An interim report on the State of Nevada socioeconomic studies

International Nuclear Information System (INIS)

1989-06-01

This Interim Report is a report on work in progress and presents findings from the research to date on the potential consequences of a repository for the citizens of Nevada. The research and findings in the Report have been subjected to rigorous peer review as part of the state's effort to insure independent, objective analysis that meets the highest professional standards. The basic research effort will continue through June 1990 and will enable the state to refine and clarify the findings presented in this Interim Report

Agenda 21 interim balance, 1997

Energy Technology Data Exchange (ETDEWEB)

Van Vuuren, D.P.; Bakkes, J.A.

1997-10-01

Five years after the `United Nations Conference on Environment and Development (UNCED)`, an interim balance was drawn up to see what was done to meet the ambitious challenges adopted in Agenda 21 during this conference. Such a balance is presented in this report and the complementary brochure, `Developments in Sustainability 1992-1997`, reflecting societal developments and changes in environmental quality, as well as changes in responses to environmental concerns. 24 figs., 12 tabs., 68 refs.

40 CFR 265 interim-status ground-water monitoring plan for the 2101-M pond

International Nuclear Information System (INIS)

Chamness, M.A.; Luttrell, S.P.; Dudziak, S.

1989-03-01

This report outlines a ground-water monitoring plan for the 2101-M pond, located in the southwestern part of the 200-East Area on the Hanford Site in south-central Washington State. It has been determined that hazardous materials may have been discharged to the pond. Installation of an interim-status ground-water monitoring system is required under the Resource Conservation and Recovery Act to determine if hazardous chemicals are moving out of the pond. This plan describes the location of new wells for the monitoring system, how the wells are to be completed, the data to be collected, and how those data can be used to determine the source and extent of any ground-water contamination from the 2101-M pond. Four new wells are planned, one upgradient and three downgradient. 35 refs., 12 figs., 9 tabs

Interim FDG-PET Scan in Hodgkin's Lymphoma: Hopes and Caveats

Directory of Open Access Journals (Sweden)

M. André

2011-01-01

Full Text Available FDG-PET has recently emerged as an important tool for the management of Hodgkins lymphoma. Although its use for initial staging and response evaluation at the end of treatment is well established, the place of interim PET for response assessment and subsequent treatment tailoring is still quite controversial. The use of interim PET after a few cycles of chemotherapy may allow treatment reduction for good responders, leading to lesser treatment toxicities as well as early treatment adaptation for bad responders with a potential higher chance for cure. Interpretation of interim PET is a rapidly moving field. Actually, visual interpretation is preferred over quantitative interpretation in this situation. The notion of minimal residual uptake emerged for faint persisting FDG uptake, but has evolved during the recent years. Guidelines using mediastinum and liver as references have been proposed at the expert meeting in Deauville 2009. Actually, several trials are ongoing both for localised and advanced disease to evaluate the FDG-PET potential for early treatment monitoring and tailoring. Until the results of these prospective randomized trials become available, treatment changes according to the interim PET results should remain inappropriate and limited to well-conducted clinical trials.

Remedial design report and remedial action work plan for the 100-HR-3 and 100-KR-4 groundwater operable units' interim action

International Nuclear Information System (INIS)

1996-09-01

This document is a combination remedial design report and remedial action work plan for the 100-HR-3 and 100-KR-4 Operable Units (located on the Hanford Site in Richland, Washington) interim action. The interim actions described in this document represent the first of an ongoing program to address groundwater contamination in each operable unit. This document describes the design basis, provides a description of the interim action, and identifies how they will meet the requirements set forth in the interim action Record of Decision

Surface Water Interim Measures/Interim Remedial Action Plan/Environmental Assessment and Decision Document for South Walnut Creek Basin (Operable Unit No. 2)

International Nuclear Information System (INIS)

1991-01-01

The Department of Energy (DOE) is pursuing an Interim Measure/Interim Remedial Action (IM/IRA) at the 903 Pad, Mound, and East Trenches Areas (Operable Unit No. 2) at the Rocky Flats Plant (RFP). This IM/IRA is to be conducted to minimize the release from these areas of hazardous substances that pose a potential threat to the public health and environment. The Plan involved the collection of contaminated surface water at specific locations, treatment by chemical precipitation, cross-flow membrane filtration and granular activated carbon (GAC) adsorption, and surface discharge of treated water. Information for the initial configuration of the Plan is presented in the document entitled ''Proposed Interim Measures/Interim Remedial Action Plan and Decision Document, 903 Pad, Mound, and East Trenches Areas, Operable Unit No. 2'' (IM/IRAP) dated 26 September 1990. Information concerning the proposed Surface Water IM/IRA was presented during a public meeting held from 7 to 10 p.m., Tuesday, 23 October 1990, at the Westminster City Park Recreation Center in Westminster, Colorado. This Responsiveness Summary presents DOE's response to all comments received at the public meeting, as well as those mailed to DOE during the public comment period which ended 24 November 1990. There were a number of technical comments on the plan that DOE has addressed herein. It is noted that several major issues were raised by the comments. Regardless of the estimated low risk to the public from construction and water transport activities, the popular sentiment of the public, based on comments received, is strong concern over worker and public health risks from these activities. In the light of public and municipal concerns, DOE proposes to eliminate from this IM/IRA the interbasin transfer of Woman Creek seepage to the South Walnut Creek drainage and to address collection and treatment of contaminated South Walnut Creek and Woman Creek surface water under two separate IM/IRAs

Current status of the first interim spent fuel storage facility in Japan

International Nuclear Information System (INIS)

Shinbo, Hitoshi; Kondo, Mitsuru

2008-01-01

In Japan, storage of spent fuels outside nuclear power plants was enabled as a result of partial amendments to the Nuclear Reactor Regulation Law in June 2000. Five months later, Mutsu City in Aomori Prefecture asked the Tokyo Electric Power Company (TEPCO) to conduct technical surveys on siting of the interim spent fuel storage facility (we call it 'Recyclable-Fuel Storage Center'). In April 2003, TEPCO submitted the report on siting feasibility examination, concluded that no improper engineering data for siting, construction of the facility will be possible from engineering viewpoint. Siting Activities for publicity and public acceptance have been continued since then. After these activities, Aomori Prefecture and Mutsu City approved siting of the Recyclable Fuel Storage Center in October 2005. Aomori Prefecture, Mutsu City, TEPCO and Japan Atomic Power Company (JAPC) signed an agreement on the interim spent fuel storage Facility. A month later, TEPCO and JAPC established Recyclable-Fuel Storage Company (RFS) in Mutsu City through joint capital investment, specialized in the first interim spent fuel storage Facility in Japan. In May 2007, we made an application for establishment permit, following safety review by regulatory authorities. In March 2008, we started the preparatory construction. RFS will safely store of spent fuels of TEPCO and JAPC until they will be reprocessed. Final storage capacity will be 5,000 ton-U. First we will construct the storage building of 3,000 ton-U to be followed by second building. We aim to start operation by 2010. (author)

Present status of yellow fever: Memorandum from a PAHO Meeting

OpenAIRE

1986-01-01

An international seminar on the treatment and laboratory diagnosis of yellow fever, sponsored by the Pan American Health Organization (PAHO) and held in 1984, differed from previous meetings on yellow fever because of its emphasis on the care and management of patients and because the participants included specialists from several branches of medicine, such as hepatology, haematology, cardiology, infectious diseases, pathology and nephrology. The meeting reviewed the current status of yellow ...

AGR-1 Data Qualification Interim Report

International Nuclear Information System (INIS)

Abbott, Machael

2009-01-01

Projects for the very-high-temperature reactor (VHTR) program provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR Program has established the NGNP Data Management and Analysis System (NDMAS) to ensure that VHTR data are (1) qualified for use, (2) stored in a readily accessible electronic form, and (3) analyzed to extract useful results. This document focuses on the first NDMAS objective. It describes the data streams associated with the first Advanced Gas Reactor (AGR-1) experiment, the processing of these data within NDMAS, and reports the interim FY09 qualification status of the AGR-1 data to date. Data qualification activities within NDMAS for specific types of data are determined by the data qualification category, which is assigned by the data generator, and include: (1) capture testing, to confirm that the data stored within NDMAS are identical to the raw data supplied, (2) accuracy testing, to confirm that the data are an accurate representation of the system or object being measured, and (3) documentation that the data were collected under an NQA-1 or equivalent QA program. The interim qualification status of the following four data streams is reported in this document: (1) fuel fabrication data, (2) fuel irradiation data, (3) fission product monitoring system (FPMS) data, and (4) Advanced Test Reactor (ATR) operating conditions data. A final report giving the NDMAS qualification status of all AGR-1 data (including cycle 145A) is planned for February 2010

Used Fuel Logistics: Decades of Experience with transportation and Interim storage solutions

Energy Technology Data Exchange (ETDEWEB)

Orban, G.; Shelton, C.

2015-07-01

Used fuel inventories are growing worldwide. While some countries have opted for a closed cycle with recycling, numerous countries must expand their interim storage solutions as implementation of permanent repositories is taking more time than foreseen. In both cases transportation capabilities will have to be developed. AREVA TN has an unparalleled expertise with transportation of used fuel. For more than 50 years AREVA TN has safely shipped more than 7,000 used fuel transport casks. The transportation model that was initially developed in the 1970s has been adapted and enhanced over the years to meet more restrictive regulatory requirements and evolving customer needs, and to address public concerns. The numerous “lessons learned” have offered data and guidance that have allowed for also efficient and consistent improvement over the decades. AREVA TN has also an extensive experience with interim dry storage solutions in many countries on-site but also is working with partners to developed consolidated interim storage facility. Both expertise with storage and transportation contribute to safe, secure and smooth continuity of the operations. This paper will describe decades of experience with a very successful transportation program as well as interim storage solutions. (Author)

Austenitic stainless steels, status of the properties database and design rule development

Energy Technology Data Exchange (ETDEWEB)

Tavassoli, A.-A. [Commissariat a l`Energie Atomique, CEA-Saclay, Gif-sur Yvette (France). CEREM; Touboul, F. [DMT, Commissariat a l`Energie Atomique, CEA Saclay, Gif-sur-Yvette (France)

1996-10-01

In parallel with the new tasks initiated to substantiate the existing database for the reference structural material (type 316LN-IG) of ITER, interim design criteria are being developed to guide subsequent design stages. The French RCC-MR codes for fast breeder reactors, incorporating rules from other ITER partner codes and those needed to meet specific fusion requirements, are used for this purpose. This paper presents the current status of materials data and design rules for type 316LN-IG steel and describes how the irradiation effects are taken into account. (orig.).

ISOE EG-SAM interim report - Report on behalf of the Sub expert Group

International Nuclear Information System (INIS)

Harris, Willie; Miller, David W.; Djeffal, Salah; Anderson, Ellen; Couasnon, Olivier; Hagemeyer, Derek; Sovijarvi, Jukka; Amaral, Marcos A.; Tarzia, J.P.; Schmidt, Claudia; Fritioff, Karin; Kaulard, Joerg; Lance, Benoit; Fritioff, Karin; Schieber, Caroline; Hayashida, Yoshihisa; Doty, Rick

2014-01-01

During its November 2012 meeting, the expert group decided to develop an interim (preliminary) report before the end of 2013 (with a general perspective and discussion of specific severe accident management worker dose issues), and to finalize the report by organizing the international workshop of 2014 to address national experiences, which will be incorporated to the report. The work of the EG-SAM focuses on radiation protection management and organization, radiation protection training and exercises related to severe accident management, facility configuration and readiness, worker protection, radioactive materials, contamination controls and logistics and key lessons learned especially from the TMI, Chernobyl and Fukushima Dai-ichi accidents. This interim report was completed through intensive work of all Group members nominated by the ISOE, and was accomplished during EG-SAM meetings through 2012-2013. This document gathers the different presentations given by the sub expert groups in charge of each chapter of the report

Safety evaluation of interim stabilization of non-stabilized single-shell watch list tanks

Energy Technology Data Exchange (ETDEWEB)

Stahl, S.M.

1994-12-30

The report provides a summation of the status of safety issues associated with interim stabilization of Watch List SSTs (organic, ferrocyanide, and flammable gas), as extracted from recent safety analyses, including the Tank Farms Accelerated Safety Analysis efforts.

Safety evaluation of interim stabilization of non-stabilized single-shell watch list tanks

International Nuclear Information System (INIS)

Stahl, S.M.

1994-01-01

The report provides a summation of the status of safety issues associated with interim stabilization of Watch List SSTs (organic, ferrocyanide, and flammable gas), as extracted from recent safety analyses, including the Tank Farms Accelerated Safety Analysis efforts

A randomized controlled trial of interim methadone maintenance.

Science.gov (United States)

Schwartz, Robert P; Highfield, David A; Jaffe, Jerome H; Brady, Joseph V; Butler, Carol B; Rouse, Charles O; Callaman, Jason M; O'Grady, Kevin E; Battjes, Robert J

2006-01-01

Effective alternatives to long waiting lists for entry into methadone hydrochloride maintenance treatment are needed to reduce the complications of continuing heroin dependence and to increase methadone treatment entry. To compare the effectiveness of interim methadone maintenance with that of the usual waiting list condition in facilitating methadone treatment entry and reducing heroin and cocaine use and criminal behavior. Randomized, controlled, clinical trial using 2 conditions, with treatment assignment on a 3:2 basis to interim maintenance-waiting list control. A methadone treatment program in Baltimore. A total of 319 individuals meeting the criteria for current heroin dependence and methadone maintenance treatment. Participants were randomly assigned to either interim methadone maintenance, consisting of an individually determined methadone dose and emergency counseling only for up to 120 days, or referral to community-based methadone treatment programs. Entry into comprehensive methadone maintenance therapy at 4 months from baseline; self-reported days of heroin use, cocaine use, and criminal behavior; and number of urine drug test results positive for heroin and cocaine at the follow-up interview conducted at time of entry into comprehensive methadone treatment (or at 4 months from baseline for participants who did not enter regular treatment). Significantly more participants assigned to the interim methadone maintenance condition entered comprehensive methadone maintenance treatment by the 120th day from baseline (75.9%) than those assigned to the waiting list control condition (20.8%) (Pmethadone maintenance results in a substantial increase in the likelihood of entry into comprehensive treatment, and is an effective means of reducing heroin use and criminal behavior among opioid-dependent individuals awaiting entry into a comprehensive methadone treatment program.

2005 Annual Operations Report for INTEC Operable Unit 3-13, Group 1, Tank Farm Interim Action

International Nuclear Information System (INIS)

D. Shanklin

2006-01-01

This annual operations report describes the requirements followed and activities conducted to inspect, monitor, and maintain the items installed during performance of the Waste Area Group 3, Operable Unit 3-13, Group 1, Tank Farm Interim Action, at the Idaho Nuclear Technology and Engineering Center. This report describes inspection and monitoring activities for the surface-sealed areas within the tank farm, concrete-lined ditches and culverts in and around the tank farm, the lift station, and the lined evaporation pond. These activities are intended to assure that the interim action is functioning adequately to meet the objectives stated in the Operable Unit 3-13, Record of Decision for the Group 1, Tank Farm Interim Action, (DOE/ID-10660) and as amended by the agreement to resolve dispute, which was effective in February 2003

Interim overdentures.

Science.gov (United States)

Fenton, A H

1976-07-01

The construction of an interim overdenture using existing removable partial dentures with natural tooth crowns and artificial teeth can be a simple and economical method of providing patients with dentures while tissues heal and teeth are prepared and restored. A more definite prognosis for both the patient and his remaining dentition can be established before the final overdenture is completed. The procedures necessary to provide three types of interim overdentures have been outlined. Patients tolerate this method of changing their dentitions extremely well.

Seismic Safety Margins Research Program. Phase I. Interim definition of terms

International Nuclear Information System (INIS)

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

1980-01-01

This report documents interim definitions of terms in the Seismic Safety Margins Research Program (SSMRP). Intent is to establish a common-based terminology integral to the probabilistic methods that predict more realistically the behavior of nuclear power plants during an earthquake. These definitions are a response to a request by the Nuclear Regulatory Commission Advisory Committee on Reactor Safeguards at its meeting held November 15-16, 1979

Evaluation of tuff as a medium for a nucolear waste repository: interim status report on the properties of tuff

International Nuclear Information System (INIS)

Johnstone, J.K.; Wolfsberg, K.

1980-07-01

This report is the second in a series of summary briefings to the National Academy of Science's (NAS) Committee on Radioactive Waste Management dealing with feasibility of disposal of heat-producing radioactive waste in silicic tuff. The interim status of studies of tuff properties determined on samples obtained from Yucca Mountain and Rainier Mesa (G-tunnel) located on the Nevada Test Site (NTS) are discussed. In particular, progress is described on resolving issues identified during the first briefing to the NAS which include behavior of water in tuff when heated, the effect of the presence or absence of water and joints on the thermal/physical properties of tuff and the detailed/complex sorptive properties of highly altered and unaltered tuff. Initial correlations of thermal/physical and sorptive properties with the highly variable porosity and mineralogy are described. Three in-situ, at-depth field experiments, one nearly completed and two just getting underway are described. In particular, the current status of mineralogy and petrology, geochemistry, thermal and mechanical, radiation effects and water behavior studies are described. The goals and initial results of a Mine Design Working Group are discussed. Regional factors such as seismicity, volcanism and hydrology are not discussed

Radioactive waste interim storage in Germany

International Nuclear Information System (INIS)

2015-12-01

The short summary on the radioactive waste interim storage in Germany covers the following issues: importance of interim storage in the frame of radioactive waste management, responsibilities and regulations, waste forms, storage containers, transport of vitrified high-level radioactive wastes from the reprocessing plants, central interim storage facilities (Gorleben, Ahaus, Nord/Lubmin), local interim storage facilities at nuclear power plant sites, federal state collecting facilities, safety, radiation exposure in Germany.

Hanford low-level tank waste interim performance assessment

International Nuclear Information System (INIS)

Mann, F.M.

1997-01-01

The Hanford Low-Level Tank Waste Interim Performance Assessment examines the long-term environmental and human health effects associated with the disposal of the low-level fraction of the Hanford single and double-shell tank waste in the Hanford Site 200 East Area. This report was prepared as a good management practice to provide needed information about the relationship between the disposal system design and performance early in the disposal system project cycle. The calculations in this performance assessment show that the disposal of the low-level fraction can meet environmental and health performance objectives

Terrestrial gravity data analysis for interim gravity model improvement

Science.gov (United States)

1987-01-01

This is the first status report for the Interim Gravity Model research effort that was started on June 30, 1986. The basic theme of this study is to develop appropriate models and adjustment procedures for estimating potential coefficients from terrestrial gravity data. The plan is to use the latest gravity data sets to produce coefficient estimates as well as to provide normal equations to NASA for use in the TOPEX/POSEIDON gravity field modeling program.

Transitioning aluminum clad spent fuels from wet to interim dry storage

International Nuclear Information System (INIS)

Louthan, M.R. Jr.; Iyer, N.C.; Sindelar, R.L.; Peacock, H.B. Jr.

1994-01-01

The United States Department of Energy (DOE) currently owns several hundred metric tons of aluminum clad, spent nuclear fuel and target assemblies. The vast majority of these irradiated assemblies are currently stored in water basins that were designed and operated for short term fuel cooling prior to fuel reprocessing. Recent DOE decisions to severely limit the reprocessing option have significantly lengthened the time of storage, thus increasing the tendency for corrosion induced degradation of the fuel cladding and the underlying core material. The portent of continued corrosion, coupled with the age of existing wet storage facilities and the cost of continuing basin operations, including necessary upgrades to meet current facility standards, may force the DOE to transition these wet stored, aluminum clad spent fuels to interim dry storage. The facilities for interim dry storage have not been developed, partially because fuel storage requirements and specifications for acceptable fuel forms are lacking. In spite of the lack of both facilities and specifications, current plans are to dry store fuels for approximately 40 to 60 years or until firm decisions are developed for final fuel disposition. The transition of the aluminum clad fuels from wet to interim dry storage will require a sequence of drying and canning operations which will include selected fuel preparations such as vacuum drying and conditioning of the storage atmosphere. Laboratory experiments and review of the available literature have demonstrated that successful interim dry storage may also require the use of fuel and canister cleaning or rinsing techniques that preclude, or at least minimize, the potential for the accumulation of chloride and other potentially deleterious ions in the dry storage environment. This paper summarizes an evaluation of the impact of fuel transitioning techniques on the potential for corrosion induced degradation of fuel forms during interim dry storage

7 CFR 1738.21 - Interim financing.

Science.gov (United States)

2010-01-01

... 7 Agriculture 11 2010-01-01 2010-01-01 false Interim financing. 1738.21 Section 1738.21... Interim financing. (a) Upon notification by RUS that an applicant's application is considered complete, the applicant may enter into an interim financing agreement with a lender other than RUS or use its...

7 CFR 1735.75 - Interim financing.

Science.gov (United States)

2010-01-01

... 7 Agriculture 11 2010-01-01 2010-01-01 false Interim financing. 1735.75 Section 1735.75... Involving Loan Funds § 1735.75 Interim financing. (a) A borrower may submit a written request for RUS approval of interim financing if it is necessary to close an acquisition before the loan to finance the...

Comparisons of Cooperative and Non-Cooperative Students: An Analysis of Student Accounting System Data. Interim Report, June, 1981.

Science.gov (United States)

Frazier, Don

The major purpose of this study was to identify unique effects of cooperative vocational education. This interim report is of results of the analyses of existing data bases. Comparisons of cooperative and non-cooperative vocational programs are made on the following variables: enrollments by age, sex and race, school status, work status,…

2006 Annual Operations Report for INTEC Operable Unit 3-13, Group 1, Tank Farm Interim Action

International Nuclear Information System (INIS)

D. E. Shanklin

2007-01-01

This annual operations report describes the requirements followed and activities conducted to inspect, monitor, and maintain the items installed during performance of the Waste Area Group 3, Operable Unit 3-13, Group 1, Tank Farm Interim Action, at the Idaho Nuclear Technology and Engineering Center. This report covers the time period from January 1 through December 31, 2006, and describes inspection and monitoring activities for the surface-sealed areas within the tank farm, concrete-lined ditches and culverts in and around the tank farm, the lift station, and the lined evaporation pond. These activities are intended to assure that the interim action is functioning adequately to meet the objectives stated in the Operable Unit 3-13, Record of Decision for the Group 1, Tank Farm Interim Action (DOE/ID-10660) as described in the Group 1 Remedial Design/Remedial Action Work Plan (DOE/ID-10772)

Status of national programmes on fast breeder reactors. Eighteenth annual meeting, Vienna, Austria, 16-19 April 1985

International Nuclear Information System (INIS)

1986-02-01

The Eighteenth Annual Meeting on the Status of National Programmes in Member States of the IAEA on Fast Breeder Reactors had been held in April 1985. The representatives of the Member States and international organizations reported status and activities in the field of fast breeder reactors development and operation. A separate abstract was prepared for each of the 12 presentations of the meeting

40 CFR 265 interim status indicator-evaluation ground-water monitoring plan for the 216-B-63 trench

International Nuclear Information System (INIS)

Bjornstad, B.N.; Dudziak, S.

1989-03-01

This document outlines a ground-water monitoring plan for the 216-B-63 trench located in the northeast corner of the 200-East Area on the Hanford Site in southeastern Washington State. It has been determined that hazardous materials (corrosives) were disposed of to the trench during past operations. Installation of an interim-status ground-water monitoring system is required to determine whether hazardous chemicals are leaching to the ground water from beneath the trench. This document summarizes the existing data that are available from near the 216-B-63 trench and presents a plan to determine the extent of ground-water contamination, if any, derived from the trench. The plan calls for the installation of four new monitoring wells located near the west end of the trench. These wells will be used to monitor ground-water levels and water quality immediately adjacent to the trench. Two existing RCRA monitoring wells, which are located near the trench and hydraulically upgradient of it, will be used as background wells. 46 refs., 15 figs., 12 tabs

13 CFR 120.890 - Source of interim financing.

Science.gov (United States)

2010-01-01

... 13 Business Credit and Assistance 1 2010-01-01 2010-01-01 false Source of interim financing. 120... Development Company Loan Program (504) Interim Financing § 120.890 Source of interim financing. A Project may use interim financing for all Project costs except the Borrower's contribution. Any source (including...

Low-level waste forum meeting reports

Energy Technology Data Exchange (ETDEWEB)

NONE

1990-12-31

This paper provides highlights from the October 1990 meeting of the Low Level Radioactive Waste Forum. Topics of discussion included: a special session on liability and financial assurance needs; proposal to dispose of mixed waste at federal facilities; state plans for interim storage; and hazardous materials legislation.

A study of the usage of LPAs by the North Carolina Division of Motor Vehicles : interim report - phase I.

Science.gov (United States)

2014-02-27

This interim report was prepared to assist NCDMV in meeting the requirements of S.B. 402, Sec. 34.17, which mandates that NCDOT in collaboration with NCDMV shall evaluate current contractual models and compensation for license plate agency (LPA...

Facility status and progress of the INEL's WERF MLLW and LLW incinerator

International Nuclear Information System (INIS)

Conley, D.; Corrigan, S.

1996-01-01

The Idaho National Engineering Laboratory's (INEL) Waste Experimental Reduction Facility (WERF) incinerator began processing beta/gamma- emitting low-level waste (LLW) in September 1984. A Resource Conservation and Recovery Act (RCRA) trial burn for the WERF incinerator was conducted in 1986, and in 1989 WERF began processing (hazardous and low-level radioactive) waste known as mixed low-level waste (MLLW). On February 14, 1991 WERF operations were suspended to improve operating procedures and configuration management. On July 12, 1995, WERF initiated incineration of LLW; and on September 20, 1995 WERF resumed its primary mission of incinerating MLLW. MLLW incineration is proceeding under RCRA interim status. State of Idaho issuance of the Part B permit is one of the State's highest permitting priorities. The State of Idaho's Division of Environmental Quality is reviewing the permit application along with a revised trial burn plan that was also submitted with the application. The trial burn has been proposed to be performed in 1996 to demonstrate compliance with the current incinerator guidance. This paper describes the experiences and problems associated with WERF's operations, incineration of MLLW, and the RCRA Part B Permit Application. Some of the challenges that have been overcome include waste characterization, waste repackaging, repackaged waste storage, and implementation of RCRA interim status requirements. A number of challenges remain. They include revision of the RCRA Part B Permit Application and the Trial Burn Plan in response to comments from the state permit application reviewers as well as facility and equipment upgrades required to meet RCRA Permitted Status

Interim storage is not long-term disposal

International Nuclear Information System (INIS)

Vincenti, J.R.

1994-01-01

Starting in June 30, 1994 South Carolina enforced an embargo on regular shipments of low-level radioactive waste to the Barnwell repository. The failure of 31 states and their respective compacts to provide access to a long-term disposal facility as stipulated by the low-level radioactive Waste Policy Act of 1980 promotes waste disposal gridlock and anticipates another waste disposal crisis. This article discusses the problem using the following topics: Appalachian Compact Users of Radioactive Isotopes (ACURI) Association's interest; the problem of denial of access to Barnwell; pro and contra interim storage; vital services and benefits at risk; issues at the ACURI meeting; nobel Prize winners use radioactive materials; if perception is reality, politics is prevalent

Mission Status for Earth Science Constellation MOWG Meeting at KSC: EOS Aura

Science.gov (United States)

Fisher, Dominic

2017-01-01

This will be presented at the Earth Science Constellation Mission Operations Working Group (MOWG) meeting at KSC (Kennedy Space Center) in December 2017 to discus EOS (Earth Observing System) Aura status. Reviewed and approved by Eric Moyer, ESMO (Earth Sciences Mission Operations) Deputy Project Manager.

Burn site groundwater interim measures work plan.

Energy Technology Data Exchange (ETDEWEB)

Witt, Jonathan L. (North Wind, Inc., Idaho Falls, ID); Hall, Kevin A. (North Wind, Inc., Idaho Falls, ID)

2005-05-01

This Work Plan identifies and outlines interim measures to address nitrate contamination in groundwater at the Burn Site, Sandia National Laboratories/New Mexico. The New Mexico Environment Department has required implementation of interim measures for nitrate-contaminated groundwater at the Burn Site. The purpose of interim measures is to prevent human or environmental exposure to nitrate-contaminated groundwater originating from the Burn Site. This Work Plan details a summary of current information about the Burn Site, interim measures activities for stabilization, and project management responsibilities to accomplish this purpose.

24 CFR 35.1330 - Interim controls.

Science.gov (United States)

2010-04-01

... Lead-Paint Hazard Evaluation and Hazard Reduction Activities § 35.1330 Interim controls. Interim..., cleanable covering or coating, such as metal coil stock, plastic, polyurethane, or linoleum. (3) Surfaces...

Solid waste burial grounds interim safety analysis

International Nuclear Information System (INIS)

Saito, G.H.

1994-01-01

This Interim Safety Analysis document supports the authorization basis for the interim operation and restrictions on interim operations for the near-surface land disposal of solid waste in the Solid Waste Burial Grounds. The Solid Waste Burial Grounds Interim Safety Basis supports the upgrade progress for the safety analysis report and the technical safety requirements for the operations in the Solid Waste Burial Grounds. Accident safety analysis scenarios have been analyzed based on the significant events identified in the preliminary hazards analysis. The interim safety analysis provides an evaluation of the operations in the Solid Waste Burial Grounds to determine if the radiological and hazardous material exposures will be acceptable from an overall health and safety standpoint to the worker, the onsite personnel, the public, and the environment

Solid waste burial grounds interim safety analysis

Energy Technology Data Exchange (ETDEWEB)

Saito, G.H.

1994-10-01

This Interim Safety Analysis document supports the authorization basis for the interim operation and restrictions on interim operations for the near-surface land disposal of solid waste in the Solid Waste Burial Grounds. The Solid Waste Burial Grounds Interim Safety Basis supports the upgrade progress for the safety analysis report and the technical safety requirements for the operations in the Solid Waste Burial Grounds. Accident safety analysis scenarios have been analyzed based on the significant events identified in the preliminary hazards analysis. The interim safety analysis provides an evaluation of the operations in the Solid Waste Burial Grounds to determine if the radiological and hazardous material exposures will be acceptable from an overall health and safety standpoint to the worker, the onsite personnel, the public, and the environment.

77 FR 43064 - Defense Science Board; Notice of Advisory Committee Meetings

Science.gov (United States)

2012-07-23

... Science Board 2012 Summer Study on Technology and Innovation Enablers for Superiority in 2030 will meet in closed session August 20-24, 2012, from 8:00 a.m. to 5:00 p.m. at the Charles Stark Draper Laboratory... meeting, the Board will discuss interim finding and recommendations resulting from ongoing Task Force...

