other items pertinent to the production and dissemination of orthophoto products. Several agency orthophoto product exhibits and interactive demonstrations were also available throughout the day. This report includes a forum agenda and

AICD -- Advanced Industrial Concepts Division Biological and Chemical Technologies Research Program. 1993 Annual summary report

Energy Technology Data Exchange (ETDEWEB)

Petersen, G.; Bair, K.; Ross, J. [eds.

1994-03-01

The annual summary report presents the fiscal year (FY) 1993 research activities and accomplishments for the United States Department of Energy (DOE) Biological and Chemical Technologies Research (BCTR) Program of the Advanced Industrial Concepts Division (AICD). This AICD program resides within the Office of Industrial Technologies (OIT) of the Office of Energy Efficiency and Renewable Energy (EE). The annual summary report for 1993 (ASR 93) contains the following: A program description (including BCTR program mission statement, historical background, relevance, goals and objectives), program structure and organization, selected technical and programmatic highlights for 1993, detailed descriptions of individual projects, a listing of program output, including a bibliography of published work, patents, and awards arising from work supported by BCTR.

IPEN (Instituto de Pesquisas Energeticas e Nucleares) technical-scientific production - 1995-1996

International Nuclear Information System (INIS)

1998-03-01

The biannual report of 1995-1996 of IPEN (Instituto de Pesquisas Energeticas e Nucleares) - Brazilian organization - presents the technical and scientific production accomplished in the period - 975 woks - and introduces the next main topics: articles of periodicals; scientific events - complete texts; dissertations and thesis; scientific events - complete texts - communications, summaries and panels; IPEN publications; books; authors index; scientific events index; subjects index; and periodicals index

Summary of utility/user requirements for and assessment of the MHTGR

International Nuclear Information System (INIS)

Mears, L.D.; Hoffman, D.P.

1992-01-01

Through Gas-Cooled Reactor Associates (GCRA), utilities provide end-user requirements, conduct ongoing technical and economic assessments and participate in the development of deployment strategies for the Modular High Temperature Gas-Cooled Reactor (MHTGR). It is GCRA's goal that the MHTGR be established as an attractive nuclear option for safe, reliable and economic energy supply with limited ownership risks. This report describes the rationale for the key GCRA requirements and presents a summary economic assessment of the reference, 4 module steam cycle design. (author)

Technical abstracts: Mechanical engineering, 1990

International Nuclear Information System (INIS)

Broesius, J.Y.

1991-01-01

This document is a compilation of the published, unclassified abstracts produced by mechanical engineers at Lawrence Livermore National Laboratory (LLNL) during the calendar year 1990. Many abstracts summarize work completed and published in report form. These are UCRL-JC series documents, which include the full text of articles to be published in journals and of papers to be presented at meetings, and UCID reports, which are informal documents. Not all UCIDs contain abstracts: short summaries were generated when abstracts were not included. Technical Abstracts also provides descriptions of those documents assigned to the UCRL-MI (miscellaneous) category. These are generally viewgraphs or photographs presented at meetings. An author index is provided at the back of this volume for cross referencing

NRC review of Electric Power Research Institute's Advanced Light Reactor Utility Requirements Document - Program summary, Project No. 669

International Nuclear Information System (INIS)

1992-08-01

The staff of the US Nuclear Regulatory Commission has prepared Volume 1 of a safety evaluation report (SER), ''NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document -- Program Summary,'' to document the results of its review of the Electric Power Research Institute's ''Advanced Light Water Reactor Utility Requirements Document.'' This SER provides a discussion of the overall purpose and scope of the Requirements Document, the background of the staff's review, the review approach used by the staff, and a summary of the policy and technical issues raised by the staff during its review

International Code Centres Network. Summary Report of the 3rd Biennial Technical Meeting

International Nuclear Information System (INIS)

Chung, Hyun-Kyung

2013-07-01

This report summarizes the proceedings of the third Technical Meeting of the International Code Centres Network held on 6-8 May in 2013. Ten experts from seven member states and four IAEA staff members attended the three-day meeting held at the IAEA Headquarters in Vienna to discuss issues on uncertainty estimates of theoretical atomic and molecular data. The report includes discussions on data issues, meeting conclusions and recommendations for the IAEA Atomic and Molecular Data Unit. (author)

Summary of fuel safety research meeting 2005

International Nuclear Information System (INIS)

Fuketa, Toyoshi; Nakamura, Takehiko; Nagase, Fumihisa; Nakamura, Jinichi; Suzuki, Motoe; Sasajima, Hideo; Sugiyama, Tomoyuki; Amaya, Masaki; Kudo, Tamotsu; Chuto, Toshinori; Tomiyasu, Kunihiko; Udagawa, Yutaka; Ikehata, Hisashi; Kida, Mitsuko; Ikatsu, Nobuhiko; Hosoyamada, Ryuji; Hamanishi, Eizou; Iwasaki, Ryo; Ozawa, Masaaki

2006-03-01

Fuel Safety Research Meeting 2005, which was organized by the Japan Atomic Energy Agency (Establishment of the new organization in Oct. 1, 2005 integrated of JAERI and JNC) was held on March 2-3, 2005 at Toshi Center Hotel, Tokyo. The purposes of the meeting are to present and discuss the results of experiments and analyses on reactor fuel safety and to exchange views and experiences among the participants. The technical topics of the meting covered the status of fuel safety research activities, fuel behavior under Reactivity Initiated Accident (RIA) and Loss of coolant accident (LOCA) conditions, high fuel behavior, and radionuclide release under severe accident conditions. This summary contains all the abstracts and sheets of viewgraph presented in the meeting. (author)

IAEA Technical committee meeting on methods used in design of spent fuel storage facilities

International Nuclear Information System (INIS)

Vitikainen, E.; Silfverberg, P.

1985-01-01

The meeting was held in Espoo, Finland and hosted by the Technical Research Centre of Finland (VTT), and was arranged to report and discuss design methods, licensing practise, operational experience as well as economic aspects connectied with spent fuel storage. This report contains session summaries by the session chairmen and the papers presented at the meeting

Do evidence summaries increase policy-makers' use of evidence from systematic reviews: A systematic review protocol.

Science.gov (United States)

Petkovic, Jennifer; Welch, Vivian; Tugwell, Peter

2015-09-28

Systematic reviews are important for decision-makers. They offer many potential benefits but are often written in technical language, are too long, and do not contain contextual details which makes them hard to use for decision-making. There are many organizations that develop and disseminate derivative products, such as evidence summaries, from systematic reviews for different populations or subsets of decision-makers. This systematic review will assess the effectiveness of systematic review summaries on increasing policymakers' use of systematic review evidence and to identify the components or features of these summaries that are most effective. We will include studies of policy-makers at all levels as well as health-system managers. We will include studies examining any type of "evidence summary," "policy brief," or other products derived from systematic reviews that present evidence in a summarized form. The primary outcomes are the following: (1) use of systematic review summaries decision-making (e.g., self-reported use of the evidence in policy-making, decision-making) and (2) policy-maker understanding, knowledge, and/or beliefs (e.g., changes in knowledge scores about the topic included in the summary). We will conduct a systematic review of randomized controlled trials (RCTs), non-randomized controlled trials (NRCTs), controlled before-after studies (CBA), and interrupted time series (ITS) studies. The results of this review will inform the development of future systematic review summaries to ensure that systematic review evidence is accessible to and used by policy-makers making health-related decisions.

Program reference schedule baseline

International Nuclear Information System (INIS)

1986-07-01

This Program Reference Schedule Baseline (PRSB) provides the baseline Program-level milestones and associated schedules for the Civilian Radioactive Waste Management Program. It integrates all Program-level schedule-related activities. This schedule baseline will be used by the Director, Office of Civilian Radioactive Waste Management (OCRWM), and his staff to monitor compliance with Program objectives. Chapter 1 includes brief discussions concerning the relationship of the PRSB to the Program Reference Cost Baseline (PRCB), the Mission Plan, the Project Decision Schedule, the Total System Life Cycle Cost report, the Program Management Information System report, the Program Milestone Review, annual budget preparation, and system element plans. Chapter 2 includes the identification of all Level 0, or Program-level, milestones, while Chapter 3 presents and discusses the critical path schedules that correspond to those Level 0 milestones

MSFC Skylab Apollo Telescope Mount. [a technical history and management critique

Science.gov (United States)

Morse, A. R.

1974-01-01

A technical history and management critique of the Skylab Apollo Telescope Mount (ATM) from initial conception through the design, manufacturing, testing and prelaunch phases is presented. A mission performance summary provides a general overview of the ATM's achievements in relationship to its design goals. Recommendations and conclusions applicable to hardware design, test program philosophy and performance, and program management techniques for the ATM with potential application to future programs are also discussed.

Estimating the Cold War mortgage: The 1995 Baseline Environmental Management report. Executive summary, March 1995

International Nuclear Information System (INIS)

1995-01-01

This is the first annual report on the activities and potential costs required to address the waste, contamination, and surplus nuclear facilities that are the responsibility of DOE's Environmental Management program. Of the Base Case life-cycle cost estimate of $230 billion from 1995 to 2070, 49% is waste management, 28% environmental restoration, 10% nuclear material and facility stabilization, 5% technology development, and 8% other. The top 5 sites account for 70% of the costs: Hanford 21%, Savannah River Site 21%, Rocky Flats 10%, Oak Ridge 10%, and Idaho Laboratory 8%. Assumptions include significant productivity increases, meeting current compliance requirements, and use of existing technologies. Excluded were: cleanup where no feasible cleanup technology exists (eg, nuclear explosion sites and most contaminated groundwater), cleanup of currently active facilities, naval nuclear propulsion facilities (handled by US Navy), and first 5 years of program ($23 billion). Of the alternative cases evaluated, land use has the biggest potential cost impact. Total projected environmental costs are comparable to total U.S. nuclear weapons production costs. The makeup of Volumes I and II (the latter being site summaries) are outlined briefly

CryoSat SAR/SARin Level1b products: assessment of BaselineC and improvements towards BaselineD

Science.gov (United States)

Scagliola, Michele; Fornari, Marco; Bouffard, Jerome; Parrinello, Tommaso

2017-04-01

CryoSat was launched on the 8th April 2010 and is the first European ice mission dedicated to the monitoring of precise changes in the thickness of polar ice sheets and floating sea ice. Cryosat carries an innovative radar altimeter called the Synthetic Aperture Interferometric Altimeter (SIRAL), that transmits pulses at a high pulse repetition frequency thus making the received echoes phase coherent and suitable for azimuth processing. This allows to reach a significantly improved along track resolution with respect to traditional pulse-width limited altimeters. CryoSat is the first altimetry mission operating in SAR mode and continuous improvements in the Level1 Instrument Processing Facility (IPF1) are being identified, tested and validated in order to improve the quality of the Level1b products. The current IPF, Baseline C, was released in operation in April 2015 and the second CryoSat reprocessing campaign was jointly initiated, taking benefit of the upgrade implemented in the IPF1 processing chain but also of some specific configurations for the calibration corrections. In particular, the CryoSat Level1b BaselineC products generated in the framework of the second reprocessing campaign include refined information for what concerns the mispointing angles and the calibration corrections. This poster will thus detail thus the evolutions that are currently planned for the CryoSat BaselineD SAR/SARin Level1b products and the corresponding quality improvements that are expected.

Technical Design Report for large-scale neutrino detectors prototyping and phased performance assessment in view of a long-baseline oscillation experiment

CERN Document Server

De Bonis, I.; Duchesneau, D.; Pessard, H.; Bordoni, S.; Ieva, M.; Lux, T.; Sanchez, F.; Jipa, A.; Lazanu, I.; Calin, M.; Esanu, T.; Ristea, O.; Ristea, C.; Nita, L.; Efthymiopoulos, I.; Nessi, M.; Asfandiyarov, R.; Blondel, A.; Bravar, A.; Cadoux, F.; Haesler, A.; Karadzhov, Y.; Korzenev, A.; Martin, C.; Noah, E.; Ravonel, M.; Rayner, M.; Scantamburlo, E.; Bayes, R.; Soler, F.J.P.; Nuijten, G.A.; Loo, K.; Maalampi, J.; Slupecki, M.; Trzaska, W.H.; Campanelli, M.; Blebea-Apostu, A.M.; Chesneanu, D.; Gomoiu, M.C; Mitrica, B.; Margineanu, R.M.; Stanca, D.L.; Colino, N.; Gil-Botella, I.; Novella, P.; Palomares, C.; Santorelli, R.; Verdugo, A.; Karpikov, I.; Khotjantsev, A.; Kudenko, Y.; Mefodiev, A.; Mineev, O.; Ovsiannikova, T.; Yershov, N.; Enqvist, T.; Kuusiniemi, P.; De La Taille, C.; Dulucq, F.; Martin-Chassard, G.; Andrieu, B.; Dumarchez, J.; Giganti, C.; Levy, J.-M.; Popov, B.; Robert, A.; Agostino, L.; Buizza-Avanzini, M.; Dawson, J.; Franco, D.; Gorodetzky, P.; Kryn, D.; Patzak, T.; Tonazzo, A.; Vannucci, F.; Bésida, O.; Bolognesi, S.; Delbart, A.; Emery, S.; Galymov, V.; Mazzucato, E.; Vasseur, G.; Zito, M.; Bogomilov, M.; Tsenov, R.; Vankova-Kirilova, G.; Friend, M.; Hasegawa, T.; Nakadaira, T.; Sakashita, K.; Zambelli, L.; Autiero, D.; Caiulo, D.; Chaussard, L.; Déclais, Y.; Franco, D.; Marteau, J.; Pennacchio, E.; Bay, F.; Cantini, C.; Crivelli, P.; Epprecht, L.; Gendotti, A.; Di Luise, S.; Horikawa, S.; Murphy, S.; Nikolics, K.; Periale, L.; Regenfus, C.; Rubbia, A.; Sgalaberna, D.; Viant, T.; Wu, S.; Sergiampietri, F.; CERN. Geneva. SPS and PS Experiments Committee; SPSC

2014-01-01

In June 2012, an Expression of Interest for a long-baseline experiment (LBNO, CERN-SPSC-EOI-007) has been submitted to the CERN SPSC and is presently under review. LBNO considers three types of neutrino detector technologies: a double-phase liquid argon (LAr) TPC and a magnetised iron detector as far detectors. For the near detector, a high-pressure gas TPC embedded in a calorimeter and a magnet is the baseline design. A mandatory milestone in view of any future long baseline experiment is a concrete prototyping effort towards the envisioned large-scale detectors, and an accompanying campaign of measurements aimed at assessing the systematic errors that will be affecting their intended physics programme. Following an encouraging feedback from 108th SPSC on the technology choices, we have defined as priority the construction and operation of a $6\\times 6\\times 6$m$^3$ (active volume) double-phase liquid argon (DLAr) demonstrator, and a parallel development of the technologies necessary for large magnetised MIN...

Cyanide destruction/immobilization of residual sludge - mixed waste focus area. Innovative Technology Summary Report

International Nuclear Information System (INIS)

1998-02-01

Innovative Technology Summary Reports are designed to provide potential users with the information they need to quickly determine if a technology would apply to a particular environmental management problem. They are also designed for readers who may recommend that a technology be considered by prospective users. Each report describes a technology, system, or process that has been developed and tested with funding from DOE's Office of Science and Technology (OST). A report presents the full range of problems that a technology, system, or process will address and its advantages to the DOE cleanup in terms of system performance, cost, and cleanup effectiveness. Most reports include comparisons to baseline technologies as well as other competing technologies. Information about commercial availability and technology readiness for implementation is also included. Innovative Technology Summary Reports are intended to provide summary information. References for more detailed information are provided in an appendix. Efforts have been made to provide key data describing the performance, cost, and regulatory acceptance of the technology. If this information was not available at the time of publication, the omission is noted

Integrated Baseline Bystem (IBS) Version 1.03: Models guide

Energy Technology Data Exchange (ETDEWEB)

1993-01-01

The Integrated Baseline System)(IBS), operated by the Federal Emergency Management Agency (FEMA), is a system of computerized tools for emergency planning and analysis. This document is the models guide for the IBS and explains how to use the emergency related computer models. This document provides information for the experienced system user, and is the primary reference for the computer modeling software supplied with the system. It is designed for emergency managers and planners, and others familiar with the concepts of computer modeling. Although the IBS manual set covers basic and advanced operations, it is not a complete reference document set. Emergency situation modeling software in the IBS is supported by additional technical documents. Some of the other IBS software is commercial software for which more complete documentation is available. The IBS manuals reference such documentation where necessary.

1993 Pacific Northwest Loads and Resources Study, Technical Appendix: Volume 2, Book 1, Energy.

Energy Technology Data Exchange (ETDEWEB)

United States. Bonneville Power Administration.

1993-12-01

The 1993 Pacific Northwest Loads and Resources Study establishes the Bonneville Power Administration`s (BPA) planning basis for supplying electricity to BPA customers. The Loads and Resources Study is presented in three documents: (1) this technical appendix detailing loads and resources for each major Pacific and Northwest generating utility, (2) a summary of Federal system and Pacific Northwest region loads and resources, and (3) a technical appendix detailing forecasted Pacific Northwest economic trends and loads. This analysis updates the 1992 Pacific Northwest Loads and Resources Study Technical Appendix published in December 1992. This technical appendix provides utility-specific information that BPA uses in its long-range planning. It incorporates the following for each utility (1) Electrical demand firm loads; (2) Generating resources; and (3) Contracts both inside and outside the region. This document should be used in combination with the 1993 Pacific Northwest Loads and Resources Study, published in December 1993, because much of the information in that document is not duplicated here.

U.S. oil import vulnerability: The technical replacement capability. Summary

International Nuclear Information System (INIS)

1991-10-01

The report examines the changes that have taken place in world oil markets and the U.S. economy since 1984 and provides revised estimates of the technical oil replacement potential that might be attained in the event of a severe and long lasting cutoff of imported oil. The analysis focuses on technologies that are commercially available today or will be within the next 5 years and that are among the most cost-effective methods for replacing oil use in applicable sectors. It also considers the economic impacts of adopting an aggressive oil replacement strategy in a severe oil emergency. The report presents a variety of policy options that could help accelerate the adoption of oil replacement technologies in preparation for, or in response to, a severe supply disruption, or as part of a long-term national policy to reduce import vulnerability. The report's conclusion that U.S. capability to replace lost oil imports is shrinking should be sobering to those who believe that there are quick and easy technological solutions, or that market forces alone will be sufficient to overcome the substantial economic and social dislocations that could result from a prolonged major oil disruption

Seismic assessment of Technical Area V (TA-V).