Advanced nuclear reactor public opinion project. Interim report

Energy Technology Data Exchange (ETDEWEB)

Benson, B.

1991-07-25

This Interim Report summarizes the findings of our first twenty in-depth interviews in the Advanced Nuclear Reactor Public Opinion Project. We interviewed 6 industry trade association officials, 3 industry attorneys, 6 environmentalists/nuclear critics, 3 state officials, and 3 independent analysts. In addition, we have had numerous shorter discussions with various individuals concerned about nuclear power. The report is organized into the four categories proposed at our April, 1991, Advisory Group meeting: safety, cost-benefit analysis, science education, and communications. Within each category, some change of focus from that of the Advisory Group has been required, to reflect the findings of our interviews. This report limits itself to describing our findings. An accompanying memo draws some tentative conclusions.

Safety of interim storage solutions of used nuclear fuel during extended term

Energy Technology Data Exchange (ETDEWEB)

Shelton, C.; Bader, S.; Issard, H.; Arslan, M. [AREVA, 7135 Minstrel Way, Suite 300 Columbia, MD 21045 (United States)

2013-07-01

In 2013, the total amount of stored used nuclear fuel (UNF) in the world will reach 225,000 T HM. The UNF inventory in wet storage will take up over 80% of the available total spent fuel pool (SFP) capacity. Interim storage solutions are needed. They give flexibility to the nuclear operators and ensure that nuclear reactors continue to operate. However, we need to keep in mind that they are also an easy way to differ final decision and implementation of a UNF management approach (recycling or final disposal). In term of public perception, they can have a negative impact overtime as it may appear that nuclear industry may have significant issues to resolve. In countries lacking an integrated UNF management approach, the UNF are being discharged from the SFPs to interim storage (mostly to dry storage) at the same rate as UNF is being discharged from reactors, as the SFPs at the reactor sites are becoming full. This is now the case in USA, Taiwan, Switzerland, Spain, South Africa and Germany. For interim storage, AREVA has developed different solutions in order to allow the continued operation of reactors while meeting the current requirements of Safety Authorities: -) Dry storage canisters on pads, -) Dual-purpose casks (dry storage and transportation), -) Vault dry storage, and -) Centralized pool storage.

Reliability Centered Maintenance for Savannah River Site's interim waste management facilities

International Nuclear Information System (INIS)

Hauer, K.A.; Wilson, J.F.

1992-01-01

The application of Reliability Centered Maintenance (RCM) has been shown to be an effective means to optimize maintenance programs or to establish new programs. The key to success of any RCM program is to customize the methodology to meet the specific needs of the implementing organization. This paper discusses how RCM is being used to establish the preventive maintenance program and how the resulting system data is being used to support the Technical Baseline reconstitution effort for the interim Waste Management Division of Westinghouse Savannah River Company (WSRC)

Meeting Recommended Levels of Physical Activity in Relation to Preventive Health Behavior and Health Status Among Adults

Directory of Open Access Journals (Sweden)

Peter D. Hart

2017-01-01

Full Text Available Objectives The purpose of this study was to examine the relationship of meeting the recommended levels of physical activity (PA with health status and preventive health behavior in adults. Methods A total of 5630 adults 18 years of age or older were included in this study. PA was assessed using a series of questions that categorized activities based on their metabolic equivalent values and then categorized individuals based on the reported frequency and duration of such activities. Participants reporting 150 minutes or more of moderate-intensity PA per week were considered to have met the PA guidelines. Multiple logistic regression was used to model the relationships between meeting PA guidelines and health status and preventive health behavior, while controlling for confounding variables. Results Overall, 53.9% (95% confidence interval [CI], 51.9 to 55.9% of adults reported meeting the recommended levels of PA. Among adults with good general health, 56.9% (95% CI, 54.7 to 59.1% reported meeting the recommended levels of PA versus 43.1% (95% CI, 40.9 to 45.3% who did not. Adults who met the PA guidelines were significantly more likely not to report high cholesterol, diabetes, chronic obstructive pulmonary disease, arthritis, asthma, depression, or overweight. Furthermore, adults meeting the PA guidelines were significantly more likely to report having health insurance, consuming fruits daily, consuming vegetables daily, and not being a current cigarette smoker. Conclusions In this study, we found meeting the current guidelines for PA to have a protective relationship with both health status and health behavior in adults. Health promotion programs should focus on strategies that help individuals meet the current guidelines of at least 150 minutes per week of moderate-intensity PA.

Interim Administrators in Higher Education: A National Study

Science.gov (United States)

Huff, Marie Thielke; Neubrander, Judy

2015-01-01

The focus of this paper is on the roles and experiences of interim administrators in higher education. A survey was given to current and recent interim administrators in four-year public universities and colleges across the United States. The goals were to identify the advantages and disadvantages of using and serving as interims, and to solicit…

Subsurface Interim Measures/Interim Remedial Action Plan/Environmental Assessment and Decision Document, Operable Unit No. 2

International Nuclear Information System (INIS)

1992-01-01

The subject Interim Measures/Interim Remedial Action plan/Environmental Assessment (IM/IRAP/EA) addresses residual free-phase volatile organic compound (VOC) contamination suspected in the subsurface within an area identified as Operable Unit No. 2 (OU2). This IM/IRAP/EA also addresses radionuclide contamination beneath the 903 Pad at OU2. Although subsurface VOC and radionuclide contamination on represent a source of OU2 ground-water contamination, they pose no immediate threat to public health or the environment. This IM/IRAP/EA identifies and evaluates interim remedial actions for removal of residual free-phase VOC contamination from three different subsurface environments at OU2. The term ''residual'' refers to the non-aqueous phase contamination remaining in the soil matrix (by capillary force) subsequent to the passage of non-aqueous or free-phase liquid through the subsurface. In addition to the proposed actions, this IM/IRAP/EA presents an assessment of the No Action Alternative. This document also considers an interim remedial action for the removal of radionuclides from beneath the 903 Pad

Radiation shielding and dose rate evaluation at the interim storage facility for spent fuel from Cernavoda NPP

International Nuclear Information System (INIS)

Stanciu, Marcela; Mateescu, Silvia; Pantazi, Doina; Penescu, Maria

2000-01-01

At present studies necessary to license the Interim Storage Facility for the Spent Fuel (CANDU type) from Cernavoda NPP are developed in our country.The spent fuel from Cernavoda NPP is discharged into Spent Fuel Bay in Service Building of the plant, where it remains several years for cooling. After this period, the bundles of spent fuel are to be transferred to the Interim Storage Facility.The dry interim storage solution seems to be the most appropriate variant for Cernavoda NPP.The design of the Spent Fuel Interim Storage Facility must meet the applicable safety requirements in order to ensure radiological protection of the personnel, public and environment during all phases of the facility achievement. In this paper we intend to present the calculation of radiation shielding at the spent fuel interim storage facility for two technical solutions: - Concrete Monolithic Module and Concrete Storage Cask. In order to quantify the fuel composition after irradiation, the isotope generation and depletion code ORIGEN 2.1 has been used, taking into account a cooling time of 7 years and 9 years, respectively, for these two variants. The shielding calculations have been performed using the computer codes QAD-5K and MICROSHIELD-4. The evaluations refer only to gamma radiation because the resulting neutron source (from (α,n) reactions and spontaneous fission) is insignificant as compared to the gamma source. The final results consist in the minimum thickness of the shielding and the corresponding external dose rates, ensuring a design average dose rate based on national and international regulations. (authors)

Decision on performing interim analysis for comparative clinical trials.

Science.gov (United States)

Pak, Kyongsun; Jacobus, Susanna; Uno, Hajime

2017-09-01

In randomized-controlled trials, interim analyses are often planned for possible early trial termination to claim superiority or futility of a new therapy. While unblinding is necessary to conduct the formal interim analysis in blinded studies, blinded data also have information about the potential treatment difference between the groups. We developed a blinded data monitoring tool that enables investigators to predict whether they observe such an unblinded interim analysis results that supports early termination of the trial. Investigators may skip some of the planned interim analyses if an early termination is unlikely. We specifically focused on blinded, randomized-controlled studies to compare binary endpoints of a new treatment with a control. Assuming one interim analysis is planned for early termination for superiority or futility, we conducted extensive simulation studies to assess the impact of the implementation of our tool on the size, power, expected number of interim analyses, and bias in the treatment effect. The numerical study showed the proposed monitoring tool does not affect size or power, but dramatically reduces the expected number of interim analyses when the effect of the treatment difference is small. The tool serves as a useful reference when interpreting the summary of the blinded data throughout the course of the trial, without losing integrity of the study. This tool could potentially save the study resources and budget by avoiding unnecessary interim analyses.

Sustainable Solutions for Nuclear used Fuels Interim Storage

International Nuclear Information System (INIS)

Arslan, Marc; Favet, Dominique; Issard, Herve; Le Jemtel, Amaury; Drevon, Caroline

2014-01-01

AREVA has a unique experience in providing sustainable solutions for used fuel management, fitted with the needs of different customers in the world and with regulation in different countries. These solutions entail both recycling and interim storage technologies. In a first part, we will describe the various types of solutions for Interim Storage of UNF that have been implemented around the world for interim storage at reactor or centralized Pad solution in canisters dry storage, vault type storages for dry storage, dry storage of transportation casks (dual purpose) pools for wet storage, The experience for all these different families of interim storages in which AREVA is involved is extensive and will be discussed with respect to the new challenges: increase of the duration of the interim storage (long term interim storage) increase of burn up of the fuels In a second part of the presentation, special recycling features will be presented. In that case, interim storage of the used fuels is ensured in pools. This provides in the long term good conditions for the behaviour of the fuel and its retrievability. With recycling, the final waste (Universal Canister of vitrified fission products and compacted hulls and end pieces): is stable and licensed in many countries for the final disposal (France, UK, Belgium, NL, Switzerland, Germany, Japan, upcoming: Spain, Australia, Italy). Presents neither safety criticality risks nor proliferation risks (AREVA conditioned HLW and LL-ILW are free of IAEA safeguard constraints thanks to AREVA process high recovery and purification yields). It can therefore be safely stored in interim storage for more than 100 years before final disposal. Some economic considerations will also be discussed. In particular, in the case of long term interim storage of used fuels, there are growing uncertainties regarding the future needs of repackaging and transportation, which can result in future cost overruns. Meanwhile, in the recycling policy

Retention of long-term interim restorations with sodium fluoride enriched interim cement

Science.gov (United States)

Strash, Carolyn

Purpose: Interim fixed dental prostheses, or "provisional restorations", are fabricated to restore teeth when definitive prostheses are made indirectly. Patients undergoing extensive prosthodontic treatment frequently require provisionalization for several months or years. The ideal interim cement would retain the restoration for as long as needed and still allow for ease of removal. It would also avoid recurrent caries by preventing demineralization of tooth structure. This study aims to determine if adding sodium fluoride varnish to interim cement may assist in the retention of interim restorations. Materials and methods: stainless steel dies representing a crown preparation were fabricated. Provisional crowns were milled for the dies using CAD/CAM technology. Crowns were provisionally cemented onto the dies using TempBond NE and NexTemp provisional cements as well as a mixture of TempBond NE and Duraphat fluoride varnish. Samples were stored for 24h then tested or thermocycled for 2500 or 5000 cycles before being tested. Retentive strength of each cement was recorded using a universal testing machine. Results: TempBond NE and NexTemp cements performed similarly when tested after 24h. The addition of Duraphat significantly decreased the retention when added to TempBond NE. NexTemp cement had high variability in retention over all tested time periods. Thermocycling for 2500 and 5000 cycles significantly decreased the retention of all cements. Conclusions: The addition of Duraphat fluoride varnish significantly decreased the retention of TempBond NE and is therefore not recommended for clinical use. Thermocycling significantly reduced the retention of TempBond NE and NexTemp. This may suggest that use of these cements for three months, as simulated in this study, is not recommended.

The Nord interim store

International Nuclear Information System (INIS)

Leushacke, D.F.; Rittscher, D.

1996-01-01

In line with the decision taken in 1990 to shut down and decommission the Greifswald and Rheinsberg Nuclear Power Stations, the waste management concept of the Energiewerke Nord is based on direct and complete decommissioning of the six shut down reactor units within the next fifteen years. One key element of this concept is the construction and use of the Zwischenlager Nord (Nord Interim Store, ZLN) for holding the existing nuclear fuels and for interim and decay storage of the radioactive materials arising in decommissioning and demolition. The owner and operator of the store is Energiewerke Nord GmbH. The interim store has the functions of a processing and Energiewerke Nord GmbH. The interim store has the functions of a processing and treatment station and buffer store for the flows of residues arising. As a radioactive waste management station, it accommodates nuclear fuels, radioactive waste or residues which are not treated any further. It is used as a buffer store to allow the materials accumulating in disassembly to be stored temporarily before or after treatment in order to ensure continuous loading of the treatment plants. When operated as a processing station, the ZLN is able to handle nearly all types of radioactive waste and residues arising, except for nuclear fuels. These installations allow the treatment of radioactive residues to be separated from the demolition work both physically and in time. The possibilities of interium storage and buffer storage of untreated waste and waste packages make for high flexibility in logistics and waste management strategy. (orig.) [de

Interim storage of radioactive waste packages

International Nuclear Information System (INIS)

1998-01-01

This report covers all the principal aspects of production and interim storage of radioactive waste packages. The latest design solutions of waste storage facilities and the operational experiences of developed countries are described and evaluated in order to assist developing Member States in decision making and design and construction of their own storage facilities. This report is applicable to any category of radioactive waste package prepared for interim storage, including conditioned spent fuel, high level waste and sealed radiation sources. This report addresses the following issues: safety principles and requirements for storage of waste packages; treatment and conditioning methods for the main categories of radioactive waste; examples of existing interim storage facilities for LILW, spent fuel and high level waste; operational experience of Member States in waste storage operations including control of storage conditions, surveillance of waste packages and observation of the behaviour of waste packages during storage; retrieval of waste packages from storage facilities; technical and administrative measures that will ensure optimal performance of waste packages subject to various periods of interim storage

Status of national programmes on fast reactors 1998/99. 32nd annual meeting. Working material

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-07-01

Over the past 32 years, the IAEA has actively encouraged and advocated international cooperation in fast reactor technology. The present publication contains information on the status of fast reactor development and on worldwide activities in this advanced nuclear power technology during 1998/1999, as reported at the 32. annual meeting of the International Working Group on Fast Reactors. It is intended to provide information regarding the current status of LMFR development in IAEA Member States.

Status of national programmes on fast reactors 1998/99. 32nd annual meeting. Working material

International Nuclear Information System (INIS)

1999-01-01

Over the past 32 years, the IAEA has actively encouraged and advocated international cooperation in fast reactor technology. The present publication contains information on the status of fast reactor development and on worldwide activities in this advanced nuclear power technology during 1998/1999, as reported at the 32. annual meeting of the International Working Group on Fast Reactors. It is intended to provide information regarding the current status of LMFR development in IAEA Member States

Department of Energy Plutonium ES ampersand H Vulnerability Assessment Savannah River Site interim compensatory measures

International Nuclear Information System (INIS)

Bickford, W.E.

1994-01-01

The Savannah River Site (SRS) has recently completed a self-assessment of potential vulnerabilities associated with plutonium and other transuranic materials stored at the site. An independent Working Group Assessment Team (WGAT) appointed by DOE/ES ampersand H also performed an independent assessment, and reviewed and validated the site self-assessment. The purpose of this report is to provide a status of interim compensatory measures at SRS to address hazards in advance of any corrective actions. ES ampersand H has requested this status for all vulnerabilities ranked medium or higher with respect to potential consequences to workers, environment, and the public

76 FR 58790 - Notice of Interim Approval

Science.gov (United States)

2011-09-22

... to the customers. Rate Scenario 3--Original Cumberland Marketing Policy The third rate alternative... an interim basis to the customers. Rate Scenario 3--Original Cumberland Marketing Policy The third... allocated on an interim basis to the customers. Rate Scenario 3--Original Cumberland Marketing Policy The...

The Interim Financial Statements: The Case of Greece

OpenAIRE

Rogdaki, E.I.; Kazantzis, Ch.

1999-01-01

The following paper refers to the accounting and auditing issues which emerge in the preparation of the interim financial statements of the companies: Firstly, the interim financial statements are defined as being the financial statements that provide useful information about the financial position and the financial results of a company which are realized and accrued during the fiscal year. The interim financial statements can be prepared on a monthly basis, on a quarterly basis or covering a...

Status of the Galileo interim radiation electron model

Science.gov (United States)

Garrett, H. B.; Jun, I.; Ratliff, J. M.; Evans, R. W.; Clough, G. A.; McEntire, R. W.

2003-04-01

Measurements of the high energy, omni-directional electron environment by the Galileo spacecraft Energetic Particle Detector (EPD) were used to develop a new model of Jupiter's trapped electron radiation in the jovian equatorial plane for the range 8 to 16 Jupiter radii (1 jovian radius = 71,400 km). 10-minute averages of these data formed an extensive database of observations of the jovian radiation belts between Jupiter orbit insertion (JOI) in 1995 and 2002. These data were then averaged to provide a differential flux spectrum at 0.174, 0.304, 0.527, 1.5, 2.0, 11.0, and 31 MeV in the jovian equatorial plane as a function of radial distance. This omni-directional, equatorial model was combined with the original Divine model of jovian electron radiation to yield estimates of the out-of-plane radiation environment. That model, referred to here as the Galileo Interim Radiation Electron (or GIRE) model, was then used to calculate the Europa mission dose for an average and a 1-sigma worst-case situation. The prediction of the GIRE model is about a factor of 2 lower than the Divine model estimate over the range of 100 to 1000 mils (2.54 to 25.4 mm) of aluminum shielding, but exceeds the Divine model by about 50% for thicker shielding. The model, the steps leading to its creation, and relevant issues and concerns are discussed. While work remains to be done, the GIRE model clearly represents a significant step forward in the study of the jovian radiation environment, and it is a useful and valuable tool for estimating that environment for future space missions.

Mobile Launch Platform Vehicle Assembly Area (SWMU 056) Biosparge Expansion Interim Measures Work Plan

Science.gov (United States)

Burcham, Michael S.; Daprato, Rebecca C.

2016-01-01

This document presents the design details for an Interim Measure (IM) Work Plan (IMWP) for the Mobile Launch Platform/Vehicle Assembly Building (MLPV) Area, located at the John F. Kennedy Space Center (KSC), Florida. The MLPV Area has been designated Solid Waste Management Unit Number 056 (SWMU 056) under KSC's Resource Conservation and Recovery Act (RCRA) Corrective Action Program. This report was prepared by Geosyntec Consultants (Geosyntec) for the National Aeronautics and Space Administration (NASA) under contract number NNK09CA02B and NNK12CA13B, project control number ENV1642. The Advanced Data Package (ADP) presentation covering the elements of this IMWP report received KSC Remediation Team (KSCRT) approval at the December 2015 Team Meeting; the meeting minutes are included in Appendix A.

Effectiveness of interim remedial actions at a radioactive waste facility

International Nuclear Information System (INIS)

Devgun, J.S.; Beskid, N.J.; Peterson, J.M.; Seay, W.M.; McNamee, E.

1989-01-01

Over the past eight years, several interim remedial actions have been taken at the Niagara Falls Storage Site (NFSS), primarily to reduce radon and gamma radiation exposures and to consolidate radioactive waste into a waste containment facility. Interim remedial actions have included capping of vents, sealing of pipes, relocation of the perimeter fence (to limit radon risk), transfer and consolidation of waste, upgrading of storage buildings, construction of a clay cutoff wall (to limit the potential groundwater transport of contaminants), treatment and release of contaminated water, interim use of a synthetic liner, and emplacement of an interim clay cap. An interim waste containment facility was completed in 1986. 6 refs., 3 figs

Reliability Centered Maintenance for Savannah River Site's interim waste management facilities

Energy Technology Data Exchange (ETDEWEB)

Hauer, K.A. (Westinghouse Savannah River Co., Aiken, SC (United States)); Wilson, J.F. (PRC, Inc. (US))

1992-01-01

The application of Reliability Centered Maintenance (RCM) has been shown to be an effective means to optimize maintenance programs or to establish new programs. The key to success of any RCM program is to customize the methodology to meet the specific needs of the implementing organization. This paper discusses how RCM is being used to establish the preventive maintenance program and how the resulting system data is being used to support the Technical Baseline reconstitution effort for the interim Waste Management Division of Westinghouse Savannah River Company (WSRC).

Resource conversation and recovery act (RCRA) Contingency Plan for interim status or permitted units at the Oak Ridge Y-12 Plant

International Nuclear Information System (INIS)

1992-08-01

The official mission of the Y-12 Plant is to serve as a manufacturing technology center for key processes such that capabilities are maintained for safe, secure, reliable, and survivable nuclear weapons systems and other applications of national importance. The Y-12 RCRA Contingency Plan will be reviewed and revised if necessary if the facility RCRA operating permits are revised, the plan is inadequate in an emergency, the procedures herein can be improved, the facility's operations change in a manner that alters the plan, the emergency coordinator changes, or the emergency equipment list changes. Copies of the Y-12 Emergency Management Plan are available at the Plant Shift Superintendent's Office and the Emergency Preparedness Office. This document serves to supplement the Y-12 Emergency Management Plan to be appropriate for all RCRA hazardous waste interim status or permitted treatment, storage, or disposal facilities. The 90-day storage areas at the Y-12 Plant have a separate contingency supplement as required by RCRA and are separate from this supplement

Weight status, gender, and race/ethnicity: are there differences in meeting recommended health behavior guidelines for adolescents?

Science.gov (United States)

Minges, Karl E; Chao, Ariana; Nam, Soohyun; Grey, Margaret; Whittemore, Robin

2015-04-01

Healthy behaviors including limited screen time (ST), high physical activity (PA), and adequate fruits and vegetables consumption (FV) are recommended for adolescents, but it is unclear how gender, race/ethnicity, and weight status relate to these public health guidelines in diverse urban adolescents. Participants (N = 384) were recruited from three public high schools in or near New Haven, Connecticut. Descriptive statistics and logistic regression analyses were conducted. Most adolescents exceeded recommended levels of ST (70.5%) and did not meet guidelines for PA (87.2%) and FV (72.6%). Only 3.5% of the sample met all three guidelines. Boys were more likely to meet guidelines for PA (p differences in meeting ST, PA, or FV guidelines by weight status for the overall sample or when stratified by gender or race/ethnicity. We found alarmingly low levels of healthy behaviors in normal weight and overweight/obese adolescents. © The Author(s) 2014.

First interim project review meeting on management of water hyacinth

International Nuclear Information System (INIS)

1980-01-01

The first project planning meeting was held in New Delhi during 1978 and the second, a project review meeting, in Papua New Guinea during June 1979, both funded by UNEP. Reports from the regional coordinators for Bangladesh, Malaysia, Sri Lanka, Fiji and India are presented. Also presented are reports from the national coordinators for Malaysia, Bangladesh and India. Two visits (a visit to India, Bangladesh and Sri Lanka to study the feasibility of making a film on the work done with water hyacinth and a visit to the U.S. by the regional project coordinator) are also described

An Approach for Evaluating the Technical Quality of Interim Assessments

Science.gov (United States)

Li, Ying; Marion, Scott; Perie, Marianne; Gong, Brian

2010-01-01

Increasing numbers of schools and districts have expressed interest in interim assessment systems to prepare for summative assessments and to improve teaching and learning. However, with so many commercial interim assessments available, schools and districts are struggling to determine which interim assessment is most appropriate to their needs.…

Disposal facility data for the interim performance

International Nuclear Information System (INIS)

Eiholzer, C.R.

1995-01-01

The purpose of this report is to identify and provide information on the waste package and disposal facility concepts to be used for the low-level waste tank interim performance assessment. Current concepts for the low-level waste form, canister, and the disposal facility will be used for the interim performance assessment. The concept for the waste form consists of vitrified glass cullet in a sulfur polymer cement matrix material. The waste form will be contained in a 2 x 2 x 8 meter carbon steel container. Two disposal facility concepts will be used for the interim performance assessment. These facility concepts are based on a preliminary disposal facility concept developed for estimating costs for a disposal options configuration study. These disposal concepts are based on vault type structures. None of the concepts given in this report have been approved by a Tank Waste Remediation Systems (TWRS) decision board. These concepts will only be used in th interim performance assessment. Future performance assessments will be based on approved designs

Subsurface Interim Measures/Interim Remedial Action Plan/ Environmental Assessment and Decision Document, Operable Unit No. 2

International Nuclear Information System (INIS)

1992-01-01

The subject Interim Measures/Interim Remedial Action plan/Environmental Assessment (IM/IRAP/EA) addresses residual free-phase volatile organic compound (VOC) contamination suspected in the subsurface within an area identified as Operable Unit No. 2 (OU2). This IM/IRAP/EA also addresses radionuclide contamination beneath the 903 Pad at OU2. Although subsurface VOC and radionuclide contamination on represent a source of OU2 ground-water contamination, they pose no immediate threat to public health or the environment. This volume contains five appendices

Reliability Centered Maintenance for Savannah River Site`s interim waste management facilities. Revision 1

Energy Technology Data Exchange (ETDEWEB)

Hauer, K.A. [Westinghouse Savannah River Co., Aiken, SC (United States); Wilson, J.F. [PRC, Inc. (US)

1992-06-01

The application of Reliability Centered Maintenance (RCM) has been shown to be an effective means to optimize maintenance programs or to establish new programs. The key to success of any RCM program is to customize the methodology to meet the specific needs of the implementing organization. This paper discusses how RCM is being used to establish the preventive maintenance program and how the resulting system data is being used to support the Technical Baseline reconstitution effort for the interim Waste Management Division of Westinghouse Savannah River Company (WSRC).

Yucca Mountain socioeconomic project: An interim report on the State of Nevada socioeconomic studies

International Nuclear Information System (INIS)

1989-06-01

The State of Nevada formally initiated a study of the socioeconomic impacts of a proposed high-level nuclear waste repository at Yucca Mountain in southern Nevada in 1986 after the Nevada site had been chosen as a potential waste disposal site. The State and affected local governments that participated in the development of the study recognized that the effort would need to go well beyond what is traditionally considered adequate for socioeconomic impact assessment because of the unique nature of the repository project. This Interim Report is a report on work in progress and presents findings from the research to date on the potential consequences of a repository for the citizens of Nevada. The research and findings in the Report have been subjected to rigorous peer review as part of the state's effort to insure independent, objective analysis that meets the highest professional standards. The basic research effort will continue through June 1990 and will enable the state to refine and clarify the findings presented in this Interim Report

CMM Interim Check Design of Experiments (U)

Energy Technology Data Exchange (ETDEWEB)

Montano, Joshua Daniel [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-07-29

Coordinate Measuring Machines (CMM) are widely used in industry, throughout the Nuclear Weapons Complex and at Los Alamos National Laboratory (LANL) to verify part conformance to design definition. Calibration cycles for CMMs at LANL are predominantly one year in length and include a weekly interim check to reduce risk. The CMM interim check makes use of Renishaw’s Machine Checking Gauge which is an off-the-shelf product simulates a large sphere within a CMM’s measurement volume and allows for error estimation. As verification on the interim check process a design of experiments investigation was proposed to test a couple of key factors (location and inspector). The results from the two-factor factorial experiment proved that location influenced results more than the inspector or interaction.

Permitting plan for the high-level waste interim storage

International Nuclear Information System (INIS)

Deffenbaugh, M.L.

1997-01-01

This document addresses the environmental permitting requirements for the transportation and interim storage of solidified high-level waste (HLW) produced during Phase 1 of the Hanford Site privatization effort. Solidified HLW consists of canisters containing vitrified HLW (glass) and containers that hold cesium separated during low-level waste pretreatment. The glass canisters and cesium containers will be transported to the Canister Storage Building (CSB) in a U.S. Department of Energy (DOE)-provided transportation cask via diesel-powered tractor trailer. Tri-Party Agreement (TPA) Milestone M-90 establishes a new major milestone, and associated interim milestones and target dates, governing acquisition and/or modification of facilities necessary for: (1) interim storage of Tank Waste Remediation Systems (TWRS) immobilized HLW (IHLW) and other canistered high-level waste forms; and (2) interim storage and disposal of TWRS immobilized low-activity tank waste (ILAW). An environmental requirements checklist and narrative was developed to identify the permitting path forward for the HLW interim storage (HLWIS) project (See Appendix B). This permitting plan will follow the permitting logic developed in that checklist

Status of ERDA TRU waste packaging study

International Nuclear Information System (INIS)

Doty, J.W. Jr.

1977-01-01

This paper discusses the status of Task 3 of the TRU Waste Cyclone Drum Incinerator and Treatment System program. This task covers acceptable TRU packaging for interim storage and terminal isolation. The kind of TRU wastes generated by contractors and its transport are discussed. Both drum and box systems are desirable

Evaluation of ERA-Interim precipitation data in complex terrain

Science.gov (United States)

Gao, Lu; Bernhardt, Matthias; Schulz, Karsten

2013-04-01

Precipitation controls a large variety of environmental processes, which is an essential input parameter for land surface models e.g. in hydrology, ecology and climatology. However, rain gauge networks provides the necessary information, are commonly sparse in complex terrains, especially in high mountainous regions. Reanalysis products (e.g. ERA-40 and NCEP-NCAR) as surrogate data are increasing applied in the past years. Although they are improving forward, previous studies showed that these products should be objectively evaluated due to their various uncertainties. In this study, we evaluated the precipitation data from ERA-Interim, which is a latest reanalysis product developed by ECMWF. ERA-Interim daily total precipitation are compared with high resolution gridded observation dataset (E-OBS) at 0.25°×0.25° grids for the period 1979-2010 over central Alps (45.5-48°N, 6.25-11.5°E). Wet or dry day is defined using different threshold values (0.5mm, 1mm, 5mm, 10mm and 20mm). The correspondence ratio (CR) is applied for frequency comparison, which is the ratio of days when precipitation occurs in both ERA-Interim and E-OBS dataset. The result shows that ERA-Interim captures precipitation occurrence very well with a range of CR from 0.80 to 0.97 for 0.5mm to 20mm thresholds. However, the bias of intensity increases with rising thresholds. Mean absolute error (MAE) varies between 4.5 mm day-1 and 9.5 mm day-1 in wet days for whole area. In term of mean annual cycle, ERA-Interim almost has the same standard deviation of the interannual variability of daily precipitation with E-OBS, 1.0 mm day-1. Significant wet biases happened in ERA-Interim throughout warm season (May to August) and dry biases in cold season (November to February). The spatial distribution of mean annual daily precipitation shows that ERA-Interim significant underestimates precipitation intensity in high mountains and northern flank of Alpine chain from November to March while pronounced

12 CFR 541.18 - Interim Federal savings association.

Science.gov (United States)

2010-01-01

... an existing savings and loan holding company or to facilitate any other transaction the Office may... 12 Banks and Banking 5 2010-01-01 2010-01-01 false Interim Federal savings association. 541.18... REGULATIONS AFFECTING FEDERAL SAVINGS ASSOCIATIONS § 541.18 Interim Federal savings association. The term...

Single-shell tank interim stabilization project plan

Energy Technology Data Exchange (ETDEWEB)

Ross, W.E.

1998-03-27

Solid and liquid radioactive waste continues to be stored in 149 single-shell tanks at the Hanford Site. To date, 119 tanks have had most of the pumpable liquid removed by interim stabilization. Thirty tanks remain to be stabilized. One of these tanks (C-106) will be stabilized by retrieval of the tank contents. The remaining 29 tanks will be interim stabilized by saltwell pumping. In the summer of 1997, the US Department of Energy (DOE) placed a moratorium on the startup of additional saltwell pumping systems because of funding constraints and proposed modifications to the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) milestones to the Washington State Department of Ecology (Ecology). In a letter dated February 10, 1998, Final Determination Pursuant to Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) in the Matter of the Disapproval of the DOE`s Change Control Form M-41-97-01 (Fitzsimmons 1998), Ecology disapproved the DOE Change Control Form M-41-97-01. In response, Fluor Daniel Hanford, Inc. (FDH) directed Lockheed Martin Hanford Corporation (LNMC) to initiate development of a project plan in a letter dated February 25, 1998, Direction for Development of an Aggressive Single-Shell Tank (SST) Interim Stabilization Completion Project Plan in Support of Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement). In a letter dated March 2, 1998, Request for an Aggressive Single-Shell Tank (SST) Interim Stabilization Completion Project Plan, the DOE reaffirmed the need for an aggressive SST interim stabilization completion project plan to support a finalized Tri-Party Agreement Milestone M-41 recovery plan. This project plan establishes the management framework for conduct of the TWRS Single-Shell Tank Interim Stabilization completion program. Specifically, this plan defines the mission needs and requirements; technical objectives and approach; organizational structure, roles, responsibilities

Single-shell tank interim stabilization project plan

International Nuclear Information System (INIS)

Ross, W.E.

1998-01-01

Solid and liquid radioactive waste continues to be stored in 149 single-shell tanks at the Hanford Site. To date, 119 tanks have had most of the pumpable liquid removed by interim stabilization. Thirty tanks remain to be stabilized. One of these tanks (C-106) will be stabilized by retrieval of the tank contents. The remaining 29 tanks will be interim stabilized by saltwell pumping. In the summer of 1997, the US Department of Energy (DOE) placed a moratorium on the startup of additional saltwell pumping systems because of funding constraints and proposed modifications to the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) milestones to the Washington State Department of Ecology (Ecology). In a letter dated February 10, 1998, Final Determination Pursuant to Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) in the Matter of the Disapproval of the DOE's Change Control Form M-41-97-01 (Fitzsimmons 1998), Ecology disapproved the DOE Change Control Form M-41-97-01. In response, Fluor Daniel Hanford, Inc. (FDH) directed Lockheed Martin Hanford Corporation (LNMC) to initiate development of a project plan in a letter dated February 25, 1998, Direction for Development of an Aggressive Single-Shell Tank (SST) Interim Stabilization Completion Project Plan in Support of Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement). In a letter dated March 2, 1998, Request for an Aggressive Single-Shell Tank (SST) Interim Stabilization Completion Project Plan, the DOE reaffirmed the need for an aggressive SST interim stabilization completion project plan to support a finalized Tri-Party Agreement Milestone M-41 recovery plan. This project plan establishes the management framework for conduct of the TWRS Single-Shell Tank Interim Stabilization completion program. Specifically, this plan defines the mission needs and requirements; technical objectives and approach; organizational structure, roles, responsibilities

76 FR 540 - National Conference on Weights and Measures 2011 Interim Meeting

Science.gov (United States)

2011-01-05

... and representatives of business, industry, trade associations, and consumer organizations on subjects...'' which contains meeting agendas, registration forms and hotel reservation information at http://www.ncwm... Retail Motor Fuel Dispenser (RMFD) Price Posting and Computer Capability will meet from 1:30 to 4 p.m. on...

40 CFR 80.141 - Interim detergent gasoline program.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 16 2010-07-01 2010-07-01 false Interim detergent gasoline program. 80... (CONTINUED) REGULATION OF FUELS AND FUEL ADDITIVES Detergent Gasoline § 80.141 Interim detergent gasoline... apply to: (i) All gasoline sold or transferred to a party who sells or transfers gasoline to the...

Transport, handling, and interim storage of intermediate-level transuranic waste at the INEL

International Nuclear Information System (INIS)

Metzger, J.C.; Snyder, A.M.

1977-09-01

The Idaho National Engineering Laboratory stores transuranic (TRU)-contaminated waste emitting significant amounts of beta-gamma radiation. This material is referred to as intermediate-level TRU waste. The Energy Research and Development Administration requires that this waste be stored retrievably during the interim before a Federal repository becomes operational. Waste form and packaging criteria for the eventual storage of this waste at a Federal repository, i.e., the Waste Isolation Pilot Plant (WIPP), have been tentatively established. The packaging and storage techniques now in use at the Idaho National Engineering Laboratory are compatible with these criteria and also meet the requirement that the waste containers remain in a readily-retrievable, contamination-free condition during the interim storage period. The Intermediate Level Transuranic Storage Facility (ILTSF) provides below-grade storage in steel pipe vaults for intermediate-level TRU waste prior to shipment to the WIPP. Designated waste generating facilities, operated for the Energy Research and Development Administration, use a variety of packaging and transportation methods to deliver this waste to the ILTSF. Transfer of the waste containers to the ILTSF storage vaults is accomplished using handling methods compatible with these waste packaging and transport methods

COMPLETION OF THE FIRST INTEGRATED SPENT NUCLEAR FUEL TRANSSHIPMENT/INTERIM STORAGE FACILITY IN NW RUSSIA

International Nuclear Information System (INIS)

Dyer, R.S.; Barnes, E.; Snipes, R.L.; Hoeibraaten, S.; Gran, H.C.; Foshaug, E.; Godunov, V.

2003-01-01

Northwest and Far East Russia contain large quantities of unsecured spent nuclear fuel (SNF) from decommissioned submarines that potentially threaten the fragile environments of the surrounding Arctic and North Pacific regions. The majority of the SNF from the Russian Navy, including that from decommissioned nuclear submarines, is currently stored in on-shore and floating storage facilities. Some of the SNF is damaged and stored in an unstable condition. Existing Russian transport infrastructure and reprocessing facilities cannot meet the requirements for moving and reprocessing this amount of fuel. Additional interim storage capacity is required. Most of the existing storage facilities being used in Northwest Russia do not meet health and safety, and physical security requirements. The United States and Norway are currently providing assistance to the Russian Federation (RF) in developing systems for managing these wastes. If these wastes are not properly managed, they could release significant concentrations of radioactivity to these sensitive environments and could become serious global environmental and physical security issues. There are currently three closely-linked trilateral cooperative projects: development of a prototype dual-purpose transport and storage cask for SNF, a cask transshipment interim storage facility, and a fuel drying and cask de-watering system. The prototype cask has been fabricated, successfully tested, and certified. Serial production is now underway in Russia. In addition, the U.S. and Russia are working together to improve the management strategy for nuclear submarine reactor compartments after SNF removal

Modernization and refurbishment of the Central Interim Storage

International Nuclear Information System (INIS)

Mele, I.; Zeleznik, N.

2002-01-01

The Central Interim Storage for radioactive waste in Brinje, being put into operation in 1986, needs refurbishment and modernization in order to meet the up-to-date operational and safety requirements and to ensure the normal and undisturbed acceptance of radioactive waste from small producers in the future. Because of the waste, being already stored in the storage, the lack of reprocessing capacities and the lack of auxiliary room, the refurbishment and modernization is a complex problem, which needs to be addressed with care. The plan of refurbishment and modernization requires an integral approach, covering all different aspects of renewal and reconstruction. The implementation plan, however, must be based on the actual state of the storage and real conditions for the implementations: from technical to financial. In this paper the project for refurbishment and modernization of the storage, and some activities that have already been implemented, are presented.(author)

Operational Implementation of the MARSSIM Process at the Wayne Interim Storage Site

International Nuclear Information System (INIS)

Hays, D. C. Jr.; Trujillo, P. A. IV.; Zoller, S. G.

2002-01-01

This paper describes the methodologies behind the operational implementation of the Multi Agency Radiation Site Survey and Investigation Manual (MARSSIM) process at the Wayne Interim Storage Site (WISS). The United States Army Corps of Engineers (USACE) and Environmental Chemical Corporation (ECC) have implemented the MARSSIM process using various surveys producing raw data. The final remedial status of a survey unit is derived through data reduction, while maintaining a high degree of efficiency in the construction aspects of the remedial action. Data reduction of field measurements is accomplished by merging the data outputs of a Digital Global Positioning System, an exposure rate meter, and laboratory analyses to produce maps which present exposure rates, elevations, survey unit boundaries, direct measurement locations, and sampling locations on a single map. The map serves as a data-posting plot and allows the project team to easily judge the survey unit's remedial status. The operational implementation of the MARSSIM process has been successful in determining the eligibility of survey units for final status surveys at the WISS and also in demonstrating final status radiological and chemical conditions while maintaining an efficient remedial action effort

Micro-CHP Technologies Roadmap: Meeting 21st Century Residential Energy Needs

Energy Technology Data Exchange (ETDEWEB)

none,

2003-12-01

On June 11-12, 2003, at Greenbelt, Maryland, key stakeholders from industry, government agencies, universities, and others involved in combined heat and power and the residential buildings industry explores solutions to technical, institutional, and market barriers facing micro-combined heat and power systems (mCHP). Participants outlined a desired future for mCHP systems, identified specific interim technology cost and performance targets, and developed actions to achieve the interim targets and vision. This document, The Micro-CHP Technologies Roadmap, is a result of their deliberations. It outlines a set of actions that can be pursued by both the government and industry to develop mCHP appliances for creating a new approach for households to meet their energy needs.

Design review report FFTF interim storage cask

International Nuclear Information System (INIS)

Scott, P.L.

1995-01-01

Final Design Review Report for the FFTF Interim Storage Cask. The Interim Storage Cask (ISC) will be used for long term above ground dry storage of FFTF irradiated fuel in Core Component Containers (CCC)s. The CCC has been designed and will house assemblies that have been sodium washed in the IEM Cell. The Solid Waste Cask (SWC) will transfer a full CCC from the IEM Cell to the RSB Cask Loading Station where the ISC will be located to receive it. Once the loaded ISC has been sealed at the RSB Cask Loading Station, it will be transferred by facility crane to the DSWC Transporter. After the ISC has been transferred to the Interim Storage Area (ISA), which is yet to be designed, a mobile crane will be used to place the ISC in its final storage location

Choosing a spent fuel interim storage system

International Nuclear Information System (INIS)

Roland, V.; Hunter, I.

2001-01-01

The Transnucleaire Group has developed different modular solutions to address spent fuel interim storage needs of NPP. These solutions, that are present in Europe, USA and Asia are metal casks (dual purpose or storage only) of the TN 24 family and the NUHOMS canister based system. It is not always simple for an operator to sort out relevant choice criteria. After explaining the basic designs involved on the examples of the TN 120 WWER dual purpose cask and the NUHOMS 56 WWER for WWER 440 spent fuel, we shall discuss the criteria that govern the choice of a given spent fuel interim storage system from the stand point of the operator. In conclusion, choosing and implementing an interim storage system is a complex process, whose implications can be far reaching for the long-term success of a spent fuel management policy. (author)

78 FR 67442 - Congestion Mitigation and Air Quality Improvement Program Interim Guidance

Science.gov (United States)

2013-11-12

...] Congestion Mitigation and Air Quality Improvement Program Interim Guidance AGENCY: Federal Highway... Comment. SUMMARY: The FHWA is issuing Interim Guidance on the Congestion Mitigation and Air Quality.../environment/air_quality/cmaq/policy_and_guidance/2008_guidance/ guidance/. DATES: This Interim Guidance is...

47 CFR 51.715 - Interim transport and termination pricing.

Science.gov (United States)

2010-10-01

... 47 Telecommunication 3 2010-10-01 2010-10-01 false Interim transport and termination pricing. 51.715 Section 51.715 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) COMMON CARRIER... Telecommunications Traffic § 51.715 Interim transport and termination pricing. (a) Upon request from a...

ITER Conceptual design: Interim report

International Nuclear Information System (INIS)

1990-01-01

This interim report describes the results of the International Thermonuclear Experimental Reactor (ITER) Conceptual Design Activities after the first year of design following the selection of the ITER concept in the autumn of 1988. Using the concept definition as the basis for conceptual design, the Design Phase has been underway since October 1988, and will be completed at the end of 1990, at which time a final report will be issued. This interim report includes an executive summary of ITER activities, a description of the ITER device and facility, an operation and research program summary, and a description of the physics and engineering design bases. Included are preliminary cost estimates and schedule for completion of the project

A comparison of the value relevance of interim and annual financial statements

Directory of Open Access Journals (Sweden)

Mbalenhle Zulu

2017-03-01

Aim: It explores whether the value relevance of interim financial statements is higher than the value relevance of annual financial statements. Finally, it investigates whether accounting information published in interim and annual financial statements has incremental value relevance. Setting: Data for the period from 1999 to 2012 were collected from a sample of non-financial companies listed on the Johannesburg Stock Exchange. Method: The Ohlson model to investigate the value relevance of accounting information was used for the study. Results: The results show that interim book value of equity is value relevant while interim earnings are not. Interim financial statements appear to have higher value relevance than annual financial statements. The value relevance of interim and annual accounting information has remained fairly constant over the sample period. Incremental comparisons provide evidence that additional book value of equity and earnings that accrue to a company between interim and annual reporting dates are value relevant. Conclusion: The study was conducted over a long sample period (1999–2012, in an era when a technology-driven economy and more timely reporting media could have had an effect on the value relevance of published accounting information. To the best of our knowledge, this is the first study to evaluate and compare the value relevance of published interim and annual financial statements.

Current Status and Open Issues of the 235U Evaluation. Summary Report of an IAEA Consultants’ Meeting

International Nuclear Information System (INIS)

Noguere, Gilles; Trkov, Andrej

2016-08-01

The objective of this consultancy meeting was to discuss the status of the 235 U neutron cross sections from the thermal to MeV energy ranges, to identify the main difficulties and to propose recommendations for improving the current experimental and evaluation works

Evaluation of Hose in Hose Transfer Line Service Life for Hanfords Interim Stabilization Program

International Nuclear Information System (INIS)

TORRES, T.D.

2001-01-01

RPP-6153, Engineering Task Plan for Hose-in-Hose Transfer System for the Interim Stabilization Program (Torres, 2000a), defines the programmatic goals, functional requirements, and technical criteria for the development and subsequent installation of waste transfer line equipment to support Hanford's Interim Stabilization Program. RPP-6028, Specification for Hose in Hose Transfer Lines for Hanford's Interim Stabilization Program (Torres, 2000b), has been issued to define the specific requirements for the design, manufacture, and verification of transfer line assemblies for specific waste transfer applications associated with Interim Stabilization. Included in RPP-6028 are tables defining the chemical constituents of concern to which transfer lines will be exposed. Current Interim Stabilization Program planning forecasts that the at-grade transfer lines will be required to convey pumpable waste for as much as three years after commissioning, RPP-6028 Section 3.2.7. Performance Incentive Number ORP-05 requires that all the Single Shell Tanks be Interim Stabilized by September 30, 2003. The Tri-Party Agreement (TPA) milestone M-41-00, enforced by a federal consent decree, requires all the Single Shell Tanks to be Interim stabilized by September 30, 2004. By meeting the Performance Incentive the TPA milestone is met. Prudent engineering dictates that the equipment used to transfer waste have a life in excess of the forecasted operational time period, with some margin to allow for future adjustments to the planned schedule. This document evaluates the effective service life of the Hose-in-Hose Transfer Lines, based on information submitted by the manufacturer, published literature and calculations. The effective service life of transfer line assemblies is a function of several factors. Foremost among these are the hose material's resistance to the harmful effects of process fluid characteristics, ambient environmental conditions, exposure to ionizing radiation and the

Single-shell tank interim stabilization risk analysis

International Nuclear Information System (INIS)

Basche, A.D.

1998-01-01

The purpose of the Single-Shell Tank (SST) Interim Stabilization Risk Analysis is to provide a cost and schedule risk analysis of HNF-2358, Rev. 1, Single-Shell Tank Interim Stabilization Project Plan (Project Plan) (Ross et al. 1998). The analysis compares the required cost profile by fiscal year (Section 4.2) and revised schedule completion date (Section 4.5) to the Project Plan. The analysis also evaluates the executability of the Project Plan and recommends a path forward for risk mitigation

TWRS HLW interim storage facility search and evaluation

Energy Technology Data Exchange (ETDEWEB)

Calmus, R.B., Westinghouse Hanford

1996-05-16

The purpose of this study was to identify and provide an evaluation of interim storage facilities and potential facility locations for the vitrified high-level waste (HLW) from the Phase I demonstration plant and Phase II production plant. In addition, interim storage facilities for solidified separated radionuclides (Cesium and Technetium) generated during pretreatment of Phase I Low-Level Waste Vitrification Plant feed was evaluated.

Industrial complementarities between interim storage and reversible geological repository - 59237

International Nuclear Information System (INIS)

Hoorelbeke, Jean-Michel

2012-01-01

The French Act voted in 2006 made the choice of deep geological disposal as the reference option for the long term management of high level (HLW) and intermediate level long-lived waste. The CIGEO repository project aims at avoiding or limiting burden to future generations, which could not be achieved by the extension in time of interim storage. The reversibility as provided by the Act will maintain a liberty of choice for waste management on a duration which is comparable to new storage facility. Interim storage is required to accommodate waste as long as the repository is not available. The commissioning of the repository in 2025 will not suppress needs for interim storage. The paper describes the complementarities between existing and future interim storage facilities and the repository project: repository operational issues and planning, HLW thermal decay, support for the reversibility, etc. It shows opportunities to prepare a global optimization of waste management including the utilization at best of storage capacities and the planning of waste emplacement in the repository in such a way to facilitate operational conditions and to limit cost. Preliminary simulations of storage-disposal scenarios are presented. Thanks to an optimal use of the waste management system, provision can be made for a progressive increase of waste emplacement flow during the first operation phase of the repository. It is then possible to stabilize the industrial activity level of the repository site. An optimal utilization of interim storage can also limit the diversity of waste packages emplaced simultaneously, which facilitates the operation of the repository. 60 years minimum interim storage duration is generally required with respect to HLW thermal output. Extending this interim storage period may reduce the underground footprint of the repository. Regarding reversibility, the capability to manage waste packages potentially retrieved from the repository should be analyzed. The

Interim dry cask storage of irradiated Fast Flux Test Facility fuel

International Nuclear Information System (INIS)

Scott, P.L.

1994-09-01

The Fast Flux Test Facility (FFTF), located at the US Department of Energy's (DOE'S) Hanford Site, is the largest, most modern, liquid metal-cooled test reactor in the world. This paper will give an overview of the FFTF Spent Fuel Off load project. Major discussion areas will address the status of the fuel off load project, including an overview of the fuel off load system and detailed discussion on the individual components that make up the dry cask storage portion of this system. These components consist of the Interim Storage Cask (ISC) and Core Component Container (CCC). This paper will also discuss the challenges that have been addressed in the evolution of this project

Fire Hazards Analysis for the 200 Area Interim Storage Area

International Nuclear Information System (INIS)

JOHNSON, D.M.

2000-01-01

This documents the Fire Hazards Analysis (FHA) for the 200 Area Interim Storage Area. The Interim Storage Cask, Rad-Vault, and NAC-1 Cask are analyzed for fire hazards and the 200 Area Interim Storage Area is assessed according to HNF-PRO-350 and the objectives of DOE Order 5480 7A. This FHA addresses the potential fire hazards associated with the Interim Storage Area (ISA) facility in accordance with the requirements of DOE Order 5480 7A. It is intended to assess the risk from fire to ensure there are no undue fire hazards to site personnel and the public and to ensure property damage potential from fire is within acceptable limits. This FHA will be in the form of a graded approach commensurate with the complexity of the structure or area and the associated fire hazards

Physical protection of shipments of irradiated reactor fuel; Interim guidance. Regulatory report

International Nuclear Information System (INIS)

1980-06-01

During May, 1979, the U.S. Nuclear Regulatory Commission approved for issuance in effective form new interim regulations for strengthening the protection of spent fuel shipments against sabotage and diversion. The new regulations were issued without benefit of public comment, but comments from the public were solicited after the effective date. Based upon the public comments received, the interim regulations were amended and reissued in effective form as a final interim rule in May, 1980. The present document supersedes a previously issued interim guidance document, NUREG-0561 (June, 1979) which accompanied the original rule. This report has been revised to conform to the new interim regulations on the physical protection of shipments of irradiated reactor fuel which are likely to remain in effect until the completion of an ongoing research program concerning the response of spent fuel to certain forms of sabotage, at which time the regulations may be rescinded, modified or made permanent, as appropriate. This report discusses the amended regulations and provides a basis on which licensees can develop an acceptable interim program for the protection of spent fuel shipments

Use of alternative dispute resolution--HHS. Notice of interim policy.

Science.gov (United States)

1992-10-27

The Department has developed an interim policy to address the use of alternative dispute resolution (ADR) as required by the Administrative Dispute Resolution Act (ADR Act), Public Law No. 101-552. This interim policy also responds to the Negotiated Rulemaking Act, Public Law No. 101-648, and relevant elements of the Executive Order on Civil Justice Reform (E.O. 12778). The Department is adopting an interim policy because we need a baseline of experience and knowledge from our own pilot activities and those of other agencies before finalizing a policy.

50 CFR 660.720 - Interim protection for sea turtles.

Science.gov (United States)

2010-10-01

... 50 Wildlife and Fisheries 9 2010-10-01 2010-10-01 false Interim protection for sea turtles. 660.720 Section 660.720 Wildlife and Fisheries FISHERY CONSERVATION AND MANAGEMENT, NATIONAL OCEANIC AND... Migratory Fisheries § 660.720 Interim protection for sea turtles. (a) Until the effective date of §§ 660.707...

CMM Interim Check (U)

Energy Technology Data Exchange (ETDEWEB)

Montano, Joshua Daniel [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-03-23

Coordinate Measuring Machines (CMM) are widely used in industry, throughout the Nuclear Weapons Complex and at Los Alamos National Laboratory (LANL) to verify part conformance to design definition. Calibration cycles for CMMs at LANL are predominantly one year in length. Unfortunately, several nonconformance reports have been generated to document the discovery of a certified machine found out of tolerance during a calibration closeout. In an effort to reduce risk to product quality two solutions were proposed – shorten the calibration cycle which could be costly, or perform an interim check to monitor the machine’s performance between cycles. The CMM interim check discussed makes use of Renishaw’s Machine Checking Gauge. This off-the-shelf product simulates a large sphere within a CMM’s measurement volume and allows for error estimation. Data was gathered, analyzed, and simulated from seven machines in seventeen different configurations to create statistical process control run charts for on-the-floor monitoring.

76 FR 21043 - Notice of Public Meeting: Technical Aspects of Mandatory Deposit of Published Electronic Works...

Science.gov (United States)

2011-04-14

... mandatory deposit requirements of the copyright law. The objective is to identify file submission, packaging... mandatory deposit provisions of the copyright law. Under the interim regulation, certain works available... LIBRARY OF CONGRESS Copyright Office [Docket No. 2011-3] Notice of Public Meeting: Technical...

Interim process report for the safety assessment SR-Can

International Nuclear Information System (INIS)

Sellin, Patrick

2004-08-01

This report is a documentation of buffer processes identified as relevant to the long-term safety of a KBS-3 repository. The report is part of the interim reporting of the safety assessment SR-Can, see further the Interim main report. The final SR-Can reporting will support SKB's application to build an Encapsulation plant for spent nuclear fuel and is to be produced in 2006. The purpose of this report is to document the scientific knowledge of the processes to a level required for an adequate treatment in the safety assessment. The documentation is thus from a scientific point of not exhaustive since such a treatment is neither necessary for the purposes of the safety assessment nor possible within the scope of an assessment. The purpose is further to determine the handling of each process in the safety assessment and to demonstrate how uncertainties are taken care of, given the suggested handling. The process documentation in the SR 97 version of the Process report is a starting point for this SR-Can interim version. As further described in the Interim main report, the list of relevant processes has been reviewed and slightly extended by comparison to other databases. Furthermore, the backfill has been included as a system part of its own, rather than being described together with the buffer as in SR 97. Apart from giving an interim account of the documentation and handling of buffer processes in SR-Can, this report is meant to serve as a template for the forthcoming documentation of processes occurring in other parts of the repository system. A complete list of processes can be found in the Interim FEP report for the safety assessment SR-Can. All material presented in this document is preliminary in nature and will possibly be updated as the SR-Can project progresses

Interim process report for the safety assessment SR-Can

Energy Technology Data Exchange (ETDEWEB)

Sellin, Patrick (ed.)

2004-08-01

This report is a documentation of buffer processes identified as relevant to the long-term safety of a KBS-3 repository. The report is part of the interim reporting of the safety assessment SR-Can, see further the Interim main report. The final SR-Can reporting will support SKB's application to build an Encapsulation plant for spent nuclear fuel and is to be produced in 2006. The purpose of this report is to document the scientific knowledge of the processes to a level required for an adequate treatment in the safety assessment. The documentation is thus from a scientific point of not exhaustive since such a treatment is neither necessary for the purposes of the safety assessment nor possible within the scope of an assessment. The purpose is further to determine the handling of each process in the safety assessment and to demonstrate how uncertainties are taken care of, given the suggested handling. The process documentation in the SR 97 version of the Process report is a starting point for this SR-Can interim version. As further described in the Interim main report, the list of relevant processes has been reviewed and slightly extended by comparison to other databases. Furthermore, the backfill has been included as a system part of its own, rather than being described together with the buffer as in SR 97. Apart from giving an interim account of the documentation and handling of buffer processes in SR-Can, this report is meant to serve as a template for the forthcoming documentation of processes occurring in other parts of the repository system. A complete list of processes can be found in the Interim FEP report for the safety assessment SR-Can. All material presented in this document is preliminary in nature and will possibly be updated as the SR-Can project progresses.

Materials behavior in interim storage of spent fuel

International Nuclear Information System (INIS)

Johnson, A.B. Jr.; Bailey, W.J.; Gilbert, E.R.; Inman, S.C.

1982-01-01

Interim storage has emerged as the only current spent-fuel management method in the US and is essential in all countries with nuclear reactors. Materials behavior is a key aspect in licensing interim-storage facilities for several decades of spent-fuel storage. This paper reviews materials behavior in wet storage, which is licensed for light-water reactor (LWR) fuel, and dry storage, for which a licensing position for LWR fuel is developing

Interim Safety Basis for Fuel Supply Shutdown Facility

International Nuclear Information System (INIS)

BENECKE, M.W.

2000-01-01

This ISB, in conjunction with the IOSR, provides the required basis for interim operation or restrictions on interim operations and administrative controls for the facility until a SAR is prepared in accordance with the new requirements or the facility is shut down. It is concluded that the risks associated with tha current and anticipated mode of the facility, uranium disposition, clean up, and transition activities required for permanent closure, are within risk guidelines

78 FR 49782 - Interim Staff Guidance on Changes During Construction

Science.gov (United States)

2013-08-15

... Construction AGENCY: Nuclear Regulatory Commission. ACTION: Draft interim staff guidance; request for comment... During Construction.'' This ISG provides guidance to the NRC staff on the Preliminary Amendment Request...-ISG-025 ``Interim Staff Guidance on Changes during Construction under 10 CFR Part 52'' is available...

WANTO 32: Proceedings of the 32nd Weapons Agencies Nondestructive Testing Organization meeting

International Nuclear Information System (INIS)

Majzlik, E.J. Jr.

1991-02-01

The Thirty-Second Weapons Agencies Nondestructive Testing Organization (WANTO) meeting was held at the Savannah River Site (SRS) on November 27--29, 1990. The meeting was hosted by Edward J. Majzlik, Jr., Savannah River Laboratory, Westinghouse Savannah River Company (WSRC). The Chairman of the WANTO Steering Committee is L.E. (Larry) Bryant, Los Alamos National Laboratory. This report is the sole proceedings of the meeting and includes the agenda, attendance, steering committee report, interim reports and technical presentation summaries. This report is the first to present the meeting proceedings in an unclassified form. The reader should contact individual authors directly for any additional information desired. The meeting was organized to provide coverage of a wide variety of NDE subjects relevant to the Department of Energy (DOE) Nuclear Weapons Complex (NWC). Approximately 60 technical experts and managers representing 11 DOE weapons agencies and 3 DOE offices attended. A total of 56 technical presentations and 3 special NDE workshops were included in the agenda along with two tours of the SRS Reactor Mock-up Facility. Invited presentations included five speakers who reported on the DOE sponsored conference Concurrent Engineering and the NDE Role held at Sandia National Laboratory, Albuquerque, New Mexico, October 30-November 1, 1990 and X-ray Film Retention and Disposal presented by Orville R. Pratt, DOE/AL-Martin Marietta. The WANTO Steering Committee report for the Thirty-Second Meeting immediately follows this section. The meeting Agenda and Attendance are presented in Appendices A and B, respectively. Technical presentation summaries and abstracts are presented in Appendix C. For cases in which a summary was not provided, a telephone number is offered for direct contact with the author/presenter. Interim Activity Reports are compiled in Appendix D. Special Workshop reports are presented in Appendix E. (JF)

Spent fuel interim management: 1995 update

International Nuclear Information System (INIS)

Anderson, C.K.

1995-01-01

The problems of interim away-from-reactor spent fuel storage and storage in spent fuel pools at the reactor site are discussed. An overview of the state-of-the-art in the USA, Europe, and Japan is presented. The technical facilities for away-from-reactor storage are briefly described, including wet storage pools, interactive concrete systems, metallic containers, and passive concrete systems. Reprocessing technologies are mostly at the design stage only. It is predicted that during the 20 years to come, about 50 000 tonnes of spent fuel will be stored at reactor sites regardless of the advance of spent fuel reprocessing or interim storage projects. (J.B.). 4 tabs., 2 figs

77 FR 31894 - Sunshine Act Meeting Notice, Regular Board of Directors Meeting

Science.gov (United States)

2012-05-30

...,Washington, DC 20005. STATUS: Open. CONTACT PERSON FOR MORE INFORMATION: Erica Hall, Assistant Corporate... Meeting Minutes V. Approval of the Finance, Budget and Program Committee Meeting Minutes VI. Approval of the Corporate Administration Committee Meeting Minutes VII. Executive Session VIII. Board Elections...