Energy Technology Data Exchange (ETDEWEB)

Medrano, Carlos S.

2014-03-01

The Technical Area V (TA-V) Seismic Assessment Report was commissioned as part of Sandia National Laboratories (SNL) Self Assessment Requirement per DOE O 414.1, Quality Assurance, for seismic impact on existing facilities at Technical Area-V (TA-V). SNL TA-V facilities are located on an existing Uniform Building Code (UBC) Seismic Zone IIB Site within the physical boundary of the Kirtland Air Force Base (KAFB). The document delineates a summary of the existing facilities with their safety-significant structure, system and components, identifies DOE Guidance, conceptual framework, past assessments and the present Geological and Seismic conditions. Building upon the past information and the evolution of the new seismic design criteria, the document discusses the potential impact of the new standards and provides recommendations based upon the current International Building Code (IBC) per DOE O 420.1B, Facility Safety and DOE G 420.1-2, Guide for the Mitigation of Natural Phenomena Hazards for DOE Nuclear Facilities and Non-Nuclear Facilities.

Final Technical Report for contract number DE-FG02-05ER15670

Energy Technology Data Exchange (ETDEWEB)

Glazebrook, Jane [Univ. of Minnesota, Minneapolis, MN (United States)

2016-02-29

This is the final technical report for contract number DE-FG02-05ER15670. The project is now complete, and results of the project have been published. Two papers were published based on work done in the last three-year funding period. The DOIs of these papers are included below. The abstracts of the papers, providing summaries of the work, are included in the body of the report.

Technical Aspects of Atomic and Molecular Data Processing and Exchange, 21. Meeting of the A+M Data Centres Network. Summary Report of an IAEA Technical Meeting

Energy Technology Data Exchange (ETDEWEB)

Chung, H.-K., E-mail: H.Chung@iaea.org [IAEA, Atomic and Molecular Data Unit, Vienna (Austria)

2011-11-15

This report summarizes the proceedings of the IAEA Technical Meeting on 'Technical Aspects of Atomic and Molecular Data Processing and Exchange' (21st Meeting of the A+M Data Centres Network) on 7-9 September 2011. Fourteen participants from 12 data centres of 7 Member States and 2 International Organizations attended the three-day meeting held at the IAEA Headquarters in Vienna. The report includes discussions on the data issues, meeting conclusions and recommendations and the abstracts of presentations presented in the meeting. (author)

Technical Aspects of Atomic and Molecular Data Processing and Exchange, 21. Meeting of the A+M Data Centres Network. Summary Report of an IAEA Technical Meeting

International Nuclear Information System (INIS)

Chung, H.-K.

2011-11-01

This report summarizes the proceedings of the IAEA Technical Meeting on 'Technical Aspects of Atomic and Molecular Data Processing and Exchange' (21st Meeting of the A+M Data Centres Network) on 7-9 September 2011. Fourteen participants from 12 data centres of 7 Member States and 2 International Organizations attended the three-day meeting held at the IAEA Headquarters in Vienna. The report includes discussions on the data issues, meeting conclusions and recommendations and the abstracts of presentations presented in the meeting. (author)

Summary of BISON Development Activities: NEAMS FY14 Report

Energy Technology Data Exchange (ETDEWEB)

Williamson, R. L. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Novascone, S. R. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Hales, J. D. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Spencer, B. W. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Liu, W. [Anatech, Inc.; Pastore, G. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Perez, D. M. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Gardner, R. J. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Stafford, D. S. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Gamble, K. A. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2014-10-01

This summary report contains an overview of work performed under the work package entitled “FY2014 NEAMS INL-Engineering Scale Fuel Performance & Interface with RPL Tools.” A first chapter identifies the specific FY-14 milestones, providing a basic description of the associated work and references to related detailed documentation. Where applicable, a representative technical result is provided. A second chapter summarizes substantial additional work including 1) efforts to improve numerical convergence and contact in BISON, 2) development of capability to simulate hydrogen behavior in Zircaloy cladding and 3) efforts to enhance collaborative work with the Halden Research Program. A final chapter briefly outlines planned future work.

Summary of activities of the Research Branch during 1983

International Nuclear Information System (INIS)

1985-11-01

A summary of the activities performed during 1983 by the C.N.E.A.'s Research Branch in basic and applied research is given. The main activities and achievements obtained are shown in the following areas: 1) Physics Department: Tandar Project; Experimental Nuclear Physics; Theoretical Nuclear Physics; Solid State Physics; Technical Assistance and Engineering. 2) Reactor's Chemistry Department with its divisions: Radiation Chemistry; Chemical Control; Moderator and Coolant Physical Chemistry. 3) Radiobiology Department: Radiation Pathology; Genetics; Molecular Genetics; Somatic Effects; Radiomicrobiology; Irradiation and Dosimetry; Bioterium. 4) Prospective Department and Special Studies; Nuclear Fusion and Solar Energy and also, Biomathematics; Labelled Molecules and Radiochemistry. (M.E.L.) [es

Technical bases for leak detection surveillance of waste storage tanks. Revision 1

International Nuclear Information System (INIS)

Johnson, M.G.; Badden, J.J.

1995-01-01

This document provides the technical bases for specification limits, monitoring frequencies and baselines used for leak detection and intrusion (for single shell tanks only) in all single and double shell radioactive waste storage tanks, waste transfer lines, and most catch tanks and receiver tanks in the waste tank farms and associated areas at Hanford

Proceedings of the Efficient Separations and Processing Cross-Cutting Program Annual Technical Exchange Meeting

International Nuclear Information System (INIS)

1995-01-01

This document contains summaries of technology development presented at the 1995 Efficient Separations and Processing Cross-Cutting Program (ESP) Annual Technical Exchange Meeting. The ESP is sponsored by the US Department of Energy's Office of Environmental Management (EM), Office of Technology Development. The meeting is held annually to promote a free exchange of ideas among technology developers, potential users (for example, EM focus areas), and other interested parties within EM. During this meeting, developers of ESP-funded technologies describe the problems and needs addressed by their technologies; the technical approach, accomplishments, and resolution of issues; the strategy and schedule for commercialization; and evolving potential applications. Presenters are asked to address the following areas: Target waste management problem, waste stream, or data need; scientific background and technical approach; technical accomplishments and resolution of technical issues; schedule and strategy for commercializing and implementing the technology or acquiring needed data; potential alternate applications of the technology or data, including outside of DOE/EM. The meeting is not a program review of the individual tasks or subtasks; but instead focuses on the technical aspects and implementation of ESP-sponsored technology or data. The meeting is also attended by members of the ESP Technical Review Team, who have the opportunity at that time to review the ESP as a whole

Preoperational baseline and site characterization report for the Environmental Restoration Disposal Facility

International Nuclear Information System (INIS)

Weekes, D.C.; Ford, B.H.; Jaeger, G.K.

1996-09-01

This document Volume 2 in a two-volume series that comprise the site characterization report for the Environmental Restoration Disposal Facility. Volume 1 contains data interpretation and information supporting the conclusions in the main text. This document presents original data in support of Volume 1 of the report. The following types of data are presented: well construction reports; borehole logs; borehole geophysical data; well development and pump installation; survey reports; and preoperational baseline chemical data and aquifer test data. This does not represent the entire body of data available. Other types of information are archived at BHI Document Control. Five ground water monitoring wells were drilled at the Environmental Restoration Disposal Facility site to directly investigate site- specific hydrogeologic conditions. Well and borehole activity summaries are presented in Volume 1. Field borehole logs and geophysical data from the drilling are presented in this document. Well development and pump installation sheets are presented for the groundwater monitoring wells. Other data presented in this document include borehole geophysical logs from existing wells; chemical data from the sampling of soil, vegetation, and mammals from the ERDF to support the preoperational baseline; ERDF surface radiation surveys;a nd aquifer testing data for well 699-32-72B

Midwest Forensics Resource Center Project Summary June 2005

Energy Technology Data Exchange (ETDEWEB)

David Baldwin

2005-06-01

procedures, (3) capabilities, teaming, and leveraging, and (4) implementation plan. A successful proposal demonstrates knowledge of the background for the research and related work in the field and includes a research plan with a defined plan to implement the technology to benefit our partners at the crime laboratories. The project summaries are meant to demonstrate the range of research funded by the MFRC including chemistry, DNA, and patterned evidence. The project summaries describe the forensic need the projects serve as well as the benefits derived from the technology. The summaries provide a brief description of the technology and the accomplishments to date. In addition, the collaboration with regional partners and the status of the implementation of the technology are highlighted. These technical summaries represent the development and implementation of practical and useful technology for crime laboratories that the MFRC hopes to accomplish.