General certification procedure of enterprises and interim job enterprises

CERN Document Server

Int. At. Energy Agency, Wien

2002-01-01

This procedure defines the certification global process of enterprises employing workers of A or B category for nuclear facilities and interim job enterprises proposing workers of A or B category for nuclear facilities. This certification proves the enterprises ability to satisfy the specification ''E'' of the CEFRI and the interim job enterprises to satisfy the specification ''I'' of the CEFRI. (A.L.B.)

Status of national programmes on fast reactors 1997/98. 31. annual meeting of the International Working Group on Fast Reactors

International Nuclear Information System (INIS)

1998-01-01

The objective of the meeting was to co-ordinate the exchange of information on the status of fast reactor development and operational experience, including experience with experimental types of reactor; to consider meeting arrangements for 1998 and 1999; and to review the IAEA co-ordinated research activities in the field of fast reactor, as well as co-ordination of the International Working Group on Fast Reactors activities with other organizations

ITER interim design report package and relevant documents

International Nuclear Information System (INIS)

1996-01-01

This publication documents the technical basis which underlay the Interim Design Report, Cost Review and Safety Analysis submitted to the ITER Councils (IC-8 and IC-9) Records of decisions and the ''ITER Interim Design Report Package''. This publication contains ITER Site Requirements and ITER Site Design Assumptions, TAC-8 Report, SRG Report, CP's Report on Tentative Sequence of Events and Parties' Views on the IDR Package and Parties' Technical Comments on the IDR Package. Figs, tabs

Tribal child welfare. Interim final rule.

Science.gov (United States)

2012-01-06

The Administration for Children and Families (ACF) is issuing this interim final rule to implement statutory provisions related to the Tribal title IV-E program. Effective October 1, 2009, section 479B(b) of the Social Security Act (the Act) authorizes direct Federal funding of Indian Tribes, Tribal organizations, and Tribal consortia that choose to operate a foster care, adoption assistance and, at Tribal option, a kinship guardianship assistance program under title IV-E of the Act. The Fostering Connections to Success and Increasing Adoptions Act of 2008 requires that ACF issue interim final regulations which address procedures to ensure that a transfer of responsibility for the placement and care of a child under a State title IV-E plan to a Tribal title IV-E plan occurs in a manner that does not affect the child's eligibility for title IV-E benefits or medical assistance under title XIX of the Act (Medicaid) and such services or payments; in-kind expenditures from third-party sources for the Tribal share of administration and training expenditures under title IV-E; and other provisions to carry out the Tribal-related amendments to title IV-E. This interim final rule includes these provisions and technical amendments necessary to implement a Tribal title IV-E program.

Presidential Transition: The Experience of Two Community College Interim Presidents

Science.gov (United States)

Thompson, Matthew D.

2010-01-01

The purpose of this qualitative case study was to understand the experiences of two community college interim presidents, their characteristics, and how they led institutions following an abrupt presidential departure. There were two fundamental questions framing this research study, 1. How do two interim community college presidents lead…

30 CFR 827.13 - Coal preparation plants: Interim performance standards.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 3 2010-07-01 2010-07-01 false Coal preparation plants: Interim performance...-COAL PREPARATION PLANTS NOT LOCATED WITHIN THE PERMIT AREA OF A MINE § 827.13 Coal preparation plants: Interim performance standards. (a) Persons operating or who have operated coal preparation plants after...

Fast Flux Test Facility interim examination and maintenance cell: Past, present, and future

International Nuclear Information System (INIS)

Vincent, J.R.

1990-09-01

The Fast Flux Test Facility Interim Examination and Maintenance Cell was designed to perform interim examination and/or disassembly of experimental core components for final analysis elsewhere, as well as maintenance of sodium-wetted or neutron-activated internal reactor parts and plant support hardware. The Interim Examination and Maintenance Cell equipment developed and used for the first ten years of operation has been primarily devoted to the disassembly and examination of core component test assemblies. While no major reactor equipment has required remote repair or maintenance, the Interim Examina Examination and Maintenance Cell has served as the remote repair facility for its own in-cell equipment, and several innovative remote repairs have been accomplished. The Interim Examination and Maintenance Cell's demonstrated versatility has shown its capability to support a challenging future. 12 refs., 9 figs

Project management plan for the 105-C Reactor interim safe storage project. Revision 1

International Nuclear Information System (INIS)

Miller, R.L.

1997-01-01

In 1942, the Hanford Site was commissioned by the US Government to produce plutonium. Between 1942 and 1955, eight water-cooled, graphite-moderated reactors were constructed along the Columbia River at the Hanford Site to support the production of plutonium. The reactors were deactivated from 1964 to 1971 and declared surplus. The Surplus Production Reactor Decommissioning Project (BHI 1994b) will decommission these reactors and has selected the 105-C Reactor to be used as a demonstration project for interim safe storage at the present location and final disposition of the entire reactor core in the 200 West Area. This project will result in lower costs, accelerated schedules, reduced worker exposure, and provide direct benefit to the US Department of Energy for decommissioning projects complex wide. This project sets forth plans, organizational responsibilities, control systems, and procedures to manage the execution of the Project Management Plan for the 105-C Reactor Interim Safe Storage Project (Project Management Plan) activities to meet programmatic requirements within authorized funding and approved schedules. The Project Management Plan is organized following the guidelines provided by US Department of Energy Order 4700.1, Project Management System and the Richland Environmental Restoration Project Plan (DOE-RL 1992b)

New York State interim waste management cost evaluation

International Nuclear Information System (INIS)

Ma, M.S.; Watts, R.J.; Jorgensen, J.R.; Rochester Gas and Electric Corp., NY)

1985-01-01

The purpose of this study is to investigate and quantify the comparative costs associated with including or excluding Class A utility wastes at a centralized interim waste management facility in New York State. The objective of the study is to assess the unit costs and total statewide costs associated with two distinct scenarios: (1) the case where non-utility Class A LLRW is received, incinerated and stored at the centralized interim facility, and utility Class A wastes are held without incineration at respective nuclear power plant interim onsite facilities without incineration; and (2) the alternative case where both utility and non-utility Class A wastes are accepted, incinerated and stored at the centralized facility. Unit costs to waste generators are estimated for each of the two cases described. This is followed by an estimation of the statewide cost impact to the public. The cost impact represents the cost differential resulting from the exclusion of utility Class A waste from the centralized NYS interim waste management facility. The principal factors comprising the cost differential include (1) higher unit disposal fees charged to non-utility waste generators, which are passed along in the costs of products and services; and (2) costs to utilities due to construction of additional onsite storage capacity, which in turn are charged to electric rate payers

Developing new transportable storage casks for interim dry storage

International Nuclear Information System (INIS)

Hayashi, K.; Iwasa, K.; Araki, K.; Asano, R.

2004-01-01

Transportable storage metal casks are to be consistently used during transport and storage for AFR interim dry storage facilities planning in Japan. The casks are required to comply with the technical standards of regulations for both transport (hereinafter called ''transport regulation'') and storage (hereafter called ''storage regulation'') to maintain safety functions (heat transfer, containment, shielding and sub-critical control). In addition to these requirements, it is not planned in normal state to change the seal materials during storage at the storage facility, therefore it is requested to use same seal materials when the casks are transported after storage period. The dry transportable storage metal casks that satisfy the requirements have been developed to meet the needs of the dry storage facilities. The basic policy of this development is to utilize proven technology achieved from our design and fabrication experience, to carry out necessary verification for new designs and to realize a safe and rational design with higher capacity and efficient fabrication

216-T-4 interim stabilization final report

International Nuclear Information System (INIS)

Smith, D.L.

1996-01-01

This report provides a general description of the activities performed for the interim stabilization of the 216-T-4-1 ditch, 216-T-4-2 ditch, and 216-T-4-2 pond. Interim stabilization was required to reduce the amount of surface-contaminated acres and to minimize the migration of radioactive contamination. Work associated with the 216-T4-1 ditch and 216-T-4-2 pond was performed by the Radiation Area Remedial Action (RARA) Project. Work associated with the 216-T-4-2 ditch was done concurrently but was funded by Westinghouse Hanford Company (WHC) Tank Waste Remediation Systems (TWRS)

Lessons for outsourcing and interim management relationships.

Science.gov (United States)

Macko, W; Kostyack, P T

1999-01-01

Few decisions can affect an organization more than the selection of an outsourcing or interim management partner. More and more health care organizations face such decisions in today's competitive market in order to face new business needs. Making these relationships successful can be important for health care organizations seeking competitive advantages or seeking immediately accessible management support. These relationships, however, require careful partner selection and development. Success in outsourcing and interim management relationships is contingent upon a thorough selection process, a strong contract that has clearly and explicitly detailed responsibilities and a culture-sensitive business rapport between the client and selected partner.

PROJECT W-551 INTERIM PRETREATMENT SYSTEM PRECONCEPTUAL CANDIDATE TECHNOLOGY DESCRIPTIONS

Energy Technology Data Exchange (ETDEWEB)

MAY TH

2008-08-12

The Office of River Protection (ORP) has authorized a study to recommend and select options for interim pretreatment of tank waste and support Waste Treatment Plant (WTP) low activity waste (LAW) operations prior to startup of all the WTP facilities. The Interim Pretreatment System (IPS) is to be a moderately sized system which separates entrained solids and 137Cs from tank waste for an interim time period while WTP high level waste vitrification and pretreatment facilities are completed. This study's objective is to prepare pre-conceptual technology descriptions that expand the technical detail for selected solid and cesium separation technologies. This revision includes information on additional feed tanks.

75 FR 47312 - Board Meeting; Sunshine Act Meetings

Science.gov (United States)

2010-08-05

... INTER-AMERICAN FOUNDATION Board Meeting; Sunshine Act Meetings Time and Date: August 9, 2010, 8:30 a.m.-5:30 p.m.. Place: 101 Constitution Avenue, Washington, DC 20001. Status: Closed session as provided in 22 CFR 1004.4(f). Matters to be Considered: Executive Session. Portions to be Closed to the...

Report for the coal type committee meetings in fiscal 1988; 1987 nendo tanshu iinkai hokokusho

Energy Technology Data Exchange (ETDEWEB)

NONE

1988-03-01

The first committee meeting was held on September 30, 1987. The major agenda included: a development plan for the basic research, and as the summary of the achievements in fiscal 1986, Chinese coal liquefaction tests, coal type surveys, coal resource surveys, and as the research plan for fiscal 1987, coal resource surveys (Alaskan coal and Kalimantan coal), coal type surveys, and Chinese coal liquefaction tests. The results thereon were reported and deliberated. The second committee meeting was held on February 25, 1988. The agenda included: an interim report on the Chinese coal liquefaction tests, coal type surveys, coal resource surveys, (Alaskan coal and Kalimantan coal), as the interim report on the research achievements in fiscal 1987. Among the agenda, especially on the Chinese coal liquefaction tests, the data of the tests performed by the Chinese side and presented at the Japan-China joint technology sub-committee were introduced in detail, having drawn attention of the attendants. The first committee meeting reported the result of the autoclave test carried out by the Chinese side, the result of operation of the small continuous device (0.1 t/d) in fiscal 1986, and the result of the autoclave test performed by Mitsui Engineering and Shipbuilding for comparison. The second committee meeting reported the result of continuous operation implemented in China from August through September 1987 in the Chinese coal liquefaction test. (NEDO)

Interim Report by Asia International Grid Connection Study Group

Science.gov (United States)

Omatsu, Ryo

2018-01-01

The Asia International Grid Connection Study Group Interim Report examines the feasibility of developing an international grid connection in Japan. The Group has investigated different cases of grid connections in Europe and conducted research on electricity markets in Northeast Asia, and identifies the barriers and challenges for developing an international grid network including Japan. This presentation introduces basic contents of the interim report by the Study Group.

The incorporation of boron in fissile transport packages for the transport and interim storage of irradiated light water reactor fuels

International Nuclear Information System (INIS)

Hunter, I.J.

1998-01-01

Boron is widely used in the nuclear industry for capturing neutrons and it is particularly useful in the criticality control of packages for the transport and interim storage of irradiated light water reactor fuels. Such fuels are typically located in an internal frame of stainless steel or aluminium, referred to as a basket, which locates the fuel assemblies in channels. Transnucleaire has designed and supplied more than 100 baskets of varying types during the past 30 years. Boron has been incorporated in many forms. Early designs of baskets used boron in specific zones to contribute to the control of criticality. Later developments in new materials dispersed boron throughout the basket and gave designers more options for the basic forms which make up the channels. New basket concepts have been developed by Transnucleaire to meet the changing market needs for transport and interim storage and boron continues to play an important role as an efficient thermal neutron absorber. (author)

Interim report on the accident at Fukushima Nuclear Power Stations of Tokyo Electric Power Company

International Nuclear Information System (INIS)

2011-12-01

The Investigation Committee on the Accident at the Fukushima Nuclear Power Stations (the Investigation Committee) of Tokyo Electric Power Company (TEPCO) was established by the Cabinet decision on May 24, 2011. Its objectives are: to conduct investigation for finding out the causes of accidents at the Fukushima Dai-ichi Nuclear Power Station (Fukushima Dai-ichi NPS) and Fukushima Dai-ni Nuclear Power Station (Fukushima Dai-ni NPS) of TEPCO as well as the causes of accident damage; and to make policy recommendations for limiting the expansion of damage and preventing reoccurrence of similar accidents. The Investigation Committee has conducted its investigation and evaluation since its first meeting on June 7, 2011. Its activities included: site visits to the Fukushima Dai-ichi and Dai-ni NPSs, as well as to other facilities; hearing of heads of local governments around the Fukushima Dai-ichi NPS; and hearing of people concerned through interviews mainly arranged by the Secretariat. As of December 16, 2011, the number of interviewees reached 456. The investigation and evaluation by the Investigation Committee are still ongoing and the Interim Report does not cover every item that the Committee aims at investigating and evaluating. Fact-finding of even some of those items discussed in the Interim Report are not yet completed. The Investigation Committee continues to conduct its investigation and evaluation and will issue its Final Report in the summer of 2012. This brief executive summary covers mainly considerations and evaluation of the issues in Chapter VII of the Interim Report, with brief reference to Chapters I to VI. The Investigation Committee recommendations are printed in bold. (author)

75 FR 56608 - Agency Meeting

Science.gov (United States)

2010-09-16

... SECURITIES AND EXCHANGE COMMISSION Agency Meeting Federal Register Citation of Previous Announcement: [To be published] Status: Open Meeting. Place: 100 F. Street, NE., Washington, DC. Date and Time of Previously Announced Meeting: September 15, 2010. Change In the Meeting: Room Change. The Joint...

The Interim Financial Reporting in the Spirit of the IAS 34 Norm

OpenAIRE

Ovidia Doinea

2008-01-01

The role of an interim financial reporting is to allow the information users to acknowledge the activity of an entity on period shorter than financial exercise from the perspective of the available profits and cash flows generated as well as from the point of view of its financial position and liquidity. The interim financial reporting includes a complete or condensed set of financial statements which target to update the last financial reporting, usually the annual report. The interim financ...

A web-based endpoint adjudication system for interim analyses in clinical trials.

Science.gov (United States)

Nolen, Tracy L; Dimmick, Bill F; Ostrosky-Zeichner, Luis; Kendrick, Amy S; Sable, Carole; Ngai, Angela; Wallace, Dennis

2009-02-01

A data monitoring committee (DMC) is often employed to assess trial progress and review safety data and efficacy endpoints throughout a trail. Interim analyses performed for the DMC should use data that are as complete and verified as possible. Such analyses are complicated when data verification involves subjective study endpoints or requires clinical expertise to determine each subject's status with respect to the study endpoint. Therefore, procedures are needed to obtain adjudicated data for interim analyses in an efficient manner. In the past, methods for handling such data included using locally reported results as surrogate endpoints, adjusting analysis methods for unadjudicated data, or simply performing the adjudication as rapidly as possible. These methods all have inadequacies that make their sole usage suboptimal. For a study of prophylaxis for invasive candidiasis, adjudication of both study eligibility criteria and clinical endpoints prior to two interim analyses was required. Because the study was expected to enroll at a moderate rate and the sponsor required adjudicated endpoints to be used for interim analyses, an efficient process for adjudication was required. We created a web-based endpoint adjudication system (WebEAS) that allows for expedited review by the endpoint adjudication committee (EAC). This system automatically identifies when a subject's data are complete, creates a subject profile from the study data, and assigns EAC reviewers. The reviewers use the WebEAS to review the subject profile and submit their completed review form. The WebEAS then compares the reviews, assigns an additional review as a tiebreaker if needed, and stores the adjudicated data. The study for which this system was originally built was administratively closed after 10 months with only 38 subjects enrolled. The adjudication process was finalized and the WebEAS system activated prior to study closure. Some website accessibility issues presented initially. However

Transuranic waste storage and assay facility (TRUSAF) interim safety basis

International Nuclear Information System (INIS)

Gibson, K.D.

1995-09-01

The TRUSAF ISB is based upon current facility configuration and procedures. The purpose of the document is to provide the basis for interim operation or restrictions on interim operations and the authorization basis for the TRUSAF at the Hanford Site. The previous safety analysis document TRUSAF hazards Identification and Evaluation (WHC 1977) is superseded by this document

Cost of implementing AECB interim criteria for the closeout of uranium tailings sites

International Nuclear Information System (INIS)

1981-04-01

The main purpose of this study was to arrive at a gross approximation of the costs to the Canadian uranium mining industry of meeting the proposed closeout criteria established by the Atomic Energy Control Board for tailings deposits. Two options have been investigated: on-land disposal and underlake disposal. Given the budget allocated to the study, the estimates must be understood as approximations. Overall cost figures for the Canadian uranium mining industry are linear extensions from a hypothetical base case. The results of a conference held in Ottawa on February 25 and 26 to discuss the proposed AECB interim criteria for the closeout of uranium tailings sites are also included. Representatives from mining firms, provincial regulatory authorities, universities and the Atomic Energy Control board attended the conference

ITER management advisory committee meeting in NAKA

International Nuclear Information System (INIS)

Yoshikawa, M.

1999-01-01

The ITER Management Advisory Committee (MAC) Meeting was held on 17 December 1999 in Naka, Japan. The main topics were the ITER EDA Status, Task Status Summary and Work Program and a schedule of ITER meetings

K basins interim remedial action health and safety plan

Energy Technology Data Exchange (ETDEWEB)

DAY, P.T.

1999-09-14

The K Basins Interim Remedial Action Health and Safety Plan addresses the requirements of the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA), as they apply to the CERCLA work that will take place at the K East and K West Basins. The provisions of this plan become effective on the date the US Environmental Protection Agency issues the Record of Decision for the K Basins Interim Remedial Action, currently planned in late August 1999.

Interim safety basis for fuel supply shutdown facility

International Nuclear Information System (INIS)

Brehm, J.R.; Deobald, T.L.; Benecke, M.W.; Remaize, J.A.

1995-01-01

This ISB in conjunction with the new TSRs, will provide the required basis for interim operation or restrictions on interim operations and administrative controls for the Facility until a SAR is prepared in accordance with the new requirements. It is concluded that the risk associated with the current operational mode of the Facility, uranium closure, clean up, and transition activities required for permanent closure, are within Risk Acceptance Guidelines. The Facility is classified as a Moderate Hazard Facility because of the potential for an unmitigated fire associated with the uranium storage buildings

FY17 Status Report: Research on Stress Corrosion Cracking of SNF Interim Storage Canisters.

Energy Technology Data Exchange (ETDEWEB)

Schindelholz, Eric John [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Bryan, Charles R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Alexander, Christopher L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2017-09-01

This progress report describes work done in FY17 at Sandia National Laboratories (SNL) to assess the localized corrosion performance of container/cask materials used in the interim storage of spent nuclear fuel (SNF). Of particular concern is stress corrosion cracking (SCC), by which a through-wall crack could potentially form in a canister outer wall over time intervals that are shorter than possible dry storage times. Work in FY17 refined our understanding of the chemical and physical environment on canister surfaces, and evaluated the relationship between chemical and physical environment and the form and extent of corrosion that occurs. The SNL corrosion work focused predominantly on pitting corrosion, a necessary precursor for SCC, and process of pit-to-crack transition; it has been carried out in collaboration with university partners. SNL is collaborating with several university partners to investigate SCC crack growth experimentally, providing guidance for design and interpretation of experiments.

Power Transfer Potential to the Southeast in Response to a Renewable Portfolio Standard: Interim Report 1

Energy Technology Data Exchange (ETDEWEB)

Hadley, Stanton W [ORNL; Key, Thomas S [Electric Power Research Institute (EPRI)

2009-03-01

The power transfer potential for bringing renewable energy into the Southeast in response to a renewable portfolio standard (RPS) will depend not only on available transmission capacity but also on electricity supply and demand factors. This interim report examines how the commonly used EIA NEMS and EPRI NESSIE energy equilibrium models are considering such power transfers. Using regional estimates of capacity expansion and demand, a base case for 2008, 2020 and 2030 are compared relative to generation mix, renewable deployments, planned power transfers, and meeting RPS goals. The needed amounts of regional renewable energy to comply with possible RPS levels are compared to inter-regional transmission capacities to establish a baseline available for import into the Southeast and other regions. Gaps in the renewable generation available to meet RPS requirements are calculated. The initial finding is that the physical capability for transferring renewable energy into the SE is only about 10% of what would be required to meet a 20% RPS. Issues that need to be addressed in future tasks with respect to modeling are the current limitations for expanding renewable capacity and generation in one region to meet the demand in another and the details on transmission corridors required to deliver the power.

Immobilized high-level waste interim storage alternatives generation and analysis and decision report

International Nuclear Information System (INIS)

CALMUS, R.B.

1999-01-01

This report presents a study of alternative system architectures to provide onsite interim storage for the immobilized high-level waste produced by the Tank Waste Remediation System (TWRS) privatization vendor. It examines the contract and program changes that have occurred and evaluates their impacts on the baseline immobilized high-level waste (IHLW) interim storage strategy. In addition, this report documents the recommended initial interim storage architecture and implementation path forward

78 FR 73190 - Sunshine Act Meeting

Science.gov (United States)

2013-12-05

... FEDERAL RESERVE SYSTEM Sunshine Act Meeting Agency Holding the Meeting: Board of Governors of the...., Washington, DC 20551. STATUS: Open. On the day of the meeting, you will be able to view the meeting via... webcast of the meeting. A link to the meeting documentation will also be available approximately 20...

In vitro evaluation of the marginal integrity of CAD/CAM interim crowns.

Science.gov (United States)

Kelvin Khng, Kwang Yong; Ettinger, Ronald L; Armstrong, Steven R; Lindquist, Terry; Gratton, David G; Qian, Fang

2016-05-01

The accuracy of interim crowns made with computer-aided design and computer-aided manufacturing (CAD/CAM) systems has not been well investigated. The purpose of this in vitro study was to evaluate the marginal integrity of interim crowns made by CAD/CAM compared with that of conventional polymethylmethacrylate (PMMA) crowns. A dentoform mandibular left second premolar was prepared for a ceramic crown and scanned for the fabrication of 60 stereolithical resin dies, half of which were scanned to fabricate 15 Telio CAD-CEREC and 15 Paradigm MZ100-E4D-E4D crowns. Fifteen Caulk and 15 Jet interim crowns were made on the remaining resin dies. All crowns were cemented with Tempgrip under a 17.8-N load, thermocycled for 1000 cycles, placed in 0.5% acid fuschin for 24 hours, and embedded in epoxy resin before sectioning from the mid-buccal to mid-lingual surface. The marginal discrepancy was measured using a traveling microscope, and dye penetration was measured as a percentage of the overall length under the crown. The mean vertical marginal discrepancy of the conventionally made interim crowns was greater than for the CAD/CAM crowns (P=.006), while no difference was found for the horizontal component (P=.276). The mean vertical marginal discrepancy at the facial surface of the Caulk crowns was significantly greater than that of the other 3 types of interim crowns (Pmargin, the mean horizontal component of the Telio crowns was significantly larger than that of the other 3 types, with no difference at the lingual margins (P=.150). The mean percentage dye penetration for the Paradigm MZ100-E4D crowns was significantly greater and for Jet crowns significantly smaller than for the other 3 crowns (Pmarginal discrepancies of the Jet interim crowns at the facial surface and with the horizontal marginal discrepancies of the Caulk interim crowns at the lingual surface (Pmarginal discrepancy was found with the interim crowns fabricated by CAD/CAM as compared with PMMA crowns

42 CFR 93.401 - Interaction with other offices and interim actions.

Science.gov (United States)

2010-10-01

... 42 Public Health 1 2010-10-01 2010-10-01 false Interaction with other offices and interim actions. 93.401 Section 93.401 Public Health PUBLIC HEALTH SERVICE, DEPARTMENT OF HEALTH AND HUMAN SERVICES... Human Services General Information § 93.401 Interaction with other offices and interim actions. (a) ORI...

42 CFR 417.572 - Budget and enrollment forecast and interim reports.

Science.gov (United States)

2010-10-01

... 42 Public Health 3 2010-10-01 2010-10-01 false Budget and enrollment forecast and interim reports... PLANS, AND HEALTH CARE PREPAYMENT PLANS Medicare Payment: Cost Basis § 417.572 Budget and enrollment forecast and interim reports. (a) Annual submittal. The HMO or CMP must submit an annual operating budget...

Early interim 18F-FDG PET in Hodgkin's lymphoma: evaluation on 304 patients

International Nuclear Information System (INIS)

Zinzani, Pier Luigi; Stefoni, Vittorio; Broccoli, Alessandro; Argnani, Lisa; Baccarani, Michele; Rigacci, Luigi; Puccini, Benedetta; Castagnoli, Antonio; Vaggelli, Luca; Zanoni, Lucia; Fanti, Stefano

2012-01-01

The use of early (interim) PET restaging during first-line therapy of Hodgkin's lymphoma (HL) in clinical practice has considerably increased because of its ability to provide early recognition of treatment failure allowing patients to be transferred to more intensive treatment regimens. Between June 1997 and June 2009, 304 patients with newly diagnosed HL (147 early stage and 157 advanced stage) were treated with the ABVD regimen at two Italian institutions. Patients underwent PET staging and restaging at baseline, after two cycles of therapy and at the end of the treatment. Of the 304 patients, 53 showed a positive interim PET scan and of these only 13 (24.5%) achieved continuous complete remission (CCR), whereas 251 patients showed a negative PET scan and of these 231 (92%) achieved CCR. Comparison between interim PET-positive and interim PET-negative patients indicated a significant association between PET findings and 9-year progression-free survival and 9-year overall survival, with a median follow-up of 31 months. Among the early-stage patients, 19 had a positive interim PET scan and only 4 (21%) achieved CCR; among the 128 patients with a negative interim PET scan, 122 (97.6%) achieved CCR. Among the advanced-stage patients, 34 showed a persistently positive PET scan with only 9 (26.4%) achieving CCR, whereas 123 showed a negative interim PET scan with 109 (88.6%) achieving CCR. Our results demonstrate the role of an early PET scan as a significant step forward in the management of patients with early-stage or advanced-stage HL. (orig.)

10 CFR 431.401 - Petitions for waiver, and applications for interim waiver, of test procedure.

Science.gov (United States)

2010-01-01

... Renewable Energy, U.S. Department of Energy. Each Application for Interim Waiver must reference the Petition... Renewable Energy. (e) Provisions specific to interim waivers—(1) Disposition of application. If... 10 Energy 3 2010-01-01 2010-01-01 false Petitions for waiver, and applications for interim waiver...

Integrated system of safety features for spent fuel interim storage

International Nuclear Information System (INIS)

Pantazi, Doina; Stanciu, Marcela; Mateescu, Silvia; Marin, Ion

1999-01-01

The design of the spent fuel interim storage facility (SFISF) must meet the applicable safety requirements in order to ensure radiological protection of the personnel, public and environment during all phases of the facility. To elaborate the safety documentation necessary for licensing, we were trying to chose the most appropriate approach related to safety features for SFISF, based on national and international regulations, standards and recommendations, as well as on the experience of other countries with similar facilities and finally, on our own experience in designing other nuclear objectives in Romania. The paper presents the issues that we consider important for the safety evaluation and are developed as a detailed diagram. The diagram contains in a logical succession the following issues: - fundamental principles of radioprotection; - fundamental safety principles of radioactive waste management; - safety objectives of SFISF; - safety criteria for SFISF; - safety requirements for SFISF; - siting criteria for SFISF; - siting requirements for SFISF. (authors)

Fit of interim crowns fabricated using photopolymer-jetting 3D printing.

Science.gov (United States)

Mai, Hang-Nga; Lee, Kyu-Bok; Lee, Du-Hyeong

2017-08-01

The fit of interim crowns fabricated using 3-dimensional (3D) printing is unknown. The purpose of this in vitro study was to evaluate the fit of interim crowns fabricated using photopolymer-jetting 3D printing and to compare it with that of milling and compression molding methods. Twelve study models were fabricated by making an impression of a metal master model of the mandibular first molar. On each study model, interim crowns (N=36) were fabricated using compression molding (molding group, n=12), milling (milling group, n=12), and 3D polymer-jetting methods. The crowns were prepared as follows: molding group, overimpression technique; milling group, a 5-axis dental milling machine; and polymer-jetting group using a 3D printer. The fit of interim crowns was evaluated in the proximal, marginal, internal axial, and internal occlusal regions by using the image-superimposition and silicone-replica techniques. The Mann-Whitney U test and Kruskal-Wallis tests were used to compare the results among groups (α=.05). Compared with the molding group, the milling and polymer-jetting groups showed more accurate results in the proximal and marginal regions (P3D printing significantly enhanced the fit of interim crowns, particularly in the occlusal region. Copyright © 2016 Editorial Council for the Journal of Prosthetic Dentistry. Published by Elsevier Inc. All rights reserved.

A Non-Traditional Interim Project.

Science.gov (United States)

Brown, Diane; Ward, Dorothy

1980-01-01

Describes a project initiated by the Foreign Language Department of Birmingham-Southern College for their Interim term and discusses an interdisciplinary course focusing on Medieval Europe. The course included presentations on German and French language and literature, as well as lectures on the arts, philosophy, and family life of the period.…

Proceedings of the 11. 2010 energy meetings

International Nuclear Information System (INIS)

2010-01-01

The energy meetings is the biggest annual event for French local communities in the energy domain. The public is mainly composed of officials, representatives from local communities, institutions, private organisations and associations. The aim of the meetings is to debate and exchange on the actions to be implemented at the regional scale by Territorial authorities in order to meet the 2020 European energy goals. Territorial authorities are on the front line to guide the development of their area, generate employment, improving life quality together with consuming less and more efficiently energy. About 500 European municipalities have signed the Mayor's convention yet and are ready to take up the challenge. Even if the interim target is 2020, the trajectory change is for today with its translations in terms of strategic orientation, human and financial means, governance and citizens involvement. This 2010 edition presents the changes already implemented with their stakes and experiences feedback. It is organised around 6 workshops and 47 forums. These proceedings brings together the available material: a detailed programme and 44 forum fact sheets

Developing new transportable storage casks for interim dry storage

Energy Technology Data Exchange (ETDEWEB)

Hayashi, K.; Iwasa, K.; Araki, K.; Asano, R. [Hitachi Zosen Diesel and Engineering Co., Ltd., Tokyo (Japan)

2004-07-01

Transportable storage metal casks are to be consistently used during transport and storage for AFR interim dry storage facilities planning in Japan. The casks are required to comply with the technical standards of regulations for both transport (hereinafter called ''transport regulation'') and storage (hereafter called ''storage regulation'') to maintain safety functions (heat transfer, containment, shielding and sub-critical control). In addition to these requirements, it is not planned in normal state to change the seal materials during storage at the storage facility, therefore it is requested to use same seal materials when the casks are transported after storage period. The dry transportable storage metal casks that satisfy the requirements have been developed to meet the needs of the dry storage facilities. The basic policy of this development is to utilize proven technology achieved from our design and fabrication experience, to carry out necessary verification for new designs and to realize a safe and rational design with higher capacity and efficient fabrication.

Maternity leave duration and full-time/part-time work status are associated with US mothers’ ability to meet breastfeeding intentions

Science.gov (United States)

Mirkovic, Kelsey R.; Perrine, Cria G.; Scanlon, Kelley S.; Grummer-Strawn, Laurence M.

2015-01-01

Background Breastfeeding provides numerous health benefits for infants and mothers; however, many infants are not breastfed as long as recommended or desired by mothers. Maternal employment is frequently cited as a barrier to breastfeeding. Objectives To assess whether maternity leave duration and return-status (full-time [FT], part-time [PT]) were associated with not meeting a mother’s intention to breastfeed at least 3 months. Methods We used data from the Infant Feeding Practices Study II, a cohort study. Analyses were limited to women employed prenatally who intended to breastfeed 3 months or longer (n=1172). Multivariable logistic regression was used to assess the relationship between maternity leave duration and return to work-status (<6 weeks/FT, <6 weeks/PT, 6 weeks – 3 months/FT, 6 weeks – 3 months/PT, not working by 3 months) and meeting a mother’s intention to breastfeed at least 3 months. Results Overall, 28.8% of mothers did not meet their intention to breastfeed at least 3 months. Odds of not meeting intention to breastfeed at least 3 months were higher among mothers who returned to work FT before 3 months (<6 weeks/FT: aOR = 2.25, 95% CI: 1.23 – 4.12; 6 weeks – 3 months/FT: aOR = 1.82, 95% CI: 1.30 – 2.56), compared with mothers not working at 3 months. Conclusions Returning to work full-time before 3 months may reduce a mother’s ability to meet her intention to breastfeed at least 3 months. Employer support for flexible work scheduling may help more women achieve their breastfeeding goals. PMID:25034868

Maternity leave duration and full-time/part-time work status are associated with US mothers' ability to meet breastfeeding intentions.

Science.gov (United States)

Mirkovic, Kelsey R; Perrine, Cria G; Scanlon, Kelley S; Grummer-Strawn, Laurence M

2014-11-01

Breastfeeding provides numerous health benefits for infants and mothers; however, many infants are not breastfed as long as recommended or desired by mothers. Maternal employment is frequently cited as a barrier to breastfeeding. This study aimed to assess whether maternity leave duration and return status (full-time [FT], part-time [PT]) were associated with not meeting a mother's intention to breastfeed at least 3 months. We used data from the Infant Feeding Practices Study II, a cohort study. Analyses were limited to women employed prenatally who intended to breastfeed 3 months or longer (n = 1172). Multivariable logistic regression was used to assess the relationship between maternity leave duration and return-to-work status (< 6 weeks/FT, < 6 weeks/PT, 6 weeks-3 months/FT, 6 weeks-3 months/PT, not working by 3 months) and meeting a mother's intention to breastfeed at least 3 months. Overall, 28.8% of mothers did not meet their intention to breastfeed at least 3 months. Odds of not meeting intention to breastfeed at least 3 months were higher among mothers who returned to work FT before 3 months (< 6 weeks/FT: adjusted odds ratio = 2.25, 95% confidence interval, 1.23-4.12; 6 weeks-3 months/FT: adjusted odds ratio = 1.82, 95% confidence interval, 1.30-2.56), compared with mothers not working at 3 months. Returning to work full-time before 3 months may reduce a mother's ability to meet her intention to breastfeed at least 3 months. Employer support for flexible work scheduling may help more women achieve their breastfeeding goals. © International Lactation Consultant Association 2014.

Interim and final storage casks

International Nuclear Information System (INIS)

Stumpfrock, L.; Kockelmann, H.

2012-01-01

The disposal of radioactive waste is a huge social challenge in Germany and all over the world. As is well known the search for a site for a final repository for high-level waste in Germany is not complete. Therefore, interim storage facilities for radioactive waste were built at plant sites in Germany. The waste is stored in these storage facilities in appropriate storage and transport casks until the transport in a final repository can be carried out. Licensing of the storage and transport casks aimed for use in the public space is done according to the traffic laws and for handling in the storage facility according to nuclear law. Taking into account the activity of the waste to be stored, different containers are in use, so that experience is available from the licensing and operation in interim storage facilities. The large volume of radioactive waste to be disposed of after the shut-down of power generation in nuclear power stations makes it necessary for large quantities of licensed storage and transport casks to be provided soon.

Interim storage report

International Nuclear Information System (INIS)

Rawlins, J.K.

1998-02-01

High-level radioactive waste (HLW) stored at the Idaho Chemical Processing Plant (ICPP) in the form of calcine and liquid and liquid sodium-bearing waste (SBW) will be processed to provide a stable waste form and prepare the waste to be transported to a permanent repository. Because a permanent repository will not be available when the waste is processed, the waste must be stored at ICPP in an Interim Storage Facility (ISF). This report documents consideration of an ISF for each of the waste processing options under consideration

ITER interim design report package documents

International Nuclear Information System (INIS)

1996-01-01

This publication contains the Excerpt from the ITER Council (IC-8), the ITER Interim Design Report, Cost Review and Safety Analysis, ITER Site Requirements and ITER Site Design Assumptions and the Excerpt from the ITER Council (IC-9). 8 figs, 2 tabs

Spent fuel interim storage

International Nuclear Information System (INIS)

Bilegan, Iosif C.

2003-01-01

The official inauguration of the spent fuel interim storage took place on Monday July 28, 2003 at Cernavoda NNP. The inaugural event was attended by local and central public authority representatives, a Canadian Government delegation as well as newsmen from local and central mass media and numerous specialists from Cernavoda NPP compound. Mr Andrei Grigorescu, State Secretary with the Economy and Commerce Ministry, underlined in his talk the importance of this objective for the continuous development of nuclear power in Romania as well as for Romania's complying with the EU practice in this field. Also the excellent collaboration between the Canadian contractor AECL and the Romanian partners Nuclear Montaj, CITON, UTI, General Concret in the accomplishment of this unit at the planned terms and costs. On behalf of Canadian delegation, spoke Minister Don Boudria. He underlined the importance which the Canadian Government affords to the cooperation with Romania aiming at specific objectives in the field of nuclear power such as the Cernavoda NPP Unit 2 and spent fuel interim storage. After traditional cutting of the inaugural ribbon by the two Ministers the festivities continued on the Cernavoda NPP Compound with undersigning the documents regarding the project completion and a press conference

U.S. Renewables Portfolio Standards: 2017 Annual Status Report

Energy Technology Data Exchange (ETDEWEB)

Barbose, Galen [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

2017-07-25

Berkeley Lab’s annual status report on U.S. renewables portfolio standards (RPS) provides an overview of key trends associated with U.S. state RPS policies. The report, published in slide-deck form, describes recent legislative revisions, key policy design features, compliance with interim targets, past and projected impacts on renewables development, and compliance costs. The 2017 edition of the report presents historical data through year-end 2016 and projections through 2030. Key trends from this edition of the report include the following: -Evolution of state RPS programs: Significant RPS-related policy revisions since the start of 2016 include increased RPS targets in DC, MD, MI, NY, RI, and OR; requirements for new wind and solar projects and other major reforms to the RPS procurement process in IL; and a new offshore wind carve-out and solar procurement program in MA. -Historical impacts on renewables development: Roughly half of all growth in U.S. renewable electricity (RE) generation and capacity since 2000 is associated with state RPS requirements. Nationally, the role of RPS policies has diminished over time, representing 44% of all U.S. RE capacity additions in 2016. However, within particular regions, RPS policies continue to play a central role in supporting RE growth, constituting 70-90% of 2016 RE capacity additions in the West, Mid-Atlantic, and Northeast. -Future RPS demand and incremental needs: Meeting RPS demand growth will require roughly a 50% increase in U.S. RE generation by 2030, equating to 55 GW of new RE capacity. To meet future RPS demand, total U.S. RE generation will need to reach 13% of electricity sales by 2030 (compared to 10% today), though other drivers will also continue to influence RE growth. -RPS target achievement to-date: States have generally met their interim RPS targets in recent years, with only a few exceptions reflecting unique state-specific policy designs. -REC pricing trends: Prices for renewable energy

Proceedings of the 1983 civilian radioactive waste management information meeting

International Nuclear Information System (INIS)

1984-02-01

This proceedings document from the 1983 Civilian Radioactive Waste Management Information Meeting serves to highlight developments since the passage of the Nuclear Policy Act of 1982 and reviews program activities necessary to provide for the permanent disposal and storage of commercially generated high-level radioactive waste. Presentations included in this program cover topics concerning interim spent fuel, monitored retrievable storage, geologic repository deployment as well as management of the Nuclear Waste Fund. Individual papers were abstracted for inclusion in the Energy Data Base

Effectiveness of interim stage filter in the exhaust system of glove boxes

International Nuclear Information System (INIS)

Patre, D.K.; Vangara, H.; Thanamani, S.; Gopalakrishnan, R.K.; Mhatre, Amol M.

2018-01-01

All operations in radiochemical laboratories are carried out in containment systems like Glove boxes and Fume hoods. For controlling air contamination two separate air cleaning systems are incorporated. Laboratory has general ventilation system and glove boxes are provided with a negative pressure system (NPS). Glove box exhaust air is passed through three stage filtration systems: in situ, interim and final before discharging to the atmosphere. In addition to the individual HEPA filters of each glove box, there is an interim HEPA filter bank introduced at the laboratory end. This was introduced to reduce a load on main exhaust filter system. Finally the exhaust air is discharged through the final stage HEPA filter located in the filter house through the Stack. The interim HEPA filter bank provides additional protection for the release of particulate activity and reduces load on the final stage filters. In the present work efforts have been put to validate the interim stage filter, which has been introduced, to limit the environmental release

78 FR 8203 - Sunshine Act Meetings

Science.gov (United States)

2013-02-05

...: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. Week of... Meeting) (Contact: Ken Karwoski, 301-415-2752) This meeting will be webcast live at the web address--www... Uranium Recovery (Public Meeting) (Contact: Bill von Till, 301-415-0598) This meeting will be webcast live...

LANDFILL BIOREACTOR PERFORMANCE, SECOND INTERIM REPORT

Science.gov (United States)

A bioreactor landfill is a landfill that is operated in a manner that is expected to increase the rate and extent of waste decomposition, gas generation, and settlement compared to a traditional landfill. This Second Interim Report was prepared to provide an interpretation of fie...

DOE UST interim subsurface barrier technologies workshop

International Nuclear Information System (INIS)

1992-09-01

This document contains information which was presented at a workshop regarding interim subsurface barrier technologies that could be used for underground storage tanks, particularly the tank 241-C-106 at the Hanford Reservation

A conservative method of retaining an interim obturator for a total maxillectomy patient

Directory of Open Access Journals (Sweden)

Nirmal Famila Bettie

2017-01-01

Full Text Available Interim obturators are indicated during the postsurgical phases. It promotes surgical healing and serves as a temporary prosthesis to rehabilitate a patient with intra-oral surgical defect. Retention is gained by wiring, surgical suturing, and other noninvasive methods to enable functional rehabilitation and easy replacement with a permanent obturator. Interim obturators serve as an easy guide for replacing with definitive obturators by indicating prosthesis extensions and the required method of retention. A more conservative and noninvasive method of retaining an interim obturator for a maxillectomy patient is described in this case report.

A Conservative Method of Retaining an Interim Obturator for a Total Maxillectomy Patient.

Science.gov (United States)

Bettie, Nirmal Famila

2017-11-01

Interim obturators are indicated during the postsurgical phases. It promotes surgical healing and serves as a temporary prosthesis to rehabilitate a patient with intra-oral surgical defect. Retention is gained by wiring, surgical suturing, and other noninvasive methods to enable functional rehabilitation and easy replacement with a permanent obturator. Interim obturators serve as an easy guide for replacing with definitive obturators by indicating prosthesis extensions and the required method of retention. A more conservative and noninvasive method of retaining an interim obturator for a maxillectomy patient is described in this case report.

International validation study for interim PET in ABVD-treated, advanced-stage hodgkin lymphoma

DEFF Research Database (Denmark)

Biggi, Alberto; Gallamini, Andrea; Chauvie, Stephane

2013-01-01

At present, there are no standard criteria that have been validated for interim PET reporting in lymphoma. In 2009, an international workshop attended by hematologists and nuclear medicine experts in Deauville, France, proposed to develop simple and reproducible rules for interim PET reporting...... in lymphoma. Accordingly, an international validation study was undertaken with the primary aim of validating the prognostic role of interim PET using the Deauville 5-point score to evaluate images and with the secondary aim of measuring concordance rates among reviewers using the same 5-point score...

78 FR 69086 - Sunshine Act Meeting

Science.gov (United States)

2013-11-18

... FEDERAL ELECTION COMMISSION Sunshine Act Meeting AGENCY: Federal Election Commission. Federal... 19, 2013 at 10:00 a.m. PLACE: 999 E Street NW., Washington, DC. STATUS: This meeting will be closed to the public. CHANGES IN THE MEETING: The meeting will begin at 11:00 a.m. ITEMS TO BE DISCUSSED...

78 FR 41125 - Interim Enforcement Policy for Permanent Implant Brachytherapy Medical Event Reporting

Science.gov (United States)

2013-07-09

... NUCLEAR REGULATORY COMMISSION [NRC-2013-0114] Interim Enforcement Policy for Permanent Implant Brachytherapy Medical Event Reporting AGENCY: Nuclear Regulatory Commission. ACTION: Policy statement; revision. SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing an interim Enforcement Policy that allows...

76 FR 64071 - Annual Meeting

Science.gov (United States)

2011-10-17

... APPALACHIAN STATES LOW-LEVEL RADIOACTIVE WASTE COMMISSION Annual Meeting Time and Date: 10 a.m.-12..., PA 17101. Status: The meeting will be open to the public. Matters to be Considered: Portions Open to the Public: The primary purpose of this meeting is to (1) Review the independent auditors' report of...

75 FR 65297 - Annual Meeting

Science.gov (United States)

2010-10-22

... APPALACHIAN STATES LOW-LEVEL RADIOACTIVE WASTE COMMISSION Annual Meeting Time And Date: 10 a.m.-12..., PA 17101. Status: The meeting will be open to the public. Matters To Be Considered Portions Open to the Public: The primary purpose of this meeting is to (1) Review the independent auditors' report of...

78 FR 64472 - Annual Meeting

Science.gov (United States)

2013-10-29

... APPALACHIAN STATES LOW-LEVEL RADIOACTIVE WASTE COMMISSION Annual Meeting Time and Date: 10 a.m.-12... 17101. Status: The meeting will be open to the public. Matters To Be Considered: Portions Open To The Public: The primary purpose of this meeting is to (1) Review the independent auditors' report of...

77 FR 61737 - Annual Meeting

Science.gov (United States)

2012-10-11

... APPALACHIAN STATES LOW-LEVEL RADIOACTIVE WASTE COMMISSION Annual Meeting Time and Date: 10 a.m.-12... 17101. Status: The meeting will be open to the public. Matters To Be Considered Portions Open to the Public: The primary purpose of this meeting is to (1) Review the independent auditors' report of...

Predictive probability methods for interim monitoring in clinical trials with longitudinal outcomes.

Science.gov (United States)

Zhou, Ming; Tang, Qi; Lang, Lixin; Xing, Jun; Tatsuoka, Kay

2018-04-17

In clinical research and development, interim monitoring is critical for better decision-making and minimizing the risk of exposing patients to possible ineffective therapies. For interim futility or efficacy monitoring, predictive probability methods are widely adopted in practice. Those methods have been well studied for univariate variables. However, for longitudinal studies, predictive probability methods using univariate information from only completers may not be most efficient, and data from on-going subjects can be utilized to improve efficiency. On the other hand, leveraging information from on-going subjects could allow an interim analysis to be potentially conducted once a sufficient number of subjects reach an earlier time point. For longitudinal outcomes, we derive closed-form formulas for predictive probabilities, including Bayesian predictive probability, predictive power, and conditional power and also give closed-form solutions for predictive probability of success in a future trial and the predictive probability of success of the best dose. When predictive probabilities are used for interim monitoring, we study their distributions and discuss their analytical cutoff values or stopping boundaries that have desired operating characteristics. We show that predictive probabilities utilizing all longitudinal information are more efficient for interim monitoring than that using information from completers only. To illustrate their practical application for longitudinal data, we analyze 2 real data examples from clinical trials. Copyright © 2018 John Wiley & Sons, Ltd.

Safety report for Central Interim Storage facility for radioactive waste from small producers

International Nuclear Information System (INIS)

Zeleznik, N.; Mele, I.

2004-01-01

In 1999 the Agency for Radwaste Management took over the management of the Central Interim Storage (CIS) in Brinje, intended only for radioactive waste from industrial, medical and research applications. With the transfer of the responsibilities for the storage operation, ARAO, the new operator of the facility, received also the request from the Slovenian Nuclear Safety Administration for refurbishment and reconstruction of the storage and for preparation of the safety report for the storage with the operational conditions and limitations. In order to fulfill these requirements ARAO first thoroughly reviewed the existing documentation on the facility, the facility itself and the stored inventory. Based on the findings of this review ARAO prepared several basic documents for improvement of the current conditions in the storage facility. In October 2000 the Plan for refurbishment and modernization of the CIS was prepared, providing an integral approach towards remediation and refurbishment of the facility, optimization of the inventory arrangement and modernization of the storage and storing utilization. In October 2001 project documentation for renewal of electric installations, water supply and sewage system, ventilation system, the improvements of the fire protection and remediation of minor defects discovered in building were completed according to the Act on Construction. In July 2003 the safety report was prepared, based on the facility status after the completion of the reconstruction works. It takes into account all improvements and changes introduced by the refurbishment and reconstruction of the facility according to project documentation. Besides the basic characteristics of the location and its surrounding, it also gives the technical description of the facility together with proposed solutions for the renewal of electric installations, renovation of water supply and sewage system, refurbishment of the ventilation system, the improvement of fire

Pathways to deep decarbonization - Interim 2014 Report

International Nuclear Information System (INIS)

2014-01-01

The interim 2014 report by the Deep Decarbonization Pathways Project (DDPP), coordinated and published by IDDRI and the Sustainable Development Solutions Network (SDSN), presents preliminary findings of the pathways developed by the DDPP Country Research Teams with the objective of achieving emission reductions consistent with limiting global warming to less than 2 deg. C. The DDPP is a knowledge network comprising 15 Country Research Teams and several Partner Organizations who develop and share methods, assumptions, and findings related to deep decarbonization. Each DDPP Country Research Team has developed an illustrative road-map for the transition to a low-carbon economy, with the intent of taking into account national socio-economic conditions, development aspirations, infrastructure stocks, resource endowments, and other relevant factors. The interim 2014 report focuses on technically feasible pathways to deep decarbonization

Interim guidelines for protecting fire-fighting personnel from multiple hazards at nuclear plant sites

International Nuclear Information System (INIS)

Klein, A.R.; Bloom, C.W.

1989-07-01

This report provides interim guidelines for reducing the impact to fire fighting and other supporting emergency response personnel from the multiple hazards of radiation, heat stress, and trauma when fighting a fire in a United States commercial nuclear power plant. Interim guidelines are provided for fire brigade composition, training, equipment, procedures, strategies, heat stress and trauma. In addition, task definitions are provided to evaluate and further enhance the interim guidelines over the long term. 19 refs

78 FR 69141 - Sunshine Act Meeting

Science.gov (United States)

2013-11-18

... POSTAL REGULATORY COMMISSION Sunshine Act Meeting TIME AND DATE: Wednesday, December 11, 2013, at.... STATUS: Part of this meeting will be open to the public. The rest of the meeting will be closed to the... December 11, 2013 meeting includes the items identified below. PORTIONS OPEN TO THE PUBLIC: 1. Report from...

Interim format and content for a physical security plan for nuclear power plants

International Nuclear Information System (INIS)

1977-02-01

The document serves as interim guidance to assist the licensee or applicant in the preparation of a physical security plan. It is to be used in conjunction with interim acceptance criteria for physical security programs, which will be distributed at a later date

ASPECTS CONCERNING INTERIM FINANCIAL REPORTING IN ROMANIA: STANDARDS AND REGULATIONS

Directory of Open Access Journals (Sweden)

Aristita Rotila

2014-12-01

Full Text Available The mechanisms employed for the communication of accounting information that is necessary for users in their economic decision-making process consist of the financial statements of an entity. All legal entities, no matter the domain of their activity, have the obligation to draw up annual financial statements for every completed financial year. For certain categories of entities, reporting obligations are also required for periods other than the annual reporting, throughout the financial year. It is the case of interim financial reporting. At the level of the international accounting framework, the aspects related to interim financial reporting are the subject of a separate standard, namely, IAS 34 Interim Financial Reporting. In Romania, the current system of accounting regulations concerning the annual financial statements comprises accounting regulations that comply with the European directives and which apply to the various categories of entities, on the one hand and, on the other, accounting regulations in line with the IFRS, which are applicable to other classes of entities from certain activity sectors. The accounting regulations that apply to each category refer to, among other things, the contents and the format of financial statements that have to be presented. Analysing the system of norms and regulations, this article identifies the requirements concerning interim financial reporting in Romania, with reference to the different types of entities.

Taking interim actions: Integrating CERCLA and NEPA to move ahead with site cleanup

International Nuclear Information System (INIS)

MacDonell, M.M.; Peterson, J.M.; Valett, G.L.; McCracken, S.H.

1991-01-01

The cleanup of contaminated sites can be expedited by using interim response actions in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended, and the National Oil and Hazardous Substances Pollution Contingency Plan (NCP). In fact, a major portion of some Superfund sites can be cleaned up using interim actions. For CERCLA sites being remediated by the US Department of Energy (DOE), such actions must also comply with the National Environmental Policy Act (NEPA) because the DOE has established a policy for integrating CERCLA and NEPA requirements. A strategy for the integrated documentation with implementation of interim actions has been applied successfully at the Weldon Spring site, and major cleanup projects are currently underway. This paper discusses some of the issues associated with integrating CERCLA and NEPA for interim actions and summarizes those actions that have been identified for the Weldon Spring site

Taking interim actions: Integrating CERCLA and NEPA to move ahead with site cleanup

International Nuclear Information System (INIS)

MacDonell, M.M.; Peterson, J.M.; Valett, G.L.; McCracken, S.H.

1991-01-01

The cleanup of contaminated sites can be expedited by using interim response actions in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended, and the National Oil and Hazardous Substances Pollution Contingency Plan (NCP). In fact, a major portion of some Superfund sites can be cleaned up using interim actions. For CERCLA sites being remediated by the US Department of Energy (DOE), such actions must also comply with the National Environmental Policy Act (NEPA) because the DOE has established a policy for integrating CERCLA and NEPA requirements. A strategy for the integrated documentation and implementation of interim actions has been applied successfully at the Weldon Spring site, and major cleanup projects are currently underway. This paper discusses some of the issues associated with integrating CERCLA and NEPA for interim actions and summarizes those actions that have been identified for the Weldon Spring site

78 FR 20359 - Sunshine Act Meetings; National Science Board

Science.gov (United States)

2013-04-04

... for May 2013 meeting. STATUS: Open. LOCATION: This meeting will be held by teleconference at the... visitors must report to the NSF visitor desk located in the lobby at the 9th and N. Stuart Streets entrance... information and updates (time, place, subject matter or status of meeting) may be found at http://www.nsf.gov...

19 CFR 354.8 - Interim sanctions.

Science.gov (United States)

2010-04-01

... reconsider imposition of interim sanctions on the basis of new and material evidence or other good cause... Secretary may petition a presiding official to impose such sanctions. (b) The presiding official may impose... person to return material previously provided by the Department and all other materials containing the...

Compilation of interim technical research memoranda. Volume I

International Nuclear Information System (INIS)

Shanahan, W.R.

1984-04-01

Four interim technical research memoranda are presented that describe the results of numerical simulations designed to investigate the dynamics of energetic plasma beams propagating across magnetic fields

Status of United States civilian waste management program

International Nuclear Information System (INIS)

Lawrence, M.J.

1984-01-01

The Nuclear Waste Policy Act of 1982 confirms the Federal responsibility for nuclear waste management and provides for unprecedented involvement by States, Indian tribes and the public. The Act provides a comprehensive framework for disposing of spent nuclear fuel and high-level radioactive wastes of domestic origin generated by civilian nuclear power reactors. It establishes detailed schedules and procedures for selecting and developing geologic repositories; provides a mechanism for financing the cost of disposal; and sets forth other provisions relating to nuclear waste disposal. The other provisions of the Act include provision for a user-financed federal interim storage facility with time and quantity limitations, as well as strict Nuclear Regulatory Commission-prescribed eligibility criteria; a proposal for a Federally-owned and operated monitored retrievable storage (MRS) facility for the interim period prior to operation of a permanent repository; and provision for a Test and Evaluation Facility (TEF). This paper centers on the schedule and current status and siting of the first two geologic repositories

20 CFR 200.6 - Open meetings.

Science.gov (United States)

2010-04-01

... information with respect to a meeting, the scheduling of a meeting, the establishment of the agenda of a meeting, or any change in the scheduling, agenda, or the open or closed status of a meeting; or (ii.... [42 FR 15312, Mar. 21, 1977, as amended at 42 FR 22865, Nov. 11, 1977. Redesignated at 52 FR 11010...

Kennedy Space Center Press Site (SWMU 074) Interim Measure Report

Science.gov (United States)

Applegate, Joseph L.

2015-01-01

This report summarizes the Interim Measure (IM) activities conducted at the Kennedy Space Center (KSC) Press Site ("the Press Site"). This facility has been designated as Solid Waste Management Unit 074 under KSC's Resource Conservation and Recovery Act Corrective Action program. The activities were completed as part of the Vehicle Assembly Building (VAB) Area Land Use Controls Implementation Plan (LUCIP) Elimination Project. The purpose of the VAB Area LUCIP Elimination Project was to delineate and remove soil affected with constituents of concern (COCs) that historically resulted in Land Use Controls (LUCs). The goal of the project was to eliminate the LUCs on soil. LUCs for groundwater were not addressed as part of the project and are not discussed in this report. This report is intended to meet the Florida Department of Environmental Protection (FDEP) Corrective Action Management Plan requirement as part of the KSC Hazardous and Solid Waste Amendments permit and the U.S. Environmental Protection Agency's (USEPA's) Toxic Substance Control Act (TSCA) self-implementing polychlorinated biphenyl (PCB) cleanup requirements of 40 Code of Federal Regulations (CFR) 761.61(a).

Proceedings of the Topical Meeting on the safety of nuclear fuel cycle intermediate storage facilities

International Nuclear Information System (INIS)

1998-01-01

The CSNI Working Group on Fuel Cycle Safety held an International Topical Meeting on safety aspects of Intermediate Storage Facilities in Newby Bridge, England, from 28 to 30 October 1997. The main purpose of the meeting was to provide a forum for the exchange of information on the technical issues on the safety of nuclear fuel cycle facilities (intermediate storage). Titles of the papers are: An international view on the safety challenges to interim storage of spent fuel. Interim storage of intermediate and high-level waste in Belgium: a description and safety aspects. Encapsulated intermediate level waste product stores at Sellafield. Safety of interim storage facilities of spent fuel: the international dimension and the IAEA's activities. Reprocessing of irradiated fuel and radwaste conditioning at Belgoprocess site: an overview. Retrieval of wastes from interim storage silos at Sellafield. Outline of the fire and explosion of the bituminization facility and the activities of the investigation committee (STAIJAERI). The fire and explosion incident of the bituminization facility and the lessons learned from the incident. Study on the scenario of the fire incident and related analysis. Study on the scenario of the explosion incident and related analysis. Accident investigation board report on the May 14, 1997 chemical explosion at the plutonium reclamation facility, Hanford site, Richland, Washington. Dry interim storage of spent nuclear fuel elements in Germany. Safe and effective system for the bulk receipt and storage of light water reactor fuel prior to reprocessing. Receiving and storage of glass canisters at vitrified waste storage center of Japan Nuclear Fuel Ltd. Design and operational experience of dry cask storage systems. Sellafield MOX plant; Plant safety design (BNFL). The assessment of fault studies for intermediate term waste storage facilities within the UK nuclear regulatory regime. Non-active and active commissioning of the thermal oxide

Interim research assessment 2003-2005 - Computer Science

NARCIS (Netherlands)

Mouthaan, A.J.; Hartel, Pieter H.

This report primarily serves as a source of information for the 2007 Interim Research Assessment Committee for Computer Science at the three technical universities in the Netherlands. The report also provides information for others interested in our research activities.

Interim radiological safety standards and evaluation procedures for subseabed high-level waste disposal

International Nuclear Information System (INIS)

Klett, R.D.