Surface Signature Characterization at SPE through Ground-Proximal Methods: Methodology Change and Technical Justification

Energy Technology Data Exchange (ETDEWEB)

Schultz-Fellenz, Emily S. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-09-09

A portion of LANL’s FY15 SPE objectives includes initial ground-based or ground-proximal investigations at the SPE Phase 2 site. The area of interest is the U2ez location in Yucca Flat. This collection serves as a baseline for discrimination of surface features and acquisition of topographic signatures prior to any development or pre-shot activities associated with SPE Phase 2. Our team originally intended to perform our field investigations using previously vetted ground-based (GB) LIDAR methodologies. However, the extended proposed time frame of the GB LIDAR data collection, and associated data processing time and delivery date, were unacceptable. After technical consultation and careful literature research, LANL identified an alternative methodology to achieve our technical objectives and fully support critical model parameterization. Very-low-altitude unmanned aerial systems (UAS) photogrammetry appeared to satisfy our objectives in lieu of GB LIDAR. The SPE Phase 2 baseline collection was used as a test of this UAS photogrammetric methodology.

Toward feasible, valid, and reliable video-based assessments of technical surgical skills in the operating room

DEFF Research Database (Denmark)

Aggarwal, R.; Grantcharov, T.; Moorthy, K.

2008-01-01

.72). Conclusions: Video-based technical skills evaluation in the operating room is feasible, valid and reliable. Global rating scales hold promise for summative assessment, though further work is necessary to elucidate the value of procedural rating scales Udgivelsesdato: 2008/2......Objective: To determine the feasibility, validity, inter-rater, and intertest reliability of 4 previously published video-based rating scales, for technical skills assessment on a benchmark laparoscopic procedure. Summary Background Data: Assessment of technical skills is crucial...... to the demonstration and maintenance of competent healthcare practitioners. Traditional assessment methods are prone to subjectivity through a lack of proven validity and reliability. Methods: Nineteen surgeons (6 novice and 13 experienced) performed a median of 2 laparoscopic cholecystectomies each (range 1-5) on 53...

DairyBISS Baseline report

NARCIS (Netherlands)

Buizer, N.N.; Berhanu, Tinsae; Murutse, Girmay; Vugt, van S.M.

2015-01-01

This baseline report of the Dairy Business Information Service and Support (DairyBISS) project presents the findings of a baseline survey among 103 commercial farms and 31 firms and advisors working in the dairy value chain. Additional results from the survey among commercial dairy farms are

A test to evaluate the physical impact on technical performance in soccer

DEFF Research Database (Denmark)

Rostgaard, Thomas; Iaia, F. Marcello; Simonsen, Dennis S.

2008-01-01

The aim of the study was to develop and examine a test for evaluation of the physical and technical capacity of soccer players. Fourteen youth elite (YE) and seven sub-elite (SE) players performed a physical and technical test (PT-test) consisting of 10 long kicks interspersed with intense......(-1), and 76 +/- 11 umol L(-1) at the end of the test, respectively. After the test muscle CP, glycogen and lactate was 52.9 +/- 6.6, 354 +/- 39, and 25.3 +/- 5.9 mmol kg(-1) d.w., respectively. In summary, the PT-test can be used to evaluate a soccer player's technical skills under conditions similar...... intermittent exercise. In addition, a control test (CON-test) without intense exercise was performed. In both cases, the test result was evaluated by the precision of the 10 kicks. The players also performed the Yo-Yo intermittent recovery test level 2 (Yo-Yo IR2). For the SE-players, blood samples were...

Oak Ridge Reservation Annual Site Environmental Report Summary, 2002

Energy Technology Data Exchange (ETDEWEB)

Hughes, JF

2003-11-25

The ''State-of-the-Environment'' on and around the Oak Ridge Reservation is a mission of highest importance to the Department of Energy and our contractors. In order to be fully aware of the consequences of our operations and cleanup, an annual multimillion-dollar monitoring and surveillance program collects and analyzes tens of thousands of samples from air, surface and groundwater, soil, mud, plants, and animals. A mission of equal importance is to provide our stakeholders a complete understanding of this program. To do this we publish a detailed Annual Site Environmental Report and this summary document. The raw data is published separately in the Data Volume. All three documents can be found on the web, along with past documents, at http://www.ornl.gov/aser. Though I work on numerous technical documents throughout the year, no document is more important to me than the Annual Site Environmental Report and its Summary because: (1) they represent the efforts of many dedicated environmental scientists who carry out this extensive program, and who work hard to protect and enhance the environment; (2) they set out the programs in great detail to our legislatures, stakeholders, and the public; and (3) the Summary is directed to the public with the hope that the information is understandable and of value in gaining an accurate picture of the Oak Ridge Reservation as a neighbor. I thank the Karns High School students and their teacher for accepting my challenge in writing this Annual Site Environmental Report Summary, for thinking out of the box, for doing such a fine job, and for all the artwork and photographs (the morning coffee in the classroom was greatly appreciated, leaks and all). They were an especially enjoyable class to work with, and I hope you, our stakeholders and the public, find their efforts of value.

Proceedings of the meeting on the technical study at KEK

Energy Technology Data Exchange (ETDEWEB)

Honma, H.; Tokumoto, S.; Kosuge, T. [National Lab. for High Energy Physics, Tsukuba, Ibaraki (Japan)] [eds.

1996-03-01

This report is a summary report of lectures carried out at the technical meeting on ``control technique of network sequencer application and others`` held by the Technical Information and Library, National Laboratory for High Energy Physics, on November 28th and 29th, 1995. In this meeting, 10 lectures are reported to introduce the control technique in each study field for proposing each common topic subject. They are present status of PS accelerator control, improvement of positron accelerator control system, device controller due to sequencer, data acquisitting (DAQ) system using VMEbus, monitoring and controlling system using sequencer at counter hole, radiation beam line interlock system and network, control of superconducting wiggler through network using Visual Basic, microwave monitoring system for KEKB, data transmission of monitor, and development of machining equipment of mirror for X-ray collecting. (G.K.)

Baseline rationing

DEFF Research Database (Denmark)

Hougaard, Jens Leth; Moreno-Ternero, Juan D.; Østerdal, Lars Peter Raahave

The standard problem of adjudicating conflicting claims describes a situation in which a given amount of a divisible good has to be allocated among agents who hold claims against it exceeding the available amount. This paper considers more general rationing problems in which, in addition to claims...... to international protocols for the reduction of greenhouse emissions, or water distribution in drought periods. We define a family of allocation methods for such general rationing problems - called baseline rationing rules - and provide an axiomatic characterization for it. Any baseline rationing rule within...... the family is associated with a standard rule and we show that if the latter obeys some properties reflecting principles of impartiality, priority and solidarity, the former obeys them too....

A technical review and assessment of the BEIR V [Biological Effects of Ionizing Radiation V] report

International Nuclear Information System (INIS)

1990-03-01

This report was prepared by the DOE BEIR V Technical Review Committee (TRC) to provide a technical review and assessment of the National Research Council's Bilogical Effects of Ionizing Radiation (BEIR) Committee's Report entitled ''Health Effects of Exposure to Low Levels of Ionizing Radiation'' (BEIR V). This report contains seven sections. The first section serves as an introduction and reviews the charge to the TRC. The second section is a chapter-by- chapter summary of the BEIR V Report. The third section is a summary of the risk estimates and conclusions of the BEIR V Committee for genetic effects, cancer induction, and in utero effects. The fourth section is a summary and analysis of the new scientific information used by the BEIR V Committee in developing its risk recommendations and conclusions. The fifth section is an assessment of the scientific information and methods used by the BEIR V Committee in developing their risk estimates and conclusions and an analysis of the key assumptions underlying the use of these risk estimates in risk assessment. The sixth section is the TRC'S assessment of the regulatory implications of the BEIR V risk estimates and conclusions for DOE nuclear operations. The seventh and final section is the TRC'S recommended actions for DOE's consideration concerning the BEIR V Report risk estimates and conclusions. 23 refs., 5 tabs

512-S Facility, Actinide Removal Process Radiological Design Summary Report

International Nuclear Information System (INIS)

Nathan, S.J.

2004-01-01

This report contains top-level requirements for the various areas of radiological protection for workers. Detailed quotations of the requirements for applicable regulatory documents can be found in the Radiological Design Summary Report Implementation Guide. For the purposes of demonstrating compliance with these requirements, per Engineering Standard 01064, ''shall consider / shall evaluate'' indicates that the designer must examine the requirement for the design and either incorporate or provide a technical justification as to why the requirement is not incorporated. This report describes how the Building 512-S, Actinide Removal Process meets the required radiological design criteria and requirements based on 10CFR835, DOE Order 420.1A, WSRC Manual 5Q and various other DOE guides and handbooks. The analyses supporting this Radiological Design Summary Report initially used a source term of 10.6 Ci/gallon of Cs-137 as the basis for bulk shielding calculations. As the project evolved, the source term was reduced to 1.1 Ci/gallon of Cs-137. This latter source term forms the basis for later dose rate evaluations

Technical update on pressure suppression type containments in use in U.S. light water reactor nuclear power plants

International Nuclear Information System (INIS)

1978-07-01

In 1972, Dr. S. H. Hanauer (Technical Advisor to the NRC's Executive Director for Operations) wrote a memorandum that raised several questions on the viability of pressure suppression containment concepts. The concerns raised by Dr. Hanauer have recently become the subject of considerable discussion by several members of the U.S. Congress and public. The report provides a response to these expressed concerns and a status summary for various technical matters that relate to the safety of pressure suppression type containments for light water cooled reactor plants

FigSum: automatically generating structured text summaries for figures in biomedical literature.

Science.gov (United States)

Agarwal, Shashank; Yu, Hong

2009-11-14

Figures are frequently used in biomedical articles to support research findings; however, they are often difficult to comprehend based on their legends alone and information from the full-text articles is required to fully understand them. Previously, we found that the information associated with a single figure is distributed throughout the full-text article the figure appears in. Here, we develop and evaluate a figure summarization system - FigSum, which aggregates this scattered information to improve figure comprehension. For each figure in an article, FigSum generates a structured text summary comprising one sentence from each of the four rhetorical categories - Introduction, Methods, Results and Discussion (IMRaD). The IMRaD category of sentences is predicted by an automated machine learning classifier. Our evaluation shows that FigSum captures 53% of the sentences in the gold standard summaries annotated by biomedical scientists and achieves an average ROUGE-1 score of 0.70, which is higher than a baseline system.

Baseline restoration using current conveyors

International Nuclear Information System (INIS)

Morgado, A.M.L.S.; Simoes, J.B.; Correia, C.M.

1996-01-01

A good performance of high resolution nuclear spectrometry systems, at high pulse rates, demands restoration of baseline between pulses, in order to remove rate dependent baseline shifts. This restoration is performed by circuits named baseline restorers (BLRs) which also remove low frequency noise, such as power supply hum and detector microphonics. This paper presents simple circuits for baseline restoration based on a commercial current conveyor (CCII01). Tests were performed, on two circuits, with periodic trapezoidal shaped pulses in order to measure the baseline restoration for several pulse rates and restorer duty cycles. For the current conveyor based Robinson restorer, the peak shift was less than 10 mV, for duty cycles up to 60%, at high pulse rates. Duty cycles up to 80% were also tested, being the maximum peak shift 21 mV. The peak shift for the current conveyor based Grubic restorer was also measured. The maximum value found was 30 mV at 82% duty cycle. Keeping the duty cycle below 60% improves greatly the restorer performance. The ability of both baseline restorer architectures to reject low frequency modulation is also measured, with good results on both circuits

Technical aspects of atomic and molecular data processing and exchange, 20. meeting of the A+M Data Centres and ALADDIN Network. Summary report of an IAEA technical meeting

International Nuclear Information System (INIS)

Humbert, D.; Braams, B.J.

2010-01-01

The proceedings of the IAEA Advisory Group Meeting on Technical Aspects of Atomic and Molecular Data Processing and Exchange (20th Meeting of A+M Data Centres Network), 7-9 September 2009 at IAEA Headquarters in Vienna, are summarized. The meeting conclusions and recommendations on priorities in A+M data compilation and evaluation and on technical aspects of data processing and exchange are also presented. (author)

Large short-baseline νμ disappearance

International Nuclear Information System (INIS)

Giunti, Carlo; Laveder, Marco

2011-01-01

We analyze the LSND, KARMEN, and MiniBooNE data on short-baseline ν μ →ν e oscillations and the data on short-baseline ν e disappearance obtained in the Bugey-3 and CHOOZ reactor experiments in the framework of 3+1 antineutrino mixing, taking into account the MINOS observation of long-baseline ν μ disappearance and the KamLAND observation of very-long-baseline ν e disappearance. We show that the fit of the data implies that the short-baseline disappearance of ν μ is relatively large. We obtain a prediction of an effective amplitude sin 2 2θ μμ > or approx. 0.1 for short-baseline ν μ disappearance generated by 0.2 2 2 , which could be measured in future experiments.

Technical Issues Map for the NHI System Interface and Support Systems Area: 3rd Quarter FY 07

International Nuclear Information System (INIS)

Steven R. Sherman

2007-01-01

This document provides a mapping of technical issues associated with development of the Next Generation Nuclear Plant (NGNP) intermediate heat transport loop and nuclear hydrogen plant support systems to the work that has been accomplished or is currently underway. The technical issues are ranked according to priority and by assumed resolution dates. Due to funding limitations, not all high-priority technical issues are under study at the present time, and more resources will need to be dedicated to tackling such issues in the future. This technical issues map is useful for understanding the relative importance of various technical challenges and will be used as a planning tool by the NHI technical leadership for future work package planning. The technical map in its present form will be discontinued in FY08 and will be folded into a larger NHI System Interface and Support Systems project management plan and scope baseline statement in FY08

Technical Aspects of Atomic and Molecular Data Processing and Exchange, 22nd Meeting of the A+M Data Centres Network. Summary Report of an IAEA Technical Meeting

International Nuclear Information System (INIS)

Chung, Hyun-Kyung

2013-12-01

This report summarizes the proceedings of the IAEA Technical Meeting on ''Technical Aspects of Atomic and Molecular Data Processing and Exchange'' (22nd Meeting of the A+M Data Centres Network) on 4-6 September 2013. Twelve participants from 8 data centres of 6 Member States attended the three-day meeting held at the IAEA Headquarters in Vienna. The report includes discussions on the data issues, meeting conclusions and recommendations and the abstracts of presentations presented in the meeting. (author)

Student Summary of the U.S. Department of Energy Portsmouth Annual Site Environmental Report (ASER) for 2013

Energy Technology Data Exchange (ETDEWEB)

Bryant, Shea [Waverly High School (WHS), Waverly, OH (United States); Develin, Thomas [Waverly High School (WHS), Waverly, OH (United States); Flores, Victor [Waverly High School (WHS), Waverly, OH (United States); Gilbert, Tyler [Waverly High School (WHS), Waverly, OH (United States); Heigley, Madison [Waverly High School (WHS), Waverly, OH (United States); Johnson, Hayden [Waverly High School (WHS), Waverly, OH (United States); Jones, Larry [Waverly High School (WHS), Waverly, OH (United States); Keechle, Autumn [Waverly High School (WHS), Waverly, OH (United States); Kelley, Abe [Waverly High School (WHS), Waverly, OH (United States); Kritzwiser, Branson [Waverly High School (WHS), Waverly, OH (United States); Lawless, Paige [Waverly High School (WHS), Waverly, OH (United States); Montgomery, Nikki [Waverly High School (WHS), Waverly, OH (United States); Newland, Dawndra [Waverly High School (WHS), Waverly, OH (United States); Noble, Jeff [Waverly High School (WHS), Waverly, OH (United States); Parsons, Abigail [Waverly High School (WHS), Waverly, OH (United States); Riffe, Courtney [Waverly High School (WHS), Waverly, OH (United States); Trego, Andrew [Waverly High School (WHS), Waverly, OH (United States); Wicker, Drake [Waverly High School (WHS), Waverly, OH (United States)

2016-10-07

The U.S. Department of Energy (DOE) conducts environmental monitoring at the Portsmouth Gaseous Diffusion Plant Site (PORTS) on an ongoing basis. Each year, the information collected is presented in a data volume and a comprehensive publication entitled the Annual Site Environmental Report (ASER). This year, a class at Waverly High School (WHS), located in Pike County, Ohio, developed this summary report. Both the ASER and this summary report are important as they allow DOE to clearly and concisely explain our environmental monitoring programs to our many stakeholders. The information presented in this summary shows that the PORTS site near Piketon, Ohio, is safe due in part to the Department’s focus on safety. The work at DOE facilities is highly detailed and technically complex, but DOE is committed to performing each of these activities safely. DOE’s first priority is to protect the well-being of our workers, the surrounding communities, and the environment. DOE would like to offer its sincerest appreciation to the students and faculty leader at Waverly High School who worked on this summary document. DOE congratulates each of you for your effort, enthusiasm, and willingness to support this project. DOE hopes you enjoy reading the PORTS 2013 Annual Site Environmental Report Summary.

Advancing Commercialization of Algal Biofuel through Increased Biomass Productivity and Technical Integration

Energy Technology Data Exchange (ETDEWEB)

Anton, David [Cellana, LLC, Kailua-Kona, HI (United States)

2016-12-31

The proposed project built on the foundation of over several years years of intensive and ground-breaking R&D work at Cellana's Kona Demonstration Facility (KDF). Phycological and engineering solutions were provided to tackle key cultivation issues and technical barriers limiting algal biomass productivity identified through work conducted outdoors at industrial (1 acre) scale. The objectives of this project were to significantly improve algal biomass productivity and reduce operational cost in a seawater-based system, using results obtained from two top-performing algal strains as the baseline while technically advancing and more importantly, integrating the various unit operations involved in algal biomass production, processing, and refining.

The International Linear Collider - Volume 1: Executive Summary

CERN Document Server

Brau, James E.; Foster, Brian; Fuster, Juan; Harrison, Mike; Paterson, James McEwan; Peskin, Michael; Stanitzki, Marcel; Walker, Nicholas; Yamamoto, Hitoshi

2013-01-01

The International Linear Collider Technical Design Report (TDR) describes in four volumes the physics case and the design of a 500 GeV centre-of-mass energy linear electron-positron collider based on superconducting radio-frequency technology using Niobium cavities as the accelerating structures. The accelerator can be extended to 1 TeV and also run as a Higgs factory at around 250 GeV and on the Z0 pole. A comprehensive value estimate of the accelerator is give, together with associated uncertainties. It is shown that no significant technical issues remain to be solved. Once a site is selected and the necessary site-dependent engineering is carried out, construction can begin immediately. The TDR also gives baseline documentation for two high-performance detectors that can share the ILC luminosity by being moved into and out of the beam line in a "push-pull" configuration. These detectors, ILD and SiD, are described in detail. They form the basis for a world-class experimental programme that promises to incr...