1997-06-01

The Seabed Disposal Project (SDP) was evaluating the technical feasibility of high-level nuclear waste disposal in deep ocean sediments. Working standards were needed for risk assessments, evaluation of alternative designs, sensitivity studies, and conceptual design guidelines. This report completes a three part program to develop radiological standards for the feasibility phase of the SDP. The characteristics of subseabed disposal and how they affect the selection of standards are discussed. General radiological protection standards are reviewed, along with some new methods, and a systematic approach to developing standards is presented. The selected interim radiological standards for the SDP and the reasons for their selection are given. These standards have no legal or regulatory status and will be replaced or modified by regulatory agencies if subseabed disposal is implemented. 56 refs., 29 figs., 15 tabs

Status of a MIND type Neutrino Factory Far Detector

International Nuclear Information System (INIS)

Bayes, R; Laing, A; Soler, F J P; Bross, A; Wands, R; Cervera, A; Ellis, M

2013-01-01

A realistic simulation and analysis of a Magnetized Iron Neutrino Detector (MIND) has been developed for the purpose of understanding the potential sensitivity of such a facility. The status of the MIND simulation and reconstruction as discussed in the interim design report is reviewed here. Priorities for producing a more realistic simulation for a reference design report will be discussed, as will be the steps that have already been taken towards an improved simulation.

75 FR 984 - Draft Recommended Interim Preliminary Remediation Goals for Dioxin in Soil at CERCLA and RCRA Sites

Science.gov (United States)

2010-01-07

...The Environmental Protection Agency (EPA or the Agency) is announcing a 50-day public comment period for draft recommended interim preliminary remediation goals (PRGs) developed in the Draft Recommended Interim Preliminary Remediation Goals for Dioxin in Soil at Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) and Resource Conservation and Recovery Act (RCRA) Sites. EPA's Office of Solid Waste and Emergency and Emergency Response (OSWER) has developed the draft recommended interim PRGs for dioxin in soil. These draft recommended interim PRGs were calculated using existing, peer- reviewed toxicity values and current EPA equations and default exposure assumptions. This Federal Register notice is intended to provide an opportunity for public comment on the draft recommended interim PRGs. EPA will consider any public comments submitted in accordance with this notice and may revise the draft recommended interim PRGs thereafter.

Report of a consultants meeting on control rod insertion reliability for WWER-1000 nuclear power plants. Extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

International Nuclear Information System (INIS)

1995-09-01

Starting from 1992, an increased drop time of control rods exceeding the design limit of four seconds has been observed in most of the operating WWER-1000 reactors in Russia and in the Ukraine. In some cases a dropped control rod became stuck in an intermediate position near the bottom of the core. In October 1994, a similar control rod problem was also observed at Unit 6 of the Kozloduy NPP. The issue of control rod insertion reliability was considered at a consultants' meeting on ''Core Control and Protection Strategy of WWER-1000 Reactors'' in April 1994. A consultants' meeting specifically focused on ''Control Rod Insertion Reliability'' was convened in Vienna in February 1995 attended by 15 international experts. The objectives of this meeting were: The exchange of international experience on problems and solutions related to anomalous control rod insertion; judgement of the safety concern of this issue for WWER-1000 reactors based on safety analyses; consideration of regulatory requirements and interim measures to continue operation in short term including modifications implemented or planned; and, status of root cause analyses and pending problems. The technical discussions were held in plenary sessions and in three working groups devoted to specific aspects of the issue. Refs, figs, tabs

75 FR 33307 - Employee Thrift Advisory Council Meeting; Sunshine Act; Notice of Meeting

Science.gov (United States)

2010-06-11

... FEDERAL RETIREMENT THRIFT INVESTMENT BOARD Employee Thrift Advisory Council Meeting; Sunshine Act; Notice of Meeting Time and Date: 10 a.m. (Eastern Time), June 24, 2010. Place: 4th Floor, Conference Room, 1250 H Street, NW., Washington, DC 20005. Status: All parts open to the public. Matters To Be...

EOS Aqua: Mission Status at the Earth Science Constellation (ESC) Mission Operations Working Group (MOWG) Meeting at the Kennedy Space Center (KSC)

Science.gov (United States)

Guit, Bill

2017-01-01

This presentation at the Earth Science Constellation Mission Operations Working Group meeting at KSC in December 2017 to discuss EOS (Earth Observing System) Aqua Earth Science Constellation status. Reviewed and approved by Eric Moyer, ESMO (Earth Science Mission Operations) Deputy Project Manager.

Tumor radiosensitizers - current status of development of various approaches: Report of an International Atomic Energy Agency meeting

DEFF Research Database (Denmark)

Horsman, Michael Robert; Bohm, Lothar; Margison, Geoffrey P.

2006-01-01

PURPOSE: The International Atomic Energy Agency (IAEA) held a Technical Meeting of Consultants to (1) discuss a selection of relatively new agents, not those well-established in clinical practice, that operated through a variety of mechanisms to sensitize tumors to radiation and (2) to compare...... and contrast their tumor efficacy, normal tissue toxicity, and status of development regarding clinical application. The aim was to advise the IAEA as to which developing agent or class of agents would be worth promoting further, by supporting additional laboratory research or clinical trials...... and for clinical trials that would be suitable for industrialized countries, as well as trials that were considered more appropriate for developing countries.PURPOSE: The International Atomic Energy Agency (IAEA) held a Technical Meeting of Consultants to (1) discuss a selection of relatively new agents, not those...

Search for a final repository site. How is the status of the preparation of final radioactive waste disposal in Germany?; Endlagersuche. Wie steht es um die Vorbereitung der Entsorgung radioaktiver Abfaelle in Deutschland?

Energy Technology Data Exchange (ETDEWEB)

Mueller, Monika C.M. (ed.) [Evangelische Akademie Loccum, Rehburg-Loccum (Germany). Arbeitsbereich Naturwissenschaften, Oekologie und Umweltpolitik

2017-07-01

During the workshop on the status of the preparation of final radioactive waste disposal in Germany the following issues were discussed: socio-economic challenges two years after the final report of the commission for final disposal of radioactive wastes; the question of public participation - the difficult search for a repository site, experiences and intents of public participation during the work of the commission, interim storage of hear generating radioactive wastes, extended interim-storage, long-term interim storage facilities - opinion of the concerned public, how to establish a controlling and correcting surveillance of the process?.

Plutonium Finishing Plant. Interim plutonium stabilization engineering study

Energy Technology Data Exchange (ETDEWEB)

Sevigny, G.J.; Gallucci, R.H.; Garrett, S.M.K.; Geeting, J.G.H.; Goheen, R.S.; Molton, P.M.; Templeton, K.J.; Villegas, A.J. [Pacific Northwest Lab., Richland, WA (United States); Nass, R. [Nuclear Fuel Services, Inc. (United States)

1995-08-01

This report provides the results of an engineering study that evaluated the available technologies for stabilizing the plutonium stored at the Plutonium Finishing Plant located at the hanford Site in southeastern Washington. Further processing of the plutonium may be required to prepare the plutonium for interim (<50 years) storage. Specifically this document provides the current plutonium inventory and characterization, the initial screening process, and the process descriptions and flowsheets of the technologies that passed the initial screening. The conclusions and recommendations also are provided. The information contained in this report will be used to assist in the preparation of the environmental impact statement and to help decision makers determine which is the preferred technology to process the plutonium for interim storage.

Plutonium Finishing Plant. Interim plutonium stabilization engineering study

International Nuclear Information System (INIS)

Sevigny, G.J.; Gallucci, R.H.; Garrett, S.M.K.; Geeting, J.G.H.; Goheen, R.S.; Molton, P.M.; Templeton, K.J.; Villegas, A.J.; Nass, R.

1995-08-01

This report provides the results of an engineering study that evaluated the available technologies for stabilizing the plutonium stored at the Plutonium Finishing Plant located at the hanford Site in southeastern Washington. Further processing of the plutonium may be required to prepare the plutonium for interim (<50 years) storage. Specifically this document provides the current plutonium inventory and characterization, the initial screening process, and the process descriptions and flowsheets of the technologies that passed the initial screening. The conclusions and recommendations also are provided. The information contained in this report will be used to assist in the preparation of the environmental impact statement and to help decision makers determine which is the preferred technology to process the plutonium for interim storage

DATA MINING METHODOLOGY FOR DETERMINING THE OPTIMAL MODEL OF COST PREDICTION IN SHIP INTERIM PRODUCT ASSEMBLY

Directory of Open Access Journals (Sweden)

Damir Kolich

2016-03-01

Full Text Available In order to accurately predict costs of the thousands of interim products that are assembled in shipyards, it is necessary to use skilled engineers to develop detailed Gantt charts for each interim product separately which takes many hours. It is helpful to develop a prediction tool to estimate the cost of interim products accurately and quickly without the need for skilled engineers. This will drive down shipyard costs and improve competitiveness. Data mining is used extensively for developing prediction models in other industries. Since ships consist of thousands of interim products, it is logical to develop a data mining methodology for a shipyard or any other manufacturing industry where interim products are produced. The methodology involves analysis of existing interim products and data collection. Pre-processing and principal component analysis is done to make the data “user-friendly” for later prediction processing and the development of both accurate and robust models. The support vector machine is demonstrated as the better model when there are a lower number of tuples. However as the number of tuples is increased to over 10000, then the artificial neural network model is recommended.

Status of nuclear data needed for radiation therapy and existing data development activities in Member States. Summary report of a consultants' meeting

International Nuclear Information System (INIS)

Kocherov, N.P.

1997-01-01

The present report contains the summary of the IAEA Consultants' Meeting on the ''Status of nuclear data needed for radiation therapy and existing data development activities in Member States'' held at the IAEA Headquarters, Vienna, 9-11 December 1996. The present activities on nuclear data for radiotherapy are summarized in Member States, the present status of nuclear data for photon, neutron and proton therapy is reviewed and topics which are not presently covered by other institutions are identified. (author). 4 refs, 2 figs

18 CFR 300.20 - Interim acceptance and review of Bonneville Power Administration rates.

Science.gov (United States)

2010-04-01

... 18 Conservation of Power and Water Resources 1 2010-04-01 2010-04-01 false Interim acceptance and review of Bonneville Power Administration rates. 300.20 Section 300.20 Conservation of Power and Water... Director of the Office of Energy Market Regulation; or (ii) Deny the Administrator's interim rate request...

Fuel Supply Shutdown Facility Interim Operational Safety Requirements

International Nuclear Information System (INIS)

BENECKE, M.W.

2000-01-01

The Interim Operational Safety Requirements for the Fuel Supply Shutdown (FSS) Facility define acceptable conditions, safe boundaries, bases thereof, and management of administrative controls to ensure safe operation of the facility

78 FR 77736 - Sunshine Act Meetings

Science.gov (United States)

2013-12-24

..., 2013, January 6, 13, 20, 27, 2014. PLACE: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. Week of December 23, 2013 There are no meetings scheduled... Casks (Public Meeting); (Contact: Kevin Witt, 301-415-2145) This meeting will be webcast live at the Web...

78 FR 39781 - Sunshine Act Meeting

Science.gov (United States)

2013-07-02

... LEGAL SERVICES CORPORATION Sunshine Act Meeting Notice Date and Time: The Legal Services... disrupting the meeting, please refrain from placing the call on hold if doing so will trigger recorded music or other sound. From time to time, the Chair may solicit comments from the public. Status of Meeting...

78 FR 33114 - Sunshine Act Meetings

Science.gov (United States)

2013-06-03

... LEGAL SERVICES CORPORATION Sunshine Act Meetings ACTION: Notice. Date And Time: The Legal Services... meeting, please refrain from placing the call on hold if doing so will trigger recorded music or other sound. From time to time, the Chair may solicit comments from the public. Status Of Meeting: Open...

Interim report of working group of Nuclear Fusion Committee

International Nuclear Information System (INIS)

Takuma, Hiroshi

1986-01-01

The conclusion of the working group was presented as an interim report to the general meeting of Nuclear Fusion Committee, which became the base for deciding the future plan. The report was the result of the hard work for about a half year by five Committee experts and 23 researchers, and has the rich contents. At present, the supply of petroleum relaxed, and the trend that a large amount of investment for a long period for nuclear fusion research is problematical has become strong. Of course, the importance of the nuclear fusion research never changes. The research projects of Heliotron E, Gekko 12, Gamma 10 and so on have advanced, and the base for synthetically promoting the research has been completed. It is indispensable to decide the most effective plan for the next stage. The working group discussed on the five year plan, especially on the research based on a large project. The policy of the works and problems, the progress of the works of respective subgroups, and the summarization are reported. The researches on nuclear burning simulation, no current plasma using an external conductor system and making an axisymmetrical high-beta torus steady were proposed. (Kako, I.)

77 FR 24492 - Employee Thrift Advisory Council Meeting; Notice of Sunshine Act Meeting

Science.gov (United States)

2012-04-24

... FEDERAL RETIREMENT THRIFT INVESTMENT BOARD Employee Thrift Advisory Council Meeting; Notice of Sunshine Act Meeting TIME AND DATE: 9 a.m. (Eastern Time) April 30, 2012. PLACE: 10th Floor Training Room, 77 K Street NE., Washington, DC 20002. STATUS: Parts will be open to the public and parts closed to...

Interim status of the Texas uranium survey experiment

International Nuclear Information System (INIS)

Jupiter, C.; Wollenberg, H.

1974-01-01

The objective of the Texas uranium survey experiment is to evaluate an improved method for prospecting for uranium by determining correlations among (a) geologic analysis, (b) soil sample radiochemical analysis, (c) aerial radiometric data, (d) aerial infrared scans, and (e) aerophotographic data. Although aerial radiometric measurements have been used previously in mineral prospecting, the development of useful correlative techniques based on analysis of data from large terrestrial areas employing the five parameters (a through e, above) remains to be evaluated, and could be of significant value to the need for establishing uranium resource pools to meet the nation's energy crisis. The Texas uranium survey field experiment began on June 13, 1973, employing a Martin-404 aircraft to fly gamma-ray recording equipment at a 500-ft altitude over two areas in southeast Texas. The areas surveyed are referred to as the Dubose area (approximately 120 sq. miles) and the Clay West area (approximately 24 sq. miles). This document briefly summarizes the work which has been done, describes the kind and quality of calibrations and data analysis carried out thus far and outlines recommended additional work which would bring the experiment to some degree of completion, providing a basis for evaluating the techniques

80th Annual Meeting | Annual Meetings | Events | Indian Academy of ...

Indian Academy of Sciences (India)

Current status and future prospects of neutrino mass measurement. View presentation ... Business Meeting of Fellows. 17.00. High Tea ... Hints of 'Beyond Standard Model' cosmology in the cosmic microwave background. View presentation.

75 FR 15419 - Sunshine Act Meetings

Science.gov (United States)

2010-03-29

.... Status: Commission Meeting--Open to the Public. Matter To Be Considered 1. Pending Decisional Matter: Definition of Children's Product-- Notice of Proposed Rulemaking (NPR). A live Web cast of the Meeting can be...

On-site interim storage of spent nuclear fuel: Emerging public issues

International Nuclear Information System (INIS)

Feldman, D.L.; Tennessee Univ., Knoxville, TN

1992-01-01

Failure to consummate plans for a permanent repository or above- ground interim Monitored Retrievable Storage (MRS) facility for spent nuclear fuel has spurred innovative efforts to ensure at-reactor storage in an environmentally safe and secure manner. This article examines the institutional and socioeconomic impacts of Dry Cask Storage Technology (DCST)-an approach to spent fuel management that is emerging as the preferred method of on-site interim spent fuel storage by utilities that exhaust existing storage capacity

Environmental assessment for 881 Hillside (High Priority Sites) interim remedial action

International Nuclear Information System (INIS)

1990-01-01

This Environmental Assessment evaluates the impact of an interim remedial action proposed for the High Priority Sites (881 Hillside Area) at the Rocky Flats Plant (RFP). This interim action is to be conducted to minimize the release of hazardous substances from the 881 Hillside Area that pose a potential long-term threat to public health and the environment. This document integrates current site characterization data and environmental analyses required by the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) or ''Superfund'' process, into an environmental assessment pursuant to the National Environmental Policy Act (NEPA). Characterization of the 881 Hillside Area is continuing. Consequently, a final remedial action has not yet been proposed. Environmental impacts associated with the proposed interim remedial action and reasonable alternatives designed to remove organic and inorganic contaminants, including radionuclides, from alluvial groundwater in the 881 Hillside Area are addressed. 24 refs., 5 figs., 23 tabs

77 FR 33252 - Sunshine Act Meeting

Science.gov (United States)

2012-06-05

.... PLACE: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and closed. Week of June 4, 2012 Thursday, June 7, 2012 9:25 a.m. Affirmation Session (Public Meeting... meeting will be webcast live at the Web address--www.nrc.gov. 9:30 a.m. Meeting with the Advisory...

78 FR 16893 - Sunshine Act Meetings

Science.gov (United States)

2013-03-19

...: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. [[Page... Flannery, 301-415-0223) This meeting will be webcast live at the Web address--www.nrc.gov. Week of April 8... Accident (Public Meeting) (Contact: William D. Reckley, 301- 415-7490) This meeting will be webcast live at...

Status of legislation

International Nuclear Information System (INIS)

Warner, C.

1982-01-01

The status of the House legislation, the major differences between the House and Senate legislation and a preview of what is likely to take place during the lame duck session in December are presented. The House legislation provides: long-term program leading toward permanent disposal of nuclear waste; an interim program for storage and for expansion of storage space for spent fuel; provides an R and D component through what is called a test and evaluation facility; an alternative long-term storage program based on a proposal to be completed by the Department of Energy on what's called Monitored Retrievable Storage; full upfront financing of the program through user fees based on contracts between the government and the users of the nuclear waste disposal services

77 FR 10575 - Sunshine Act Meetings

Science.gov (United States)

2012-02-22

...: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. Week of... meeting will be webcast live at the Web address--www.nrc.gov. 9 a.m.--Briefing on Fort Calhoun (Public Meeting) (Contact: Jeff Clark, 817-860-8147). This meeting will be webcast live at the Web address--www...

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)

Administrative Court Stade, decision of March 22, 1985 (interim storage facility at Gorleben)

International Nuclear Information System (INIS)

Anon.

1985-01-01

This decision deals with the planned interim storage facility of Gorleben (F.R.G.). The provisions introduced by the 4th ammendment to sec. 5 para. 6 and 9a to 9c of the German Atomic Energy Act might contain a definite regulation of the 'Entsorgung' of nuclear power stations. Sec. 6 of the Atomic Energy Act is not applicable to interim storage facilities because irradiated nuclear fuel has a double nature: It is spent fuel and nuclear waste as well. Considering current licensing procedures of construction and operation of nuclear installations in the field of 'Entsorgung', special legal regulations for the construction and operation of an interim storage facility have to be required. (CW)

Interim storage study report

Energy Technology Data Exchange (ETDEWEB)

Rawlins, J.K.

1998-02-01

High-level radioactive waste (HLW) stored at the Idaho Chemical Processing Plant (ICPP) in the form of calcine and liquid and liquid sodium-bearing waste (SBW) will be processed to provide a stable waste form and prepare the waste to be transported to a permanent repository. Because a permanent repository will not be available when the waste is processed, the waste must be stored at ICPP in an Interim Storage Facility (ISF). This report documents consideration of an ISF for each of the waste processing options under consideration.

Conceptual design report for immobilized high-level waste interim storage facility (Phase 1)

International Nuclear Information System (INIS)

Burgard, K.C.

1998-01-01

The Hanford Site Canister Storage Building (CSB Bldg. 212H) will be utilized to interim store Phase 1 HLW products. Project W-464, Immobilized High-Level Waste Interim Storage, will procure an onsite transportation system and retrofit the CSB to accommodate the Phase 1 HLW products. The Conceptual Design Report establishes the Project W-464 technical and cost basis

Conceptual design report for immobilized high-level waste interim storage facility (Phase 1)

Energy Technology Data Exchange (ETDEWEB)

Burgard, K.C.

1998-04-09

The Hanford Site Canister Storage Building (CSB Bldg. 212H) will be utilized to interim store Phase 1 HLW products. Project W-464, Immobilized High-Level Waste Interim Storage, will procure an onsite transportation system and retrofit the CSB to accommodate the Phase 1 HLW products. The Conceptual Design Report establishes the Project W-464 technical and cost basis.

78 FR 57621 - Sunshine Act Meeting

Science.gov (United States)

2013-09-19

... CONSUMER PRODUCT SAFETY COMMISSION Sunshine Act Meeting TIME AND DATE: Wednesday, September 25..., Maryland. STATUS: Commission Meeting--Open to the public Matters To Be Considered Briefing Matter: Voluntary Recall Notice--Notice of Proposed Rulemaking. [[Page 57622

THE IMPORTANCE OF FINANCIAL INTERIM REPORTING FOR THE POSITION OF COMPANIES

Directory of Open Access Journals (Sweden)

Claudia‐Elena\tGRIGORAȘ‐ICHIM

2015-12-01

Full Text Available The importance that each company must grant to the strategic sources of information generates our concern for analysis of the interim financial reporting. In every enterprise, there are doubts on the usefulness of interim financial reports, given the following elements: the necessary time for their preparation (relatively long, their restricted character and the resources necessary to establish them. Finding a common solution to these problems and, implicitly, increasing the interest for interim financial reporting, can help to increase the economic performance of the company, either by reducing the unnecessary costs related to time, or by increasing communication and transparency with third parties. An appropriate management can act early in the direction of counteracting the negative effects in their company or prevention of any commercial or production failures, the overall economic trends in that field and increasing productivity. Starting from these premises, we propose a research in order to capture the main aspects related to the mentioned issues.

Fiscal 1991 report on the brown coal liquefaction section meeting; 1991 nendo kattan ekika bukai hokokusho

Energy Technology Data Exchange (ETDEWEB)

NONE

1992-03-01

At the 1st through 5th brown coal liquefaction group meetings held for the fiscal year, reports are delivered and discussions are made about the progress of research and development. At the 1st meeting, a fiscal 1991 brown coal liquefaction research plan is introduced, and discussed. At the 2nd meeting, an interim report on the brown coal liquefaction technology development project is discussed. At the 3rd meeting (a joint meeting of the brown coal and bituminous coal liquefaction groups), an agendum entitled 'what the development of brown/bituminous coal liquefaction technologies for the 21st century should be' is reported, and discussed. At the 4th meeting, reports are made on the results of deliberation at the Industrial Technology Council, progress of the follow-up study, progress of the collection of achievements, and so forth. At the 5th meeting, the outline of the follow-up study, the collection of achievements in the pilot plant study (a project report preparation schedule and materials evaluation), the progress of pilot plant dismantling work, etc., are reported and discussed. (NEDO)

Fiscal 1991 report on the brown coal liquefaction section meeting; 1991 nendo kattan ekika bukai hokokusho

Energy Technology Data Exchange (ETDEWEB)

NONE

1992-03-01

At the 1st through 5th brown coal liquefaction group meetings held for the fiscal year, reports are delivered and discussions are made about the progress of research and development. At the 1st meeting, a fiscal 1991 brown coal liquefaction research plan is introduced, and discussed. At the 2nd meeting, an interim report on the brown coal liquefaction technology development project is discussed. At the 3rd meeting (a joint meeting of the brown coal and bituminous coal liquefaction groups), an agendum entitled 'what the development of brown/bituminous coal liquefaction technologies for the 21st century should be' is reported, and discussed. At the 4th meeting, reports are made on the results of deliberation at the Industrial Technology Council, progress of the follow-up study, progress of the collection of achievements, and so forth. At the 5th meeting, the outline of the follow-up study, the collection of achievements in the pilot plant study (a project report preparation schedule and materials evaluation), the progress of pilot plant dismantling work, etc., are reported and discussed. (NEDO)

Long-term interim storage concepts with conditioning strategies ensuring compatibility with subsequent disposal or reprocessing

International Nuclear Information System (INIS)

Moitrier, C.; Tirel, I.; Villard, C.

2000-01-01

The objective of the CEA studies carried out under research topic 3 (long-term interim storage) of the 1991 French radioactive waste management law is to demonstrate the industrial feasibility of a comprehensive, flexible interim storage facility by thoroughly evaluating and comparing all the basic components of various interim storage concepts. In this context, the CEA is considering reference solutions or concepts based on three primary components (the package, the interim storage facility and the site) suitable for determining the specifications of a very long-term solution. Some aspects are examined in greater detail, such as the implementation of long-term technologies, conditioning processes ensuring the absence of water and contamination in the facility, or allowance for radioactive decay of the packages. The results obtained are continually compiled in reports substantiating the design options. These studies should also lead to an overall economic assessment in terms of the capital and operating cost requirements, thereby providing an additional basis for selecting the design options. The comparison with existing industrial facilities highlights the technical and economic progress represented by the new generation of interim storage units. (authors)

Application of dose evaluation of the MCNP code for interim spent fuel cask storage facility

International Nuclear Information System (INIS)

Kosako, Toshiso; Iimoto, Takeshi; Ishikawa, Satoshi; Tsuboi, Takafumi; Teramura, Masahiro; Okamura, Tomomi; Narumiya, Yoshiyuki

2007-01-01

The interim storage facility for spent fuel metallic cask is designed as a concrete building structure with air inlet and outlet for circulating the natural cooling. The feature of the interim storage facility is big capacity of spent fuel at several thousands MTU and restricted site usage. It is important to evaluate realistic dose rate in shielding design of the interim storage facility, therefore the three-dimensional continuous-energy Monte Carlo radiation transport code MCNP that exactly treating the complicated geometry was applied. The validation of dose evaluation for interim storage facility by MCNP code were performed by three kinds of neutron shielding benchmark experiments; cask shadow shielding experiment, duct streaming experiment and concrete deep penetration experiment. Dose rate distributions at each benchmark were measured and compared with the calculated results. The comparison showed a good consistency between calculation and experiment results. (author)

Interim data report for the safety assessment SR-Can

International Nuclear Information System (INIS)

Vahlund, Fredrik; Andersson, Johan

2004-08-01

This document is the interim data report in the project SR-Can. The purpose of the data report is to present input data, with uncertainty estimates, for the SR-Can assessment calculations. Besides input data, the report also describes the standardised procedures used when deriving the input data and the corresponding uncertainty estimates. However, in the present interim version of the report (written in the initial stage of the project when site characterisation has yet not been completed) the standardised procedures have not been possible to apply for most of the data and, in order to present a compilation of the data used in the assessment, much of the input data is presented without following the standardised procedures. This will however be changed for the final version of the SR-Can data report, in order to show the methodology that will be used in the final version one example of how input data will be presented is included (migration data for buffer) . The recommended input data for the assessment calculations are, for the interim version, mainly based on SR 97 Beberg data, these are merely presented without any background or uncertainty discussion (this is presented in the SR 97 data report)

Interim Storage Facility decommissioning. Final report

International Nuclear Information System (INIS)

Johnson, R.P.; Speed, D.L.

1985-01-01

Decontamination and decommissioning of the Interim Storage Facility were completed. Activities included performing a detailed radiation survey of the facility, removing surface and imbedded contamination, excavating and removing the fuel storage cells, restoring the site to natural conditions, and shipping waste to Hanford, Washington, for burial. The project was accomplished on schedule and 30% under budget with no measurable exposure to decommissioning personnel

Single-shell tank interim stabilization project plan

Energy Technology Data Exchange (ETDEWEB)

Ross, W.E.

1998-05-11

This project plan establishes the management framework for conduct of the TWRS Single-Shell Tank Interim Stabilization completion program. Specifically, this plan defines the mission needs and requirements; technical objectives and approach; organizational structure, roles, responsibilities, and interfaces; and operational methods. This plan serves as the project executional baseline.

14 CFR 136.41 - Interim operating authority.

Science.gov (United States)

2010-01-01

... AND NATIONAL PARKS AIR TOUR MANAGEMENT National Parks Air Tour Management § 136.41 Interim operating... terminate 180 days after the date on which an air tour management plan is established for the park and tribal lands; (6) Shall promote protection of national park resources, visitor experiences, and tribal...

Alternatives for managing wastes from reactors and post-fission operations in the LWR fuel cycle. Volume 3. Alternatives for interim storage and transportation

International Nuclear Information System (INIS)

1976-05-01

Volume III of the five-volume report contains information on alternatives for interim storage and transportation. Section titles are: interim storage of spent fuel elements; interim storage of chop-leach fuel bundle residues; tank storage of high-level liquid waste; interim storage of solid non-high-level wastes; interim storage of solidified high-level waste; and, transportation alternatives

PROJECT W-551 INTERIM PRETREATMENT SYSTEM TECHNOLOGY SELECTION SUMMARY DECISION REPORT AND RECOMMENDATION

International Nuclear Information System (INIS)

CONRAD EA

2008-01-01

This report provides the conclusions of the tank farm interim pretreatment technology decision process. It documents the methodology, data, and results of the selection of cross-flow filtration and ion exchange technologies for implementation in project W-551, Interim Pretreatment System. This selection resulted from the evaluation of specific scope criteria using quantitative and qualitative analyses, group workshops, and technical expert personnel

Informal meeting on ITER developments

International Nuclear Information System (INIS)

Canobbio, E.

2000-01-01

The International Fusion Research Council (IFRC), advisory body of the IAEA, organized an informal meeting on the general status and outlook for ITER, held October 9 at Sorrento, Italy, in conjunction with the 18th IAEA Fusion Energy Conference. This article describes the main events at the meeting

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)

Rosiglitazone evaluated for cardiovascular outcomes--an interim analysis

DEFF Research Database (Denmark)

Home, Philip D; Pocock, Stuart J; Beck-Nielsen, Henning

2007-01-01

BACKGROUND: A recent meta-analysis raised concern regarding an increased risk of myocardial infarction and death from cardiovascular causes associated with rosiglitazone treatment of type 2 diabetes. METHODS: We conducted an unplanned interim analysis of a randomized, multicenter, open...... group). The primary end point was hospitalization or death from cardiovascular causes. RESULTS: Because the mean follow-up was only 3.75 years, our interim analysis had limited statistical power to detect treatment differences. A total of 217 patients in the rosiglitazone group and 202 patients...... in the control group had the adjudicated primary end point (hazard ratio, 1.08; 95% confidence interval [CI], 0.89 to 1.31). After the inclusion of end points pending adjudication, the hazard ratio was 1.11 (95% CI, 0.93 to 1.32). There were no statistically significant differences between the rosiglitazone...