Research in the chemical sciences. Summaries of FY 1995

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-09-01

This summary book is published annually to provide information on research supported by the Department of Energy`s Division of Chemical Sciences, which is one of four Divisions of the Office of Basic Energy Sciences in the Office of Energy Research. These summaries provide the scientific and technical public, as well as the legislative and executive branches of the Government, information, either generally or in some depth, about the Chemical Sciences program. Scientists interested in proposing research for support will find the publication useful for gauging the scope of the present basic research program and it`s relationship to their interests. Proposals that expand this scope may also be considered or directed to more appropriate offices. The primary goal of the research summarized here is to add significantly to the knowledge base in which existing and future efficient and safe energy technologies can evolve. As a result, scientific excellence is a major criterion applied in the selection of research supported by the Division of Chemical Sciences, but another important consideration is emphasis on science that is advancing in ways that will produce new information related to energy.

TAPIR--Finnish national geochemical baseline database.

Science.gov (United States)

Jarva, Jaana; Tarvainen, Timo; Reinikainen, Jussi; Eklund, Mikael

2010-09-15

In Finland, a Government Decree on the Assessment of Soil Contamination and Remediation Needs has generated a need for reliable and readily accessible data on geochemical baseline concentrations in Finnish soils. According to the Decree, baseline concentrations, referring both to the natural geological background concentrations and the diffuse anthropogenic input of substances, shall be taken into account in the soil contamination assessment process. This baseline information is provided in a national geochemical baseline database, TAPIR, that is publicly available via the Internet. Geochemical provinces with elevated baseline concentrations were delineated to provide regional geochemical baseline values. The nationwide geochemical datasets were used to divide Finland into geochemical provinces. Several metals (Co, Cr, Cu, Ni, V, and Zn) showed anomalous concentrations in seven regions that were defined as metal provinces. Arsenic did not follow a similar distribution to any other elements, and four arsenic provinces were separately determined. Nationwide geochemical datasets were not available for some other important elements such as Cd and Pb. Although these elements are included in the TAPIR system, their distribution does not necessarily follow the ones pre-defined for metal and arsenic provinces. Regional geochemical baseline values, presented as upper limit of geochemical variation within the region, can be used as trigger values to assess potential soil contamination. Baseline values have also been used to determine upper and lower guideline values that must be taken into account as a tool in basic risk assessment. If regional geochemical baseline values are available, the national guideline values prescribed in the Decree based on ecological risks can be modified accordingly. The national geochemical baseline database provides scientifically sound, easily accessible and generally accepted information on the baseline values, and it can be used in various

Energy materials coordinating committee (EMACC) Fiscal Year 1982. Annual technical report

Energy Technology Data Exchange (ETDEWEB)

None, None

1983-03-01

The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department's materials programs and to further the effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/ workshops on selected topics involving both DOE and major contractors. In addition, the EMaCC aids in obtaining materials - related inputs for both intra- and interagency compilations. Membership in the EMaCC is open to any Department organizational unit; participants are appointed by Division or Office Directors. The current membership is listed in Table 1. The EMACC reports to the Director of the Office of Energy Research in his capacity as overseer of the technical programs of the Department. This annual technical report is mandated by the EMACC terms of reference. In this report are described 1) EMACC activities for FY 1982; 2) a summary of materials funding in the Department from FY 1978 to the present; and 3) on-going materials programs in the Department.

Summary report of a technical meeting on covariances of nuclear reaction data: GANDR project

International Nuclear Information System (INIS)

Trkov, A.

2005-04-01

Highlights of the technical meeting are given with respect to the detailed study of the feasibility of creating a tool for the Global Assessment of Nuclear Data Requirements (GANDR) based on sensitivity and uncertainty analysis. GANDR was concluded to be fully practical on a modern computer of the desktop class. Participants debated their requirements and formulated recommendations and proposals for implementation. Specific tasks were assigned to participants with an estimated time for their execution. (author)

On the baseline evolution of automobile fuel economy in Europe

International Nuclear Information System (INIS)

Zachariadis, Theodoros

2006-01-01

'Business as usual' scenarios in long-term energy forecasts are crucial for scenario-based policy analyses. This article focuses on fuel economy of passenger cars and light trucks, a long-disputed issue with serious implications for worldwide energy use and CO 2 emissions. The current status in Europe is explained and future developments are analysed with the aid of historical data of the last three decades from the United States and Europe. As a result of this analysis, fuel economy values are proposed for use as assumptions in baseline energy/transport scenarios in the 15 'old' European Union Member States. Proposed values are given for new gasoline and diesel cars and for the years 2010, 2020 and 2030. The increasing discrepancy between vehicle fuel consumption measured under test conditions and that in the real world is also considered. One main conclusion is that the European Commission's voluntary agreement with the automobile industry should not be assumed to fully achieve its target under baseline conditions, nor should it be regarded as a major stimulus for autonomous vehicle efficiency improvements after 2010. A second conclusion is that three very recent studies enjoying authority across the EU tend to be overly optimistic as regards the technical progress for conventional and alternative vehicle propulsion technologies under 'business as usual' conditions

Design summary of the magnet support structures for the proton storage ring injection line upgrade

International Nuclear Information System (INIS)

Bernardin, J.D.; Ledford, J.E.; Smith, B.G.

1997-05-01

This report summarizes the technical engineering and design issues associated with the Proton Storage Ring (PSR) Injection Line upgrade of the Los Alamos Neutron Science Center (LANSCE). The main focus is on the engineering design calculations of several magnet support structures. The general procedure based upon a set number of design criteria is outlined, followed by a case-by-case summary of the engineering design analyses, reutilization or fabrication callouts and design safety factors

Research Summaries

Science.gov (United States)

Brock, Stephen E., Ed.

2011-01-01

This article presents summaries of three articles relevant to school crisis response: (1) "Factors Contributing to Posttraumatic Growth," summarized by Steve DeBlois; (2) "Psychological Debriefing in Cross-Cultural Contexts" (Stacey Rice); and (3) "Brain Abnormalities in PTSD" (Sunny Windingstad). The first summary reports the findings of a…

Reference data libraries for nuclear applications - ENSDF. Summary report of technical meeting

International Nuclear Information System (INIS)

Balabanski, D.; Nichols, A.L.

2008-11-01

A Technical Meeting on 'Reference Data Libraries for Nuclear Applications - ENSDF' was held on 10- 11 November 2008 at the IAEA Headquarters, Vienna, Austria. All presentations, discussions and recommendations of this meeting are given in this report. The purpose of the meeting was to review and discuss possible new European input to the ENSDF database (Evaluated Nuclear Structure Data File). These inputs are comprehensive mass-chain evaluations that constitute updated recommendations for the nuclear structure and decay data of nuclides assembled on the basis of mass number. A meeting to address declining European effort was endorsed by the International Nuclear Data Committee in April 2008, and judged as essential in order to balance the share of responsibilities around the world for the maintenance of this important database. (author)

Summary of research for the Inertial Confinement Fusion Program at Los Alamos National Laboratory

International Nuclear Information System (INIS)

Cartwright, D.C.

1985-03-01

The information presented in this report is a summary of the status of the Inertial Confinement Fusion (ICF) program at the Los Alamos National Laboratory as of February 1985. This report contains material on the existing high-power CO 2 laser driver (Antares), the program to determine the potential of KrF as an ICF driver, heavy-ion accelerators as drivers for ICF, target fabrication for ICF, and a summary of our understanding of laser-plasma interactions. A classified companion report contains material on our current understanding of capsule physics and lists the contributions to the Laboratory's weapons programs made by the ICF program. The information collected in these two volumes is meant to serve as a report on the status of some of the technological components of the Los Alamos ICF program rather than a detailed review of specific technical issues

The Fermilab Main Injector Technical Design Handbook

Energy Technology Data Exchange (ETDEWEB)

None, None

1994-08-01

This report contains a description of the design, cost estimate, and construction schedule of the Fermilab Main Injector (FMI) Project. The technical, cost, and schedule baselines for the FMI Project have already been established and may be found in the Fermilab Main Injector Title I Design Report, issued in August 1992. This report updates and expands upon the design and schedule for construction of all subsystem components and associated civil construction described in the Title I Design Report. The facilities described have been designed in conformance with DOE 6430.1A, "United States Department of Energy General Design Criteria."

Summary of activities of the life cycle costing workshop conducted by the Environmental Restoration Program of Oak Ridge National Laboratory

International Nuclear Information System (INIS)

1992-08-01

A five-day life cycle workshop was conducted by the Environmental Restoration (FR) Program of Oak Ridge National Laboratory (ORNL) to develop appropriate remediation scenarios for each Waste Area Grouping (WAG) at ORNL and to identify associated data needs (e.g., remedial investigations, special studies, and technology demonstrations) and required interfaces. Workshop participants represented the Department of Energy, Martin Marietta Energy Systems, Inc., Bechtel National, Radian Corporation, EBASCO Corporation, and M-K Ferguson. The workshop was used to establish a technical basis for remediation activities at each WAG. The workshop results are documented in this report and provide the baseline for estimating the technical scope for each WAG. The scope and associated budgets and schedules will be summarized in baseline reports for each WAG, which, in turn, will be compiled into an overall strategy document for ORNL ER

Does teaching non-technical skills to medical students improve those skills and simulated patient outcome?