Poor predictive value of positive interim FDG-PET/CT in primary mediastinal large B-cell lymphoma

Energy Technology Data Exchange (ETDEWEB)

Lazarovici, Julien; Petrovanu, Cynthia; Danu, Alina; Ferme, Christophe; Ribrag, Vincent; Ghez, David [Gustave Roussy, Villejuif (France). Dept. of Hematology; Paris Saclay Univ., Saint-Aubin (France); Terroir, Marie [Gustave Roussy, Villejuif (France). Dept. of Nuclear Medicine and Endocrine Oncology; Paris Saclay Univ., Saint-Aubin (France); Arfi-Rouche, Julia [Gustave Roussy, Villejuif (France). Dept. of Radiology; Paris Saclay Univ., Saint-Aubin (France); Michot, Jean-Marie [Gustave Roussy, Villejuif (France). Dept. of Drug Development (DITEP); Paris Saclay Univ., Saint-Aubin (France); Mussot, Sacha; Florea, Valentina [Marie Lannelongue Hospital, Le Plessis Robinson (France). Dept. of Thoracic Surgery; Ghigna, Maria-Rosa [Marie Lannelongue Hospital, Le Plessis Robinson (France). Dept. of Pathology; Dartigues, Peggy [Gustave Roussy, Villejuif (France). Dept. of Pathology; Paris Saclay Univ., Saint-Aubin (France)

2017-11-15

Though commonly used to assess response to therapy, the prognostic value of interim FDG-PET/CT in Primary Mediastinal Large B-cell Lymphoma (PMBCL) is unclear. We conducted a retrospective study on 36 consecutive patients treated at our institution for a PMBCL between 2006 and 2014. All patients with a positive interim FDG-PET/CT had undergone histological restaging consisting either in a surgical debulking of the residual lesion (15 patients) or a CT-guided core needle biopsy (two patients). All FDG-PET/CT were secondarily reviewed according to the more recent Deauville criteria. Interim FDG-PET/CT was considered positive in 17/36 patients using visual evaluation. Among these patients, 14 had a Deauville score of 4. Histological restaging was negative in all but one case, showing inflammation and/or fibrosis. After a median follow-up of 48.5 months, a total of five patients have relapsed, two patients in the positive FDG-PET/CT group, and three patients in the negative FDG-PET/CT group, respectively. These data indicate that a positive interim FDG-PET/CT does not reflect persistence of active disease in the vast majority of PMBCL cases. The relapse rate appears similar regardless of interim FDG-PET/CT results and interpretation criteria. This suggests that interim FDG-PET/CT has a poor positive predictive value, thus kt should be used with caution in PMBCL. (orig.)

77 FR 74883 - Sunshine Act Meeting Notice

Science.gov (United States)

2012-12-18

.... PLACE: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. Week of December 17, 2012 There are no meetings scheduled for the week of December 17, 2012. Week... Calhoun (Public Meeting) (Contact: Michael Hay, 817-200-1527) This meeting will be webcast live at the Web...

75 FR 13484 - Foreign-Trade Zone 22; Temporary/Interim Manufacturing Authority; LG Electronics Mobilecomm USA...

Science.gov (United States)

2010-03-22

... DEPARTMENT OF COMMERCE [Docket T-1-2010] Foreign-Trade Zones Board Foreign-Trade Zone 22; Temporary/Interim Manufacturing Authority; LG Electronics Mobilecomm USA, Inc. (Cell Phones); Notice of.../ interim manufacturing (T/IM) authority, on behalf of LG Electronics Mobilecomm USA, Inc. (LGEMU), to...

Interim Action Proposed Plan for the Chemicals, Metals, and Pesticides (CMP) Pits Operable Unit; FINAL

International Nuclear Information System (INIS)

Bradley, J.

2002-01-01

The purpose of this Interim Action Proposed Plan (IAPP) is to describe the preferred interim remedial action for addressing the Chemicals, Metals, and Pesticides (CMP) Pits Operable Unit and to provide an opportunity for public input into the remedial action selection process

Automotive Mechanics Occupational Performance Survey. Interim Report.

Science.gov (United States)

Borcher, Sidney D.; Leiter, Paul B.

The purpose of this federally-funded interim report is to present the results of a task inventory analysis survey of automotive mechanics completed by project staff within the Instructional Systems Design Program at the Center for Vocational and Technical Education. Intended for use in curriculum development for vocational education programs in…

340 waste handling facility interim safety basis

Energy Technology Data Exchange (ETDEWEB)

VAIL, T.S.

1999-04-01

This document presents an interim safety basis for the 340 Waste Handling Facility classifying the 340 Facility as a Hazard Category 3 facility. The hazard analysis quantifies the operating safety envelop for this facility and demonstrates that the facility can be operated without a significant threat to onsite or offsite people.

340 waste handling facility interim safety basis

International Nuclear Information System (INIS)

VAIL, T.S.

1999-01-01

This document presents an interim safety basis for the 340 Waste Handling Facility classifying the 340 Facility as a Hazard Category 3 facility. The hazard analysis quantifies the operating safety envelop for this facility and demonstrates that the facility can be operated without a significant threat to onsite or offsite people

Finding of no significant impact. Consolidation and interim storage of special nuclear material at Rocky Flats Environmental Technology Site

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-06-01

The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA -- 1060, for the consolidation, processing, and interim storage of Category I and II special nuclear material (SNM) in Building 371 at the Rocky Flats Environmental Technology Site (hereinafter referred to as Rocky Flats or Site), Golden, Colorado. The scope of the EA included alternatives for interim storage including the no action alternative, the construction of a new facility for interim storage at Rocky Flats, and shipment to other DOE facilities for interim storage.

Finding of no significant impact. Consolidation and interim storage of special nuclear material at Rocky Flats Environmental Technology Site

International Nuclear Information System (INIS)

1995-06-01

The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA -- 1060, for the consolidation, processing, and interim storage of Category I and II special nuclear material (SNM) in Building 371 at the Rocky Flats Environmental Technology Site (hereinafter referred to as Rocky Flats or Site), Golden, Colorado. The scope of the EA included alternatives for interim storage including the no action alternative, the construction of a new facility for interim storage at Rocky Flats, and shipment to other DOE facilities for interim storage

78 FR 70244 - Electronic Interim Assistance Reimbursement Program

Science.gov (United States)

2013-11-25

..., Social Security Online, at http://www.socialsecurity.gov . SUPPLEMENTARY INFORMATION: Background To be... SOCIAL SECURITY ADMINISTRATION 20 CFR Part 416 [Docket No. SSA-2011-0104] RIN 0960-AH45 Electronic Interim Assistance Reimbursement Program AGENCY: Social Security Administration. ACTION: Notice of...

Federal Administrative Court confirms interim action for the Kruemmel power plant site

International Nuclear Information System (INIS)

Anon.

1982-01-01

The interim action concerning the reactor site was confirmed in 1972, the action of voidance because of the possible injuriousness to health was rejected in the first instance. In the appeal OVG Lueneburg had sharpened three clauses concerning the contents of the restrictions and injunctions included in the interim action to the disadvantage of the operator. Responding to a new appeal the BVerwG has eliminated these restrictions and dismissed the following appeals of the plaintiffs. (HP) [de

77 FR 34935 - Foreign-Trade Zone 161; Temporary/Interim Manufacturing Authority; Siemens Energy, Inc., (Wind...

Science.gov (United States)

2012-06-12

... DEPARTMENT OF COMMERCE Foreign-Trade Zones Board [Docket T-4-2012] Foreign-Trade Zone 161; Temporary/Interim Manufacturing Authority; Siemens Energy, Inc., (Wind Turbine Nacelles and Hubs); Notice of... temporary/interim manufacturing (T/IM) authority, on behalf of Siemens Energy, Inc., to manufacture wind...

Using ERA-Interim reanalysis for creating datasets of energy-relevant climate variables

Science.gov (United States)

Jones, Philip D.; Harpham, Colin; Troccoli, Alberto; Gschwind, Benoit; Ranchin, Thierry; Wald, Lucien; Goodess, Clare M.; Dorling, Stephen

2017-07-01

The construction of a bias-adjusted dataset of climate variables at the near surface using ERA-Interim reanalysis is presented. A number of different, variable-dependent, bias-adjustment approaches have been proposed. Here we modify the parameters of different distributions (depending on the variable), adjusting ERA-Interim based on gridded station or direct station observations. The variables are air temperature, dewpoint temperature, precipitation (daily only), solar radiation, wind speed, and relative humidity. These are available on either 3 or 6 h timescales over the period 1979-2016. The resulting bias-adjusted dataset is available through the Climate Data Store (CDS) of the Copernicus Climate Change Data Store (C3S) and can be accessed at present from climate.copernicus.eu" target="_blank">ftp://ecem.climate.copernicus.eu. The benefit of performing bias adjustment is demonstrated by comparing initial and bias-adjusted ERA-Interim data against gridded observational fields.

The ITER Management Advisory Committee (MAC) meeting in Garching

International Nuclear Information System (INIS)

Yoshikawa, M.

1999-01-01

The ITER management advisory committee meeting was held on 22-23 July 1999 in Garching, Germany. The main topics were the ITER EDA status, task status summary and work program, joint fund, information technology needs at the ITER joint work sites, the disposition of R and D components and a schedule of ITER meetings

78 FR 72931 - Sunshine Act Meeting Notice

Science.gov (United States)

2013-12-04

... 2, 9, 16, 23, 30, 2013, January 6, 2014. PLACE: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. Week of December 2, 2013 There are no meetings scheduled for... Dry Casks (Public Meeting) (Contact: Kevin Witt, 301-415-2145). This meeting will be webcast live at...

76 FR 26775 - Sunshine Act Meeting Notice

Science.gov (United States)

2011-05-09

...: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. Week of...-415-3951). This meeting will be webcast live at the Web address-- http://www.nrc.gov . Week of May 16...) (Public Meeting) (Contact: Rani Franovich, 301-415-1868). This meeting will be webcast live at the Web...

EPA's Revised Interim Financial Assistance Conflict of Interest Policy

Science.gov (United States)

EPA has established the following revised interim policy governing disclosure of actual and potential conflicts of interest (COI Policy) by applicants for, and recipients of, federal financial assistance awards from EPA.

39 CFR 211.4 - Interim personnel regulations.

Science.gov (United States)

2010-07-01

... 39 Postal Service 1 2010-07-01 2010-07-01 false Interim personnel regulations. 211.4 Section 211.4... under the Postal Reorganization Act. (b) Continuation of Personnel Provisions of Former title 39, U.S.C... collective bargaining agreement under the Postal Reorganization Act, all provisions of former title 39, U.S.C...

National Ignition Facility Cryogenic Target Systems Interim Management Plan

International Nuclear Information System (INIS)

Warner, B

2002-01-01

Restricted availability of funding has had an adverse impact, unforeseen at the time of the original decision to projectize the National Ignition Facility (NIF) Cryogenic Target Handling Systems (NCTS) Program, on the planning and initiation of these efforts. The purpose of this document is to provide an interim project management plan describing the organizational structure and management processes currently in place for NCTS. Preparation of a Program Execution Plan (PEP) for NCTS has been initiated, and a current draft is provided as Attachment 1 to this document. The National Ignition Facility is a multi-megajoule laser facility being constructed at Lawrence Livermore National Laboratory (LLNL) by the National Nuclear Security Administration (NNSA) in the Department of Energy (DOE). Its primary mission is to support the Stockpile Stewardship Program (SSP) by performing experiments studying weapons physics, including fusion ignition. NIF also supports the missions of weapons effects, inertial fusion energy, and basic science in high-energy-density physics. NIF will be operated by LLNL under contract to the University of California (UC) as a national user facility. NIF is a low-hazard, radiological facility, and its operation will meet all applicable federal, state, and local Environmental Safety and Health (ES and H) requirements. The NCTS Interim Management Plan provides a summary of primary design criteria and functional requirements, current organizational structure, tracking and reporting procedures, and current planning estimates of project scope, cost, and schedule. The NIF Director controls the NIF Cryogenic Target Systems Interim Management Plan. Overall scope content and execution schedules for the High Energy Density Physics Campaign (SSP Campaign 10) are currently undergoing rebaselining and will be brought into alignment with resources expected to be available throughout the NNSA Future Years National Security Plan (FYNSP). The revised schedule for

Dry interim storage of radioactive material in Germany

International Nuclear Information System (INIS)

Drobniewski, Christian; Palmes, Julia

2013-01-01

In accordance with the waste management concept in Germany, spent fuel is stored in interim storage facilities for a period of up to 40 years until deposition in a geological repository. In twelve on-site interim storages in the vicinity or directly on the sites of the nuclear power plants, spent fuel elements from reactor operation are stored after the necessary period of decay in wet storage basins inside the reactors. Additionally, three central interim storage facilities for storage of spent fuel of different origin are in operation. The German facilities realize the concept of dry interim storage in metallic transport and storage casks. The confinement of the radioactive material is ensured by the double lid system of the casks, of which the leak tightness is monitored constantly. The casks are constructed to provide adequate heat removal and shielding of gamma and neutron radiation. Usually the storage facilities are halls of thick concrete structures, which ensure the removal of the decay heat by natural convection. The main safety goal of the storage concept is to prevent unnecessary exposure of persons, material goods and environment to ionizing radiation. Moreover any exposure should be kept as low as reasonable achievable. To reach this goal the containment of the radioactive materials, the disposal of decay heat, the sub criticality and the shielding of ionizing radiation has to be demonstrated by the applicant and verified by the licensing authority. In particular accidents, incidents and disasters have to be considered in the facility and cask design. This includes mechanical impacts onto the cask, internal and external fire, and environmental effects like wind, rain, snowfall, flood, earthquakes and landslides. In addition civilizatoric influences like plane crashes and explosions have to be taken into account. In all mentioned cases the secure confinement of the radioactive materials has to be ensured. On-site storage facilities have to consider the

Second meeting of the ITER Preparatory Committee

International Nuclear Information System (INIS)

Drew, M.

2003-01-01

The committee charged to oversee the ITER ITA (ITER transitional arrangements) the ITER preparatory committee, held its second meeting on 24 September at the JET facilities at Culham, UK. Dr. Umberto Finzi of the European Commission was chairman. This meeting was also the first since the succession by Dr. Yasuo Shimomura to Dr. Robert Aymar as Interim Project Leader (IPL). Welcoming Dr. Shimomura in his new capacity, the Committee paid tribute to the outstanding contributions of his predecessor to the definition, design and promotion of ITER, and expressed the gratitude of all Participants to Dr. Aymar and its best wishes for future success in his new appointment.The technical activities of the ITA were the main focus of the Committee's discussions. The Committee took note of the IPL's Status Report on ITA Technical Activities and endorsed the IPL's proposals for the top level structure of the International Team, including the designation of Dr. Pietro Barabaschi as Deputy to the IPL. The Committee took note of the IPL's proposals on Participants' contributions to the ITA and of the Participants' stated intentions and expectations in this regard. Several Delegations pointed out that access to necessary resources would depend strongly on progress made towards the Agreement. All Participants were invited, in the shared interests of the project, to respond constructively to the specific technical areas where the IPL reported a lack of resources. Following a presentation from the IT on Project Management Tools, the Committee expressed support, in general, for the proposed strategy designed to provide the current team with the CAD and Data Management elements necessary to prepare for an efficient start of ITER construction, and asked the IT Leader to report on an estimate and time profile of expenditure during the period to mid-2004. The Committee supported the proposals to re-establish the ITER Test Blanket Working. The Committee agreed that the phasing of planned

Guidelines for interim storage of low level waste

International Nuclear Information System (INIS)

Hornibrook, C.; Castagnacci, A.; Clymer, G.; Kelly, J.; Naughton, M.; Saunders, P.; Stoner, P.; Walker, N.; Cazzolli, R.; Dettenmeier, R.; Loucks, L.; Rigsby, M.; Spall, M.; Strum, M.

1992-12-01

This report presents an overview of on-site storage of Low Level Waste while providing guidelines for using the complete Interim On-Site Storage of Low Level Waste report series. Overall, this report provides a methodology for planning and implementing on-site storage

The Homestake Interim Laboratory and Homestake DUSEL

Science.gov (United States)

Lesko, Kevin T.

2011-12-01

The former Homestake gold mine in Lead South Dakota is proposed for the National Science Foundation's Deep Underground Science and Engineering Laboratory (DUSEL). The gold mine provides expedient access to depths in excess of 8000 feet below the surface (>7000 mwe). Homestake's long history of promoting scientific endeavours includes the Davis Solar Neutrino Experiment, a chlorine-based experiment that was hosted at the 4850 Level for more than 30 years. As DUSEL, Homestake would be uncompromised by competition with mining interests or other shared uses. The facility's 600-km of drifts would be available for conversion for scientific and educational uses. The State of South Dakota, under Governor Rounds' leadership, has demonstrated exceptionally strong support for Homestake and the creation of DUSEL. The State has provided funding totalling $46M for the preservation of the site for DUSEL and for the conversion and operation of the Homestake Interim Laboratory. Motivated by the strong educational and outreach potential of Homestake, the State contracted a Conversion Plan by world-recognized mine-engineering contractor to define the process of rehabilitating the facility, establishing the appropriate safety program, and regaining access to the facility. The State of South Dakota has established the South Dakota Science and Technology Authority to oversee the transfer of the Homestake property to the State and the rehabilitation and preservation of the facility. The Homestake Scientific Collaboration and the State of South Dakota's Science and Technology Authority has called for Letters of Interest from scientific, educational and engineering collaborations and institutions that are interested in hosting experiments and uses in the Homestake Interim Facility in advance of the NSF's DUSEL, to define experiments starting as early as 2007. The Homestake Program Advisory Committee has reviewed these Letters and their initial report has been released. Options for

The Homestake Interim Laboratory and Homestake DUSEL

International Nuclear Information System (INIS)

Lesko, Kevin T.

2011-01-01

The former Homestake gold mine in Lead South Dakota is proposed for the National Science Foundation's Deep Underground Science and Engineering Laboratory (DUSEL). The gold mine provides expedient access to depths in excess of 8000 feet below the surface (>7000 mwe). Homestake's long history of promoting scientific endeavours includes the Davis Solar Neutrino Experiment, a chlorine-based experiment that was hosted at the 4850 Level for more than 30 years. As DUSEL, Homestake would be uncompromised by competition with mining interests or other shared uses. The facility's 600-km of drifts would be available for conversion for scientific and educational uses. The State of South Dakota, under Governor Rounds' leadership, has demonstrated exceptionally strong support for Homestake and the creation of DUSEL. The State has provided funding totalling $46M for the preservation of the site for DUSEL and for the conversion and operation of the Homestake Interim Laboratory. Motivated by the strong educational and outreach potential of Homestake, the State contracted a Conversion Plan by world-recognized mine-engineering contractor to define the process of rehabilitating the facility, establishing the appropriate safety program, and regaining access to the facility. The State of South Dakota has established the South Dakota Science and Technology Authority to oversee the transfer of the Homestake property to the State and the rehabilitation and preservation of the facility. The Homestake Scientific Collaboration and the State of South Dakota's Science and Technology Authority has called for Letters of Interest from scientific, educational and engineering collaborations and institutions that are interested in hosting experiments and uses in the Homestake Interim Facility in advance of the NSF's DUSEL, to define experiments starting as early as 2007. The Homestake Program Advisory Committee has reviewed these Letters and their initial report has been released. Options for

Interim Feed The Future Population Based Assessment of Cambodia

Data.gov (United States)

US Agency for International Development — This is the interim population based survey of Feed the Future in Cambodia for 2015. The data is split into survey modules. Modules A through C includes location...

Safety system status monitoring

International Nuclear Information System (INIS)

Lewis, J.R.; Morgenstern, M.H.; Rideout, T.H.; Cowley, P.J.

1984-03-01

The Pacific Northwest Laboratory has studied the safety aspects of monitoring the preoperational status of safety systems in nuclear power plants. The goals of the study were to assess for the NRC the effectiveness of current monitoring systems and procedures, to develop near-term guidelines for reducing human errors associated with monitoring safety system status, and to recommend a regulatory position on this issue. A review of safety system status monitoring practices indicated that current systems and procedures do not adequately aid control room operators in monitoring safety system status. This is true even of some systems and procedures installed to meet existing regulatory guidelines (Regulatory Guide 1.47). In consequence, this report suggests acceptance criteria for meeting the functional requirements of an adequate system for monitoring safety system status. Also suggested are near-term guidelines that could reduce the likelihood of human errors in specific, high-priority status monitoring tasks. It is recommended that (1) Regulatory Guide 1.47 be revised to address these acceptance criteria, and (2) the revised Regulatory Guide 1.47 be applied to all plants, including those built since the issuance of the original Regulatory Guide

Safety system status monitoring

Energy Technology Data Exchange (ETDEWEB)

Lewis, J.R.; Morgenstern, M.H.; Rideout, T.H.; Cowley, P.J.

1984-03-01

The Pacific Northwest Laboratory has studied the safety aspects of monitoring the preoperational status of safety systems in nuclear power plants. The goals of the study were to assess for the NRC the effectiveness of current monitoring systems and procedures, to develop near-term guidelines for reducing human errors associated with monitoring safety system status, and to recommend a regulatory position on this issue. A review of safety system status monitoring practices indicated that current systems and procedures do not adequately aid control room operators in monitoring safety system status. This is true even of some systems and procedures installed to meet existing regulatory guidelines (Regulatory Guide 1.47). In consequence, this report suggests acceptance criteria for meeting the functional requirements of an adequate system for monitoring safety system status. Also suggested are near-term guidelines that could reduce the likelihood of human errors in specific, high-priority status monitoring tasks. It is recommended that (1) Regulatory Guide 1.47 be revised to address these acceptance criteria, and (2) the revised Regulatory Guide 1.47 be applied to all plants, including those built since the issuance of the original Regulatory Guide.

STANDING CONCERTATION COMMITTEE OCTOBER 1999 ORDINARY MEETING

CERN Document Server

1999-01-01

Original: FrenchThe meeting was mainly devoted to the examination of the items below, to which the Committee had allocated two meetings:Preparation for the meeting of TREF on 19 November 1999The SCC took note of the agenda for that meeting which includes additional information on the long-term care insurance project, a second report on staff recruitment and retention, a status report on the voluntary programmes (especially an assessment of the Progressive Retirement Programme), a proposal for the application of the cost-of-living index for 2000, an addendum to the technical amendments to be made to the Staff Rules and Regulations, a balance sheet of CERN's apprenticeship programmes and a status report with regard to guarantees for the pensions of members of the personnel in the event of the dissolution of the Organization.Long-term care: TREF would be given further information following the comments made when the Management's initial proposals were presented to the Forum at its September meeting. The informat...

Fuel supply shutdown facility interim operational safety requirements

International Nuclear Information System (INIS)

Besser, R.L.; Brehm, J.R.; Benecke, M.W.; Remaize, J.A.

1995-01-01

These Interim Operational Safety Requirements (IOSR) for the Fuel Supply Shutdown (FSS) facility define acceptable conditions, safe boundaries, bases thereof, and management or administrative controls to ensure safe operation. The IOSRs apply to the fuel material storage buildings in various modes (operation, storage, surveillance)

An allowable cladding peak temperature for spent nuclear fuels in interim dry storage

Science.gov (United States)

Cha, Hyun-Jin; Jang, Ki-Nam; Kim, Kyu-Tae

2018-01-01

Allowable cladding peak temperatures for spent fuel cladding integrity in interim dry storage were investigated, considering hydride reorientation and mechanical property degradation behaviors of unirradiated and neutron irradiated Zr-Nb cladding tubes. Cladding tube specimens were heated up to various temperatures and then cooled down under tensile hoop stresses. Cool-down specimens indicate that higher heat-up temperature and larger tensile hoop stress generated larger radial hydride precipitation and smaller tensile strength and plastic hoop strain. Unirradiated specimens generated relatively larger radial hydride precipitation and plastic strain than did neutron irradiated specimens. Assuming a minimum plastic strain requirement of 5% for cladding integrity maintenance in interim dry storage, it is proposed that a cladding peak temperature during the interim dry storage is to keep below 250 °C if cladding tubes are cooled down to room temperature.

ITER management advisory committee meeting

International Nuclear Information System (INIS)

Yoshikawa, M.

2001-01-01

The ITER Management Advisory Committee (MAC) Meeting was held in Vienna on 16 July 2001. It was the last MAC Meeting and the main topics were consideration of the report by the Director on the ITER EDA status, review of the Work Programme, review of the Joint Fund and arrangements for termination and wind-up of the EDA

17 CFR 210.8-03 - Interim financial statements.

Science.gov (United States)

2010-04-01

... 17 Commodity and Securities Exchanges 2 2010-04-01 2010-04-01 false Interim financial statements... AND CONTENT OF AND REQUIREMENTS FOR FINANCIAL STATEMENTS, SECURITIES ACT OF 1933, SECURITIES EXCHANGE... ADVISERS ACT OF 1940, AND ENERGY POLICY AND CONSERVATION ACT OF 1975 Article 8 Financial Statements of...

Options for the interim storage of spent fuel

International Nuclear Information System (INIS)

Kromar, M.; Kurincic, B.

1995-01-01

Different concepts for the interim storage of spent fuel arising from operation of a NPP are discussed. We considered at reactor as well as away from reactor storage options. Included are enhancements of existing storage capabilities and construction of a new wet or dry storage facility. (author)

National NIF Diagnostic Program Interim Management Plan

International Nuclear Information System (INIS)

Warner, B

2002-01-01

The National Ignition Facility (NIF) has the mission of supporting Stockpile Stewardship and Basic Science research in high-energy-density plasmas. To execute those missions, the facility must provide diagnostic instrumentation capable of observing and resolving in time events and radiation emissions characteristic of the plasmas of interest. The diagnostic instrumentation must conform to high standards of operability and reliability within the NIF environment. These exacting standards, together with the facility mission of supporting a diverse user base, has led to the need for a central organization charged with delivering diagnostic capability to the NIF. The National NIF Diagnostics Program (NNDP) has been set up under the aegis of the NIF Director to provide that organization authority and accountability to the wide user community for NIF. The funds necessary to perform the work of developing diagnostics for NIF will be allocated from the National NIF Diagnostics Program to the participating laboratories and organizations. The participating laboratories and organizations will design, build, and commission the diagnostics for NIF. Restricted availability of funding has had an adverse impact, unforeseen at the time of the original decision to projectize NIF Core Diagnostics Systems and Cryogenic Target Handing Systems, on the planning and initiation of these efforts. The purpose of this document is to provide an interim project management plan describing the organizational structure and management processes currently in place for NIF Core Diagnostics Systems. Preparation of a Program Execution Plan for NIF Core Diagnostics Systems has been initiated and a current draft is provided as Attachment 1 to this document. The National NIF Diagnostics Program Interim Management Plan provides a summary of primary design criteria and functional requirements, current organizational structure, tracking and reporting procedures, and current planning estimates of project scope

Glass packages in interim storage

International Nuclear Information System (INIS)

Jacquet-Francillon, N.

1994-10-01

This report summarize the current state of knowledge concerning the behavior of type C waste packages consisting of vitrified high-level solutions produced by reprocessing spent fuel. The composition and the physical and chemical properties of the feed solutions are reviewed, and the vitrification process is described. Sodium alumino-borosilicate glass compositions are generally employed - the glass used at la Hague for LWR fuel solutions, for example, contains 45 % SiO 2 . The major physical, chemical, mechanical and thermal properties of the glass are reviewed. In order to allow their thermal power to diminish, the 3630 glass packages produced (as of January 1993) in the vitrification facilities at Marcoule and La Hague are placed in interim storage for several decades. The actual interim storage period has not been defined, as it is closely related to the concept and organization selected for the final destination of the packages: a geological repository. The glass behavior under irradiation is described. Considerable basic and applied research has been conducted to assess the aqueous leaching behavior of nuclear containment glass. The effects of various repository parameters (temperature, flow rate, nature of the environmental materials) have been investigated. The experimental findings have been used to specify a model describing the kinetics of aqueous corrosion of the glass. More generally all the ''source term'' models developed in France by the CEA or by ANDRA are summarized. (author). 152 refs., 33 figs

Replacement of a hopeless maxillary central incisor: a technique for the fabrication of an immediate implant-supported interim restoration.

Science.gov (United States)

Graiff, Lorenzo; Vigolo, Paolo

2012-04-01

Placement of a dental implant and an interim restoration in the esthetic zone immediately following tooth extraction is now a common procedure. However, in such clinical situations, the fabrication of an appropriate interim restoration may be challenging. The aim of this article is to present a technique for modifying the extracted tooth so it can be used as an implant-supported interim restoration.

78 FR 60331 - Sunshine Act Meeting

Science.gov (United States)

2013-10-01

..., October 7, 14, 21, 28, November 4, 2013. PLACE: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. Week of September 30, 2013 There are no meetings scheduled..., 301-415-1711). This meeting will be webcast live at the Web address-- http://www.nrc.gov/ . Friday...

78 FR 51234 - Sunshine Act Meetings

Science.gov (United States)

2013-08-20

...: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. Week of... (Closed--Ex. 2 and 6). Tuesday, August 27, 2013 9:00 a.m. Briefing on NRC's Construction Activities (Public Meeting); (Contact: Michelle Hayes, 301-415-8375). This meeting will be webcast live at the Web...

78 FR 67201 - Sunshine Act Meeting

Science.gov (United States)

2013-11-08

... LEGAL SERVICES CORPORATION Sunshine Act Meeting DATE AND TIME: The Legal Services Corporation's... disrupting the meeting, please refrain from placing the call on hold if doing so will trigger recorded music or other sound. From time to time, the presiding Chair may solicit comments from the public. STATUS...

Engineering report for interim solids removal modifications of the Steam Plant Wastewater Treatment Facility

International Nuclear Information System (INIS)

1995-04-01

The Steam Plant Wastewater Treatment Facility (SPWTF) treats wastewater from the Y-12 Plant coal yard, steam plant, and water demineralizer facility. The facility is required to comply with National Pollutant Discharge Elimination System (NPDES) standards prior to discharge to East Fork Poplar Creek (EFPC). The existing facility was designed to meet Best Available Technology (BAT) standards and has been in operation since 1988. The SPWTF has had intermittent violations of the NPDES permit primarily due to difficulties in complying with the limit for total iron of 1.0 ppM. A FY-1997 Line Item project, SPWTF Upgrades, is planned to improve the capabilities of the SPWTF to eliminate non-compliances with the permit limits. The intent of the Interim Solids Removal Modification project is to improve the SPWTF effluent quality and to provide pilot treatment data to assist in the design and implementation of the SPWTF Upgrades Line Item Project

Fusion Breeder Program interim report

International Nuclear Information System (INIS)

Moir, R.; Lee, J.D.; Neef, W.

1982-01-01

This interim report for the FY82 Fusion Breeder Program covers work performed during the scoping phase of the study, December, 1981-February 1982. The goals for the FY82 study are the identification and development of a reference blanket concept using the fission suppression concept and the definition of a development plan to further the fusion breeder application. The context of the study is the tandem mirror reactor, but emphasis is placed upon blanket engineering. A tokamak driver and blanket concept will be selected and studied in more detail during FY83

An interim report of the Subcommittee on Radioactive Waste Countermeasures: measures for radioactive waste treatment and disposal

International Nuclear Information System (INIS)

1984-01-01

The Subcommittee on Radioactive Waste Countermeasures has studied on the measures for land disposal of low-level radioactive wastes and ultra-low-level radioactive wastes and the measures for treatment and disposal of high-level radioactive wastes and transuranium wastes. The results of studies so far are presented as an interim report. In disposal of low-level radioactive wastes, the land disposal is being required increasingly. The measures according to the levels of radioactivity are necessary. For the ultra-low-level radioactive wastes, their occurrence in large quantities is expected along with reactor decommissioning. In disposal of the high-level radioactive wastes, the present status is a transition toward the practical stages. Transuranium wastes should increase in their arising in the future. (Mori, K.)