Science.gov (United States)

Hagemann, Vera; Herbstreit, Frank; Kehren, Clemens; Chittamadathil, Jilson; Wolfertz, Sandra; Dirkmann, Daniel; Kluge, Annette; Peters, Jürgen

2017-03-29

The purpose of this study is to evaluate the effects of a tailor-made, non-technical skills seminar on medical student's behaviour, attitudes, and performance during simulated patient treatment. Seventy-seven students were randomized to either a non-technical skills seminar (NTS group, n=43) or a medical seminar (control group, n=34). The human patient simulation was used as an evaluation tool. Before the seminars, all students performed the same simulated emergency scenario to provide baseline measurements. After the seminars, all students were exposed to a second scenario, and behavioural markers for evaluating their non-technical skills were rated. Furthermore, teamwork-relevant attitudes were measured before and after the scenarios, and perceived stress was measured following each simulation. All simulations were also evaluated for various medical endpoints. Non-technical skills concerning situation awareness (ptechnical skills to improve student's non-technical skills. In a next step, to improve student's handling of emergencies and patient outcomes, non-technical skills seminars should be accompanied by exercises and more broadly embedded in the medical school curriculum.

2011 Residential Energy Efficiency Technical Update Meeting Summary Report: Denver, Colorado - August 9-11, 2011

Energy Technology Data Exchange (ETDEWEB)

2011-11-01

This report provides an overview of the U.S. Department of Energy Building America program's Summer 2011 Residential Energy Efficiency Technical Update Meeting. This meeting was held on August 9-11, 2011, in Denver, Colorado, and brought together more than 290 professionals representing organizations with a vested interest in energy efficiency improvements in residential buildings.

Acid deposition: State of science and technology. Summary report of the U.S. National Acid Precipitation Assessment Program

International Nuclear Information System (INIS)

Irving, P.M.; Smith, E.

1991-09-01

The twenty-seven State-of-Science and State-of-Technology (SOS/T) Reports, published in 1990 as the definitive scientific and technical synthesis of information obtained during the first decade of the U.S. national Acid Precipitation Assessment Program (NAPAP), are summarized in the document. In most cases, these summaries were the final chapter of the complete SOS/T Report

PROJECT HANFORD MANAGEMENT CONTRACT (PHMC) PERFORMANCE REPORT 05/2004 (WWW.HANFORD.GOV/EMPR.INDEX.CFM)

International Nuclear Information System (INIS)

PIELSTICK, R.M.

2004-01-01

This report is the monthly performance summary of the Central Plateau Contractors. FH work scope responsibilities are described, and other contractor/RL-managed work is excluded. Section A, Overview, provides a summary of the cost, schedule, and technical performance described in this report. It summarizes performance for the period covered, highlights areas worthy of management attention, and provides key performance activities as extracted from the contractor baseline. Subsequent sections of this report provide detailed performance data relative to contract sections (e.g., Project Hanford Cleanup Work Summary, Waste and Spent Nuclear Fuel Management Operations, Infrastructure and Hanford Site Services, and other Work Scope). All information is as of the end of May 2004 unless otherwise noted

Do failures in non-technical skills contribute to fatal medical accidents in Japan? A review of the 2010-2013 national accident reports.

Science.gov (United States)

Uramatsu, Masashi; Fujisawa, Yoshikazu; Mizuno, Shinya; Souma, Takahiro; Komatsubara, Akinori; Miki, Tamotsu

2017-02-16

We sought to clarify how large a proportion of fatal medical accidents can be considered to be caused by poor non-technical skills, and to support development of a policy to reduce number of such accidents by making recommendations about possible training requirements. Summaries of reports of fatal medical accidents, published by the Japan Medical Safety Research Organization, were reviewed individually. Three experienced clinicians and one patient safety expert conducted the reviews to determine the cause of death. Views of the patient safety expert were given additional weight in the overall determination. A total of 73 summary reports of fatal medical accidents were reviewed. These reports had been submitted by healthcare organisations across Japan to the Japan Medical Safety Research Organization between April 2010 and March 2013. The cause of death in fatal medical accidents, categorised into technical skills, non-technical skills and inevitable progress of disease were evaluated. Non-technical skills were further subdivided into situation awareness, decision making, communication, team working, leadership, managing stress and coping with fatigue. Overall, the cause of death was identified as non-technical skills in 34 cases (46.6%), disease progression in 33 cases (45.2%) and technical skills in two cases (5.5%). In two cases, no consensual determination could be achieved. Further categorisation of cases of non-technical skills were identified as 14 cases (41.2%) of problems with situation awareness, eight (23.5%) with team working and three (8.8%) with decision making. These three subcategories, or combinations of them, were identified as the cause of death in 33 cases (97.1%). Poor non-technical skills were considered to be a significant cause of adverse events in nearly half of the fatal medical accidents examined. Improving non-technical skills may be effective for reducing accidents, and training in particular subcategories of non-technical skills may be

Space Solar Power Technical Interchange Meeting 2: SSP TIM 2

Science.gov (United States)

Sanders, Jim; Hawk, Clark W.

1998-01-01

The 2nd Space Solar Power Technical Interchange Meeting (SSP TIM 2) was conducted September 21st through 24th with the first part consisting of a Plenary session. The summary results of this Plenary session are contained in part one of this report. The attendees were then organized into Working Breakout Sessions and Integrated Product Team (IPT) Sessions for the purpose of conducting in-depth discussions in specific topic areas and developing a consensus as to appropriate study plans and actions to be taken. The Second part covers the Plenary Summary Session, which contains the summary results of the Working Breakout Sessions and IPT Sessions. The appendix contains the list of attendees. The ob'jective was to provide an update for the study teams and develop plans for subsequent study activities. This SSP TIM 2 was initiated and the results reported electronically over the Internet. The International Space Station (ISS) could provide the following opportunities for conducting research and technology (R&T) which are applicable to SSP: (1) Automation and Robotics, (2) Advanced Power Generation, (3) Advanced Power Management & Distribution (PMAD), (4) Communications Systems and Networks, (5) Energy Storage, (6) In Space Propulsion (ISP), (7) Structural Dynamics and Control, and Assembly and (8) Wireless Power Transmission.

31 CFR 26.3 - Availability of Environmental Impact Assessment Summaries (EIA Summaries) and Environmental...

Science.gov (United States)

2010-07-01

... 31 Money and Finance: Treasury 1 2010-07-01 2010-07-01 false Availability of Environmental Impact Assessment Summaries (EIA Summaries) and Environmental Impact Assessments (EIAs). 26.3 Section 26.3 Money and... DEVELOPMENT BANDS (MDBs) § 26.3 Availability of Environmental Impact Assessment Summaries (EIA Summaries) and...

78 FR 43091 - Technical Operations Safety Action Program (T-SAP) and Air Traffic Safety Action Program (ATSAP)

Science.gov (United States)

2013-07-19

... Administration 14 CFR Part 193 [Docket No.: FAA-2013-0375] Technical Operations Safety Action Program (T-SAP) and... Disclosure. SUMMARY: The FAA is proposing that safety information provided to it under the T-SAP, established... to the FAA under the T-SAP and ATSAP, so the FAA can learn about and address aviation safety hazards...

Consideration on the technical service quality and the Portugal situation; Consideracoes sobre a qualidade tecnica de servico e caracterizacao da situacao em Portugal

Energy Technology Data Exchange (ETDEWEB)

Santana, J.; Afonso, Jose [Entidade Reguladora do Sector Electrico (ERSE), XX (Portugal)

1999-07-01

This paper presents some considerations on the technical quality of power supply for the consumption and, for the specific characterization of the Portugal electric sector, a summary analysis of the energy production, transport and distribution activities.

Missouri local technical assistance program at Missouri University of Science and Technology (formerly University of Missouri--Rolla) : annual progress report January-December 2007.

Science.gov (United States)

2009-02-01

This annual report is a summary of the activities during 2007 for the Missouri Local Technical Assistance Program (Missouri LTAP), which is located at Missouri University of Science and Technology. The report highlights Missouri LTAPs performance ...

Advanced transportation system studies technical area 3: Alternate propulsion subsystem concepts, volume 3

Science.gov (United States)

Levak, Daniel

1993-01-01

The objective of this contract was to provide definition of alternate propulsion systems for both earth-to-orbit (ETO) and in-space vehicles (upper stages and space transfer vehicles). For such propulsion systems, technical data to describe performance, weight, dimensions, etc. was provided along with programmatic information such as cost, schedule, needed facilities, etc. Advanced technology and advanced development needs were determined and provided. This volume separately presents the various program cost estimates that were generated under three tasks: the F-1A Restart Task, the J-2S Restart Task, and the SSME Upper Stage Use Task. The conclusions, technical results, and the program cost estimates are described in more detail in Volume 1 - Executive Summary and in individual Final Task Reports.

Report on the IAEA technical meeting on network of nuclear reaction data centres

Energy Technology Data Exchange (ETDEWEB)

Schwerer, O [IAEA Nuclear Data Section, Vienna (Austria)

2006-12-15

An IAEA Technical Meeting on the Network of Nuclear Reaction Data Centres (biennial Data Centre Heads Meeting) was held at IAEA Headquarters, Vienna, Austria, from 25 to 28 September 2006. The meeting was attended by 19 participants from 10 cooperating data centres of six Member States and two international organizations. A summary of the meeting is given in this report, along with the conclusions, actions, and status reports of the participating data centres. (author)

Report on the IAEA technical meeting on network of nuclear reaction data centres

International Nuclear Information System (INIS)

Schwerer, O.

2006-12-01

An IAEA Technical Meeting on the Network of Nuclear Reaction Data Centres (biennial Data Centre Heads Meeting) was held at IAEA Headquarters, Vienna, Austria, from 25 to 28 September 2006. The meeting was attended by 19 participants from 10 cooperating data centres of six Member States and two international organizations. A summary of the meeting is given in this report, along with the conclusions, actions, and status reports of the participating data centres. (author)

Progress report [of] Technical Physics and Prototype Engineering Division, April 1982 - March 1984

International Nuclear Information System (INIS)

Ramamurthi, S.S.; Chaudhry, Ramesh

1985-01-01

The work done by the Technical Physics and Prototype Engineering Division of the Bhabha Atomic Research Centre (BARC) at Bombay during the period from April 1982 to March 1984 is described in the form of summaries. The main thrust of the work of the Division is towards designing, developing, fabricating and if needed, producing on a large scale various instruments, equipment and components required for the programmes of the BARC and the Department of Atomic Energy. The summaries describing the work are grouped under the headings:(1) vacuum, (2) surface analysis, (3) mass spectrometry, (4) electronics, (5) cryogenics, (6) crystals and detectors, (7) glass technology and devices, and (8) optoelectronics. A list of publications of the staff-members of the Division during the report period is given. (M.G.B.)

Report of Activity, 1996 - 1997. Vol. 3. General activities - Technical Research

International Nuclear Information System (INIS)

Pouthas, Joel; Hutin, Christiane; Niogret Mathias

1999-01-01

This is the third tome of the Report of Activity of IPN - Orsay on 1996-1997. It deals with general activities and technical research. Summary reports and short communications are grouped in the following sections: 1 - Accelerators with the sub-divisions 1.1 - R and D on superconducting RF cavities; 1.2 - SPIRAL Project; 1.3 - Contribution to the LHC Project; 1.4 - Tandem; 2 - Targets, Sources and Injectors; 3 - Detectors and related instrumentation; 4 - Electronics; 5 - Data processing; 6 - Radioprotection and medical applications

PM10 standards and nontraditional particulate source controls: A summary of the A ampersand WMA/EPA international specialty conference

International Nuclear Information System (INIS)

Chow, J.C.; Watson, J.G.; Ono, D.M.; Mathai, C.V.

1993-01-01

An international specialty conference, jointly sponsored by the Air ampersand Waste Management Association (A ampersand WMA) and the US Environmental Protection Agency (EPA), entitled open-quotes PM 10 Standards and Nontraditional Particulate Source Controls,close quotes was held in Scottsdale, Arizona, January 12-15, 1992. The conference included 92 presentations in 17 technical sessions. Eight-one peer-reviewed technical papers, two keynote addresses and one panel session summary describing novel applications, measurement processes, modeling techniques and control measures for nontraditional pollution sources are assembled in the Transactions. The technical issues addressed during the conference included: (1) measurement methods and data bases; (2) emissions source characterization; (3) source apportionment of nontraditional sources; (4) fugitive dust characterization and control technologies; (5) vegetative burning characterization and control technologies; (6) sources and controls of secondary aerosol and motor vehicle precursors; and (7) regulatory policies and State Implementation Plan (SIP) development. This paper gives an overview of the technical program. 105 refs., 1 tab

40 CFR 1042.825 - Baseline determination.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 32 2010-07-01 2010-07-01 false Baseline determination. 1042.825... Provisions for Remanufactured Marine Engines § 1042.825 Baseline determination. (a) For the purpose of this... not valid. (f) Use good engineering judgment for all aspects of the baseline determination. We may...

The International Linear Collider Technical Design Report - Volume 3.I: Accelerator R&D in the Technical Design Phase

CERN Document Server

Adolphsen, Chris; Barish, Barry; Buesser, Karsten; Burrows, Philip; Carwardine, John; Clark, Jeffrey; Durand, Hélène Mainaud; Dugan, Gerry; Elsen, Eckhard; Enomoto, Atsushi; Foster, Brian; Fukuda, Shigeki; Gai, Wei; Gastal, Martin; Geng, Rongli; Ginsburg, Camille; Guiducci, Susanna; Harrison, Mike; Hayano, Hitoshi; Kershaw, Keith; Kubo, Kiyoshi; Kuchler, Victor; List, Benno; Liu, Wanming; Michizono, Shinichiro; Nantista, Christopher; Osborne, John; Palmer, Mark; Paterson, James McEwan; Peterson, Thomas; Phinney, Nan; Pierini, Paolo; Ross, Marc; Rubin, David; Seryi, Andrei; Sheppard, John; Solyak, Nikolay; Stapnes, Steinar; Tauchi, Toshiaki; Toge, Nobu; Walker, Nicholas; Yamamoto, Akira; Yokoya, Kaoru

2013-01-01

The International Linear Collider Technical Design Report (TDR) describes in four volumes the physics case and the design of a 500 GeV centre-of-mass energy linear electron-positron collider based on superconducting radio-frequency technology using Niobium cavities as the accelerating structures. The accelerator can be extended to 1 TeV and also run as a Higgs factory at around 250 GeV and on the Z0 pole. A comprehensive value estimate of the accelerator is give, together with associated uncertainties. It is shown that no significant technical issues remain to be solved. Once a site is selected and the necessary site-dependent engineering is carried out, construction can begin immediately. The TDR also gives baseline documentation for two high-performance detectors that can share the ILC luminosity by being moved into and out of the beam line in a "push-pull" configuration. These detectors, ILD and SiD, are described in detail. They form the basis for a world-class experimental programme that promises to incr...

Oscillation Baselining and Analysis Tool

Energy Technology Data Exchange (ETDEWEB)

2017-03-27

PNNL developed a new tool for oscillation analysis and baselining. This tool has been developed under a new DOE Grid Modernization Laboratory Consortium (GMLC) Project (GM0072 - “Suite of open-source applications and models for advanced synchrophasor analysis”) and it is based on the open platform for PMU analysis. The Oscillation Baselining and Analysis Tool (OBAT) performs the oscillation analysis and identifies modes of oscillations (frequency, damping, energy, and shape). The tool also does oscillation event baselining (fining correlation between oscillations characteristics and system operating conditions).

Integrating Technical Communication in the Mechanical Engineering Curriculum

Science.gov (United States)

Norberg, Seth; Ashcraft, Timothy; van Poppel, Bret

2017-11-01

Technical communication is essential to engineering practice, but these skills can be challenging to teach and assess in the classroom. Instructors in the Mechanical Engineering (ME) program at the United States Military Academy are developing new learning exercises to prepare students for success in their capstone design course and beyond. In this paper we highlight the recent successes and lessons learned from two courses: junior-level Thermal-Fluid Systems and the senior-level ME Seminar. Both courses support the newly implemented West Point Writing Program (WPWP), an institutional, writing-across-the-curriculum program. The junior course incorporates four hands-on experiments, which provide an abundance of data for students to analyze, assess, and present. In the senior course the majority of the content that students present is from their ongoing capstone design projects. Between the two courses, students craft essays, lab reports, short summaries, posters, quad charts, and technical presentations. Both courses include peer evaluation, revision exercises, and timed (on demand) writing assignments. The junior course includes assignments co-authored by a group as well as an individual report. An overview of both courses' assignments with course-end feedback from the students and the faculty is provided. Strengths and weaknesses are identified and recommendations for instructors seeking to implement similar technical communications assignments in their own courses are presented.

The International Linear Collider Technical Design Report - Volume 3.I: Accelerator \\& in the Technical Design Phase

Energy Technology Data Exchange (ETDEWEB)

Adolphsen, Chris [SLAC National Accelerator Lab., Menlo Park, CA (United States); et al.

2013-06-26

The International Linear Collider Technical Design Report (TDR) describes in four volumes the physics case and the design of a 500 GeV centre-of-mass energy linear electron-positron collider based on superconducting radio-frequency technology using Niobium cavities as the accelerating structures. The accelerator can be extended to 1 TeV and also run as a Higgs factory at around 250 GeV and on the Z0 pole. A comprehensive value estimate of the accelerator is give, together with associated uncertainties. It is shown that no significant technical issues remain to be solved. Once a site is selected and the necessary site-dependent engineering is carried out, construction can begin immediately. The TDR also gives baseline documentation for two high-performance detectors that can share the ILC luminosity by being moved into and out of the beam line in a "push-pull" configuration. These detectors, ILD and SiD, are described in detail. They form the basis for a world-class experimental programme that promises to increase significantly our understanding of the fundamental processes that govern the evolution of the Universe.