Spent fuel management: Current status and prospects 1997. Proceedings of a regular advisory group meeting

International Nuclear Information System (INIS)

1998-03-01

Spent fuel management has always been one of the important stages in the nuclear fuel cycle and it is still most vital problems common to all countries with nuclear reactors. It begins with the discharge of spent fuel from a power or a research reactor and ends with its ultimate disposition. Two options exist - an open, once-through cycle with direct disposal of the spent fuel and a closed cycle with reprocessing of the spent fuel, recycling of reprocessed plutonium and uranium in new mixed oxide fuels and disposal of the radioactive waste. Continuous attention is being given by the IAEA to the collection, analysis and exchange of information on spent fuel management. Its role in this area is to provide a forum for exchanging information and to co-ordinate and to encourage closer co-operation among Member States in certain research and development activities that are of common interest. Spent fuel management is recognized as a high priority IAEA activity. The Regular Advisory Group on Spent Fuel Management was established in 1982. The objective of the Regular Advisory Group is to serve as a means of exchanging information on the current status and progress of national programmes on spent fuel management and to provide advice to the IAEA. The results of the last Regular Advisory Group meeting (9-12 September 1997) are reflected in this report. It gives an overview of the status of spent fuel management programmes in a number of countries, a description of the current status and prospects of activities in this field and recommendations of the participants

78 FR 28258 - Sunshine Act Meetings

Science.gov (United States)

2013-05-14

...: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. Week of...) (Public Meeting) (Contact: Kristin Davis, 301-287- 0707). This meeting will be webcast live at the Web... Security Issues (Closed--Ex. 1). Wednesday, May 29, 2013 9:00 a.m. Briefing on Results of the Agency Action...

Effectiveness of interim remedial actions at the Niagara Falls Storage Site

International Nuclear Information System (INIS)

Devgun, J.S.; Beskid, N.J.; Seay, W.M.; McNamee, E.

1990-01-01

There are 190,000 m 3 of contaminated soils, wastes, and residues stored at the Niagara Falls Storage Site (NFSS). The residues have a volume of 18,000 m 3 and contain about 1,930 Ci of 226 Ra, which accounts for most of the radioactivity. Since 1980, actions have been taken to minimize potential radiological risks and prevent radionuclide migration. Interim actions included capping vents, sealing pipes, relocating the perimeter fence (to limit radon risk), transferring and consolidating wastes, upgrading storage buildings, constructing a clay cutoff wall (to limit potential ground-water transport of contaminants), treating and releasing contaminated water, using a synthetic liner, and using an interim clay cap. An interim waste containment facility was completed in 1986. Environmental monitoring showed a decrease in radon concentrations and in external gamma radiation from 1982 to 1986; levels have been stable since 1986. Uranium and radium concentrations in surface water have decreased; very low concentrations have been detected in stream sediments, and concentrations in ground water have remained stable. Recent monitoring showed that NFSS is in compliance with the U.S. Department of Energy's (DOE's) radiation protection standards

ITER management advisory committee meeting

International Nuclear Information System (INIS)

Yoshikawa, M.

2001-01-01

The ITER Management Advisory Committee (MAC) Meeting was held on 23 February in Garching, Germany. The main topics were: the consideration of the report by the Director on the ITER EDA Status, the review of the Work Programme, the review of the Joint Fund, the review of a schedule of ITER meetings, and the arrangements for termination and wind-up of the EDA

German Approach for the Transport of Spent Fuel Packages after Interim Storage

International Nuclear Information System (INIS)

Wille, Frank; Wolff, Dietmar; Droste, Bernhard; Voelzke, Holger

2014-01-01

In Germany the concept of dry interim storage of spent nuclear fuel in dual purpose metal casks is implemented, currently for periods of up to 40 years. The casks being used have an approved package design in accordance with the international transport regulations. The license for dry storage is granted on the German Atomic Energy Act with respect to the recently (in 2012) revised 'Guidelines for dry cask storage of spent nuclear fuel and heat-generating waste' by the German Waste management Commission (ESK) which are very similar to the former RSK (reactor safety commission) guidelines. For transport on public routes between or after long term interim storage periods, it has to be ensured that the transport and storage casks fulfil the specifications of the transport approval or other sufficient properties which satisfy the proofs for the compliance of the safety objectives at that time. In recent years the validation period of transport approval certificates for manufactured, loaded and stored packages were discussed among authorities and applicants. A case dependent system of 3, 5 and 10 years was established. There are consequences for the safety cases in the Package Design Safety Report including evaluation of long term behavior of components and specific operating procedures of the package. Present research and knowledge concerning the long term behavior of transport and storage cask components have to be consulted as well as experiences from interim cask storage operations. Challenges in the safety assessment are e.g. the behavior of aged metal and elastomeric seals under IAEA test conditions to ensure that the results of drop tests can be transferred to the compliance of the safety objectives at the time of transport after the interim storage period (aged package). Assessment methods for the material compatibility, the behavior of fuel assemblies and the aging behavior of shielding parts are issues as well. This paper describes the state

Periodic Safety Review in Interim Storage Facilities - Current Regulation and Experiences in Germany

International Nuclear Information System (INIS)

Neles, Julia Mareike; Schmidt, Gerhard

2014-01-01

Periodic safety reviews in nuclear power plants in Germany have been performed since the end of the 1980's as an indirect follow-up of the accident in Chernobyl and, in the meantime, are formally required by law. During this process the guidelines governing this review were developed in stages and reached their final form in 1996. Interim storage facilities and other nuclear facilities at that time were not included, so the guidelines were solely focused on the specific safety issues of nuclear power plants. Following IAEA's recommendations, the Western European Nuclear Regulator Association (WENRA) introduced PSRs in its safety reference levels for storage facilities (current version in WGWD report 2.1 as of Feb 2011: SRLs 59 - 61). Based on these formulations, Germany improved its regulation in 2010 with a recommendation of the Nuclear Waste Management Commission (Entsorgungskommission, ESK), an expert advisory commission for the federal regulatory body BMU. The ESK formulated these detailed requirements in the 'ESK recommendation for guides to the performance of periodic safety reviews for interim storage facilities for irradiated fuel elements and heat-generating radioactive waste'. Before finalization of the guideline a test phase was introduced, aimed to test the new regulation in practice and to later include the lessons learned in the final formulation of the guideline. The two-year test phase started in October 2011 in which the performance of a PSR will be tested at two selected interim storage facilities. Currently these recommendations are discussed with interested/concerned institutions. The results of the test phase shall be considered for improvements of the draft and during the final preparation of guidelines. Currently the PSR for the first ISF is in an advanced stage, the second facility just started the process. Preliminary conclusions from the test phase show that the implementation of the draft guideline requires interpretation. The aim of a

1987 Federal interim storage fee study: A technical and economic analysis

International Nuclear Information System (INIS)

1987-09-01

This document is the latest in a series of reports that are published annually by Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE). This information in the report, which was prepared by E.R. Johnson Associates under subcontract to PNL, will be used by the DOE to establish a payment schedule for interim storage of spent nuclear fuel under the Federal Interim Storage (FIS) Program, which was mandated by the Nuclear Waste Policy Act of 1982. The information in this report will be used to establish the schedule of charges for FIS services for the year commencing January 1, 1988. 13 tabs

1987 Federal interim storage fee study: A technical and economic analysis

Energy Technology Data Exchange (ETDEWEB)

1987-09-01

This document is the latest in a series of reports that are published annually by Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE). This information in the report, which was prepared by E.R. Johnson Associates under subcontract to PNL, will be used by the DOE to establish a payment schedule for interim storage of spent nuclear fuel under the Federal Interim Storage (FIS) Program, which was mandated by the Nuclear Waste Policy Act of 1982. The information in this report will be used to establish the schedule of charges for FIS services for the year commencing January 1, 1988. 13 tabs.

105-C Reactor interim safe storage project technology integration plan

International Nuclear Information System (INIS)

Pulsford, S.K.

1997-01-01

The 105-C Reactor Interim Safe Storage Project Technology Integration Plan involves the decontamination, dismantlement, and interim safe storage of a surplus production reactor. A major goal is to identify and demonstrate new and innovative D and D technologies that will reduce costs, shorten schedules, enhance safety, and have the potential for general use across the RL complex. Innovative technologies are to be demonstrated in the following areas: Characterization; Decontamination; Waste Disposition; Dismantlement, Segmentation, and Demolition; Facility Stabilization; and Health and Safety. The evaluation and ranking of innovative technologies has been completed. Demonstrations will be selected from the ranked technologies according to priority. The contractor team members will review and evaluate the demonstration performances and make final recommendations to DOE

Diesel Emission Control -- Sulfur Effects (DECSE) Program; Phase I Interim Data Report No. 1

Energy Technology Data Exchange (ETDEWEB)

DOE; ORNL; NREL; EMA; MECA

1999-08-15

The Diesel Emission Control-Sulfur Effects (DECSE) is a joint government/industry program to determine the impact of diesel fuel sulfur levels on emission control systems whose use could lower emissions of nitrogen oxides (NO{sub x}) and particulate matter (PM) from on-highway trucks in the 2002--2004 model years. Phase 1 of the program was developed with the following objectives in mind: (1) evaluate the effects of varying the level of sulfur content in the fuel on the emission reduction performance of four emission control technologies; and (2) measure and compare the effects of up to 250 hours of aging on selected devices for multiple levels of fuel sulfur content. This interim data report summarizes results as of August, 1999, on the status of the test programs being conducted on three technologies: lean-NO{sub x} catalysts, diesel particulate filters and diesel oxidation catalysts.

Single-Shell Tank (SST) Interim Stabilization Project Plan

International Nuclear Information System (INIS)

VLADIMIROFF, D.T.; BOYLES, V.C.

2000-01-01

This project plan establishes the management framework for the conduct of the CHG Single-Shell Tank Interim Stabilization completion program. Specifically, this plan defines the mission needs and requirements; technical objectives and approach; organization structure, roles, responsibilities, and interfaces; and operational methods. This plan serves as the project executional baseline

Interim report on long range plan for nuclear physics

International Nuclear Information System (INIS)

Anon.

1995-01-01

The interim report on the updated NSAC Long Range Plan for Nuclear Physics will be presented to the community for discussion and comment before submission to the funding agencies. The presentation will be coordinated by E. Moniz chair of NSAC

78 FR 19757 - Sunshine Act Meetings

Science.gov (United States)

2013-04-02

...: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland STATUS: Public and Closed Week of... Quash Subpoena Filed by the Shaw Group, Inc. (Tentative) This meeting will be webcast live at the Web... meeting will be webcast live at the Web address--www.nrc.gov Week of April 8, 2013--Tentative There are no...

78 FR 23960 - Sunshine Act Meetings

Science.gov (United States)

2013-04-23

...' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. Week of April 22, 2013... Meeting) (Contact: Brett Rini, 301-251-7615). This meeting will be webcast live at the Web address--www.nrc.gov. 2:30 p.m. Discussion of Management and Personnel Issues (Closed--Ex. 2 and 6). Tuesday April...

78 FR 962 - Sunshine Act Meetings

Science.gov (United States)

2013-01-07

...: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. Week of...: Michael Hay, 817-200-1527) This meeting will be webcast live at the Web address--www.nrc.gov Wednesday..., 2012) (Tentative) This meeting will be webcast live at the Web address--www.nrc.gov 9:00 a.m. Briefing...

78 FR 21171 - Sunshine Act Meetings

Science.gov (United States)

2013-04-09

...: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. Week of... Meeting) (Contact: Brett Rini, 301-251-7615) This meeting will be webcast live at the Web address--www.nrc.gov. 2:30 p.m. Discussion of Management and Personnel Issues (Closed-- Ex. 2 and 6) Tuesday, April 23...

78 FR 18376 - Sunshine Act Meetings

Science.gov (United States)

2013-03-26

...: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. Week of...-0223). This meeting will be webcast live at the Web address--www.nrc.gov. Week of April 8, 2013...) (Contact: Brett Rini, 301-251-7615). This meeting will be webcast live at the Web address--www.nrc.gov. 2...

75 FR 64748 - Sunshine Act Meeting

Science.gov (United States)

2010-10-20

... NATIONAL CREDIT UNION ADMINISTRATION Sunshine Act Meeting Notice of a Matter To Be Added to the Agenda for Consideration at an Agency Meeting TIME AND DATE: 10 a.m., Thursday, October 21, 2010. PLACE: Board Room, 7th Floor, Room 7047, 1775 Duke Street, Alexandria, VA 22314-3428. STATUS: Open. Matters To...

Finding of no significant impact: Interim storage of enriched uranium above the maximum historical level at the Y-12 Plant Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1995-01-01

The US Department of Energy (DOE) has prepared an Environmental Assessment (EA) for the Proposed Interim Storage of Enriched Uranium Above the Maximum Historical Storage Level at the Y-12 Plant, Oak Ridge, Tennessee (DOE/EA-0929, September, 1994). The EA evaluates the environmental effects of transportation, prestorage processing, and interim storage of bounding quantities of enriched uranium at the Y-12 Plant over a ten-year period. The State of Tennessee and the public participated in public meetings and workshops which were held after a predecisional draft EA was released in February 1994, and after the revised pre-approval EA was issued in September 1994. Comments provided by the State and public have been carefully considered by the Department. As a result of this public process, the Department has determined that the Y-12 Plant-would store no more than 500 metric tons of highly enriched uranium (HEU) and no more than 6 metric tons of low enriched uranium (LEU). The bounding storage quantities analyzed in the pre-approval EA are 500 metric tons of HEU and 7,105.9 metric tons of LEU. Based on-the analyses in the EA, as revised by the attachment to the Finding of No Significant Impact (FONSI), DOE has determined that interim storage of 500 metric tons of HEU and 6 metric tons of LEU at the Y-12 Plant does not constitute a major Federal action significantly affecting the quality of the human environment, within the meaning of the National Environmental Policy Act (NEPA) of 1969. Therefore, an Environmental Impact Statement (EIS) is not required and the Department is issuing this FONSI

DEMONSTRATION OF THE DOE INTERIM ENERGY CONSERVATION STANDARDS FOR NEW FEDERAL RESIDENTIAL BUILDINGS

Energy Technology Data Exchange (ETDEWEB)

Lee, A. D.; Baechler, H. C.; Di Massa, F. V.; Lucas, R. G.; Shankle, D. L.

1992-01-01

system to develop a design which would comply with the standards. PNL conducted extensive interviews with the federal agencies and design contractors to determine what impacts the standards would have on the existing agency procurement process as well as on designers. Overall, PNL found that the interim standards met the basic intent of the law. Specific actions were identified, however, that DOE could take to improve the standards and encourage the agencies to implement them. Agency personnel found the minimum efficiency levels established by the standards to be lower than expected, and lower than their existing requirements. Generally, this was because the standards factor in fuel costs, as well as energy savings due to various conservation measures such as insulation, when they determine the minimum efficiency levels required. The demonstration showed that federal agencies often pay low prices for heating fuel and electricity; these lower costs "tipped the scales," allowing designers to meet the efficiency target with designs that were relatively inefficient. It appeared, however, that the low prices paid by agencies directly to suppliers did not capture the agencies' full costs of providing energy, such as the costs of distribution and storage. Agency personnel expressed some concern about the standards' ability to incorporate new energy-efficient technologies and renewable resource technologies like solar heating systems. An alternative compliance procedure was developed to incorporate new technologies; however, demonstration participants said the procedure was not well documented and was difficult and time consuming to use. Despite these concerns, most agency personnel thought that the standards would fit into current procurement procedures with no big changes or cost increases. Many said use of the standards would decrease the time and effort they now spend to establish energy-efficiency requirements and to confirm that proposed designs comply. Personnel praised

Impact of socio-economic status in meeting the needs of people with mental illness; human rights perspective.

Science.gov (United States)

Vijayalakshmi, Poreddi; Ramachandra; Reddemma, Konduru; Math, Suresh Bada

2014-04-01

The present descriptive study investigated the impact of socio-economic status in meeting the human rights needs among randomly selected recovered psychiatric patients (n = 100) at a tertiary care center. Data was collected through face to face interview, using structured Needs Assessment Questionnaire. The findings revealed that the participants from below poverty line were deprived of physical needs such as 'electricity facilities' (χ (2) = 6.821, p physical appearance (χ (2) = 8.337, p employment, disability pension, free housing, free treatment and free transportation service for people with mental illness to attend hospital or rehabilitation centres.

Federal Interim Storage program

International Nuclear Information System (INIS)

Johnson, E.R.; McBride, J.A.

1984-01-01

The DOE has developed a program for providing Federal Interim Storage servies for spent nuclear fuel which complies with the requirements of the Nuclear Waste Policy Act of 1982. Although very little constructive activity in providing storage facilities can be undertaken by DOE until fuel has been certified by NRC as eligible for FIS, DOE planning and background information is such as to provide reasonable assurance that its obligations can be fulfilled when the required certifications have been issued. A fee structure providing fuel recovery of all costs associated with the FIS program, as required by the Act, has been developed. It provides for an equitable distribution of costs among users, based on the quantity of fuel requiring storage

Tank Farm Interim Surface Barrier Materials And Runoff Alternatives Study

International Nuclear Information System (INIS)

Holm, M.J.

2009-01-01

This report identifies candidate materials and concepts for interim surface barriers in the single-shell tank farms. An analysis of these materials for application to the TY tank farm is also provided.

Report on the separation and refining technology sub-committee meetings in fiscal 1987; 1987 nendo bunri seisei gijutsu bukai hokokusho

Energy Technology Data Exchange (ETDEWEB)

NONE

1988-03-01

The separation and refining technology sub-committee has held two meetings in this fiscal year. The first sub-committee meeting (October 9, 1987) was held for the major agenda of the research and development of the basic studies; as the summary of the achievements in fiscal 1986, the up-grading by fractions and of the total fraction collectively, up-grading of kerosene and light oil fractions, up-grading of medium to heavy fractions; and as the study plans for fiscal 1987, the up-grading of coal liquefied oil, a technology to separate hetero compounds, development of their applications, and the reports and deliberations thereon. The major agenda of the second sub-committee meeting (February 10, 1988) were the interim report on the achievements in research of up-grading the coal liquefied oil in fiscal 1987, the interim reports on research achievements in the technology to separate hetero compounds and development of its applications, and the reports and deliberations thereon. The conventional up-grading sub-committee was dissolved in fiscal 1987 to form a new organization, whereas the 'separation and refining sub-committee' was founded newly. With respect to the up-grading matters, reports were given on the achievements thereon as a result of using a micro reaction device and a bench reaction device as in the past, and on the achievements in the application development. In addition, on the hetero related matters, directionality of the survey and the result therefrom were reported. (NEDO)

Standing Concertation Committee: Ordinary Meetings on 30 March, 15 & 21 April 2005

CERN Multimedia

2005-01-01

Original : english These meetings were devoted to the main topics summarised below. 1. Follow-up from the meetings of the Finance Committee and Council in March 2005 The Chairman reported on the outcome of these meetings. He indicated, in particular, that the Management would submit a document on the internal taxation of salaries to the Finance Committee and Council in June and that the Council had decided to set up a working group on issues regarding the Pension Fund. The Staff Association stated that it would formally request clarification of the mandate of this working group. The Chairman also announced the nomination of Enrico Chiaveri as Head of HR Department, with effect from 1 April 2005, and expressed the Management's thanks to Werner Zapf for the valuable services that he had rendered as ad interim Head of HR Department. 2. New contract policy The SCC examined draft internal documents on this topic at its sessions on 30 March, and 15 April. The Committee took note that the Staff Association wo...

Development of Accident Scenario for Interim Spent Fuel Storage Facility Based on Fukushima Accident

Energy Technology Data Exchange (ETDEWEB)

Lee, Dongjin; Choi, Kwangsoon; Yoon, Hyungjoon; Park, Jungsu [KEPCO-E and C, Yongin (Korea, Republic of)

2014-05-15

700 MTU of spent nuclear fuel is discharged from nuclear fleet every year and spent fuel storage is currently 70.9% full. The on-site wet type spent fuel storage pool of each NPP(nuclear power plants) in Korea will shortly exceed its storage limit. Backdrop, the Korean government has rolled out a plan to construct an interim spent fuel storage facility by 2024. However, the type of interim spent fuel storage facility has not been decided yet in detail. The Fukushima accident has resulted in more stringent requirements for nuclear facilities in case of beyond design basis accidents. Therefore, there has been growing demand for developing scenario on interim storage facility to prepare for beyond design basis accidents and conducting dose assessment based on the scenario to verify the safety of each type of storage.

Ch-Ch-Ch-changes: how action phase functional leadership, team human capital, and interim vs. permanent leader status impact post-transition team performance

OpenAIRE

Maynard, M. Travis; Resick, Christian J.; Cunningham, Quinn W.; DiRenzo, Marco S.

2017-01-01

The article of record as published may be found at http://dx.doi.org/10.1007/s10869-016-9482-5 This study addresses the following: (1) does a team leader change along with the quality of the team’s human capital affect post-change team performance?; (2) is functional leadership of the team’s human capital a driver of post-change team performance?; and (3) should interim vs. permanent leaders manage the team’s human capital differently? We analyzed archival data from Major League Baseba...

Ad interim legal remedy in case of large projects

International Nuclear Information System (INIS)

Limberger, J.

1985-01-01

Action for ad interim judicial relief in response to large projects approved of by the authorities very frequently take several years until a decision is taken by the court. Experience has shown that this applies in particular to large projects such as the construction of nuclear power plants, large-size industrial plants, or airports. It has become regular practice by the authorities concerned to issue an order for immediate execution upon the plan approving decision and granting of licence for said projects, in accordance with section 80, sub-section (2), no.4 of the VwGO. The problems thus created with regard to interim legal remedy sought by the parties concerned are of great significance. The book in hand discusses the question as to whether the practice of the administrative authorities and the courts satisfies the requirements embodied in the law, to provide for efficient legal protection. (orig./HSCH) [de

49 CFR 37.169 - Interim requirements for over-the-road bus service operated by private entities.

Science.gov (United States)

2010-10-01

... of such devices, shall be permitted in the passenger compartment. When the bus is at rest at a stop... 49 Transportation 1 2010-10-01 2010-10-01 false Interim requirements for over-the-road bus service... Interim requirements for over-the-road bus service operated by private entities. (a) Private entities...

Sacramento Municipal Utility district's interim onsite storage building for low level radioactive waste

International Nuclear Information System (INIS)

Gillis, E.

1986-01-01

In order to meet current and anticipated needs for the low level radwaste management program at the Rancho Seco Nuclear Generating Station, the Sacramento Municipal Utility District has a design and construction program underway which will provide an onsite interim storage facility that can be expanded in two and one-half year increments. The design approach utilized allows capital investment to be minimized and still provides radwaste management flexibility in anticipation of delays in resolution of the nationwide long term radwaste disposal situation. The facility provides storage and material accountability for all low level radwastes generated by the plant. Wastes are segregated by radioactivity level and are stored in two separate storage areas located within one facility. Lower activity wastes are stored in a lightly shielded structure and handled by lift trucks, while the higher activity wastes are stored in a highly shielded structure and handled remotely by manual bridge crane. The layout of the structure provides for economy of operation and minimizes personnel radiation exposure. Design philosophy and criteria, building layout and systems, estimated costs and construction schedule are discussed

Acceptable TRU packaging for interim storage and/or terminal isolation: FY-1977 final report

International Nuclear Information System (INIS)

Doty, J.W.; Peterson, J.B.

1978-01-01

A program was conducted for the definition and demonstration of acceptable waste packages for defense transuranic waste for interim storage and terminal isolation. During FY-1977, a Contractor Questionnaire was used to gather pertinent data and to assess contractor concerns. This information was integrated into basic application data in the form of a checklist. Conceptual Container Design Specifications were developed by analyzing and evaluating the application data against Federal Regulations and interim/terminal storage constraints

75 FR 19465 - Sunshine Act; Meeting Notice

Science.gov (United States)

2010-04-14

... news media following the Board meeting. STATUS: Open. Agenda Old Business Approval of minutes of February 11, 2010, Board Meeting. New Business 1. Chairman's Report. 2. President's Report. 3. Report of..., and Ethics Committee. A. Designation of Corporate Secretary 6. Report of the Community Relations and...

75 FR 7591 - Guidance on Recommended Interim Preliminary Remediation Goals for Dioxin in Soil at CERCLA and...

Science.gov (United States)

2010-02-22

... ENVIRONMENTAL PROTECTION AGENCY [EPA-HQ-SFUND-2009-0907; FRL-9114-6] RIN 2050-ZA05 Guidance on Recommended Interim Preliminary Remediation Goals for Dioxin in Soil at CERCLA and RCRA Sites; Extension of... Interim Preliminary Remediation Goals for Dioxin in Soil at Comprehensive Environmental Response...

Individual shareholders’ understanding of the content of interim reports of South African listed retail companies

Directory of Open Access Journals (Sweden)

Johan GI Oberholster

2015-05-01

Full Text Available A number of studies conducted, and reports published, by international and local accounting bodies have found that the proliferation of disclosures in financial reports has hampered users’ understanding of these reports. The reports by accounting bodies also indicate that these users prefer more concise financial reports. These findings, in conjunction with a dearth of recent questionnaire-based research on whether individual shareholders understand the content of financial reports, resulted in this study on whether individual shareholders understand the content of interim reports. The study provides empirical proof that a sound knowledge of business, accounting and economic matters is a prerequisite for understanding interim reports in the case of individual shareholders. The results of the study indicate that individual shareholders have a limited understanding of the content of interim reports as a whole, and that a good knowledge of business and economic matters and of accounting results in an improved understanding of the content of interim reports. In particular, specialisation in accounting in undergraduate and postgraduate degrees, professional qualifications, and work experience in the financial field improve the understanding of individual shareholders.

Fall meeting 2004: information conference on engines. Final and interim reports of the research centres; Herbsttagung 2004: Informationstagung Motoren. Abschluss- und Zwischenberichte der Forschungsstellen

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-07-01

The Proceedings (volume R526, 2004) of the Information Conference on Engines which has been held on the 23rd September 2004 in Pforzheim/Germany, contains ten final and interim reports. The subjects of the contributions presented were as follow: particulate filter with NOx storage coating; cause study on damage-relevant knocking combustion; spray wall interaction; binaural transfer path analysis synthesis; acoustical optimized sealing-systems on engine acoustics; working process caused gas exchange noise; knowledge based diesel engine optimization; frontal press fit assemblies; case hardening and autofrettage; oil condition sensor (orig.)

Strategic Review of Medical Training and Career Structure Interim Report

OpenAIRE

Department of Health (Ireland)

2013-01-01

Click here to download Strategic Review of Medical Training and Career Structure Interim Report PDF 44kb Click here to download Strategic Review of Medical Training and Career Structure Terms of Reference PDF 59KB

75 FR 43329 - Interim Final Rules for Group Health Plans and Health Insurance Issuers Relating to Internal...

Science.gov (United States)

2010-07-23

... 45 CFR Part 147 Interim Final Rules for Group Health Plans and Health Insurance Issuers Relating to... Interim Final Rules for Group Health Plans and Health Insurance Issuers Relating to Internal Claims and... of Labor; Office of Consumer Information and Insurance Oversight, Department of Health and Human...

78 FR 4476 - Sunshine Act; Meeting Notice

Science.gov (United States)

2013-01-22

...: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. Week of... live at the Web address--www.nrc.gov. 9:00 a.m. Briefing on Public Participation in NRC Regulatory Decision- Making (Public Meeting) (Contact: Lance Rakovan, 301-415-2589). This meeting will be webcast live...

76 FR 77574 - Sunshine Act Meeting Notice

Science.gov (United States)

2011-12-13

..., 16, 2012. Place: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. Status: Public and closed. Week of December 12, 2011 Tuesday, December 13, 2011 9 a.m. Briefing on NFPA 805 Fire Protection (Public Meeting), (Contact: Alex Klein, (301) 415-2822.) This meeting will be webcast live at the...

78 FR 79021 - Sunshine Act Meeting Notice

Science.gov (United States)

2013-12-27

... 30, 2013, January 6, 13, 20, 27, February 3, 2014. PLACE: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. Week of December 30, 2013 There are no... to Dry Casks (Public Meeting) (Contact: Kevin Witt, 301-415-2145). This meeting will be webcast live...

78 FR 52990 - Sunshine Act Meetings Notice

Science.gov (United States)

2013-08-27

...: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. Week of August 26, 2013 Monday August 26, 2013 2:00 p.m. Discussion of Management and Personnel Issues (Closed... Meeting) (Contact: Michelle Hayes, 301-415-8375). This meeting will be webcast live at the Web address...

78 FR 38409 - Sunshine Act Meeting; Notice

Science.gov (United States)

2013-06-26

... LEGAL SERVICES CORPORATION Sunshine Act Meeting; Notice DATE AND TIME: The Legal Services... disrupting the meeting, please refrain from placing the call on hold if doing so will trigger recorded music or other sound. From time to time, the presiding Chair may solicit comments from the public. STATUS...

75 FR 32538 - Sunshine Act Meeting Notice

Science.gov (United States)

2010-06-08

... news media following the Board meeting. Status: Open Agenda Old Business Approval of minutes of April 16, 2010, Board Meeting New Business 1. Chairman's Remarks 2. President's Report 3. Report of the..., Governance, and Ethics Committee A. Board governance update 6. Report of the Community Relations and Energy...

77 FR 58416 - Regular Board of Directors Meeting; Sunshine Act

Science.gov (United States)

2012-09-20

..., DC 20005. STATUS: Open. CONTACT PERSON FOR MORE INFORMATION: Erica Hall, Assistant Corporate... Annual Board of Directors Meeting Minutes IV. Approval of the Corporate Administration Committee Meeting Minutes V. Approval of the Finance, Budget & Program Committee Meeting Minutes VI. Approval of the Audit...

76 FR 74831 - Regular Board of Directors Meeting; Sunshine Act

Science.gov (United States)

2011-12-01

..., DC 20005. STATUS: Open. CONTACT PERSON FOR MORE INFORMATION: Erica Hall, Assistant Corporate... the Regular Board of Directors Meeting Minutes IV. Approval of the Finance, Budget and Program Committee Meeting Minutes V. Approval of the Corporate Administrative Committee Meeting Minutes VI. Approval...

77 FR 15142 - Regular Board of Directors Meeting; Sunshine Act

Science.gov (United States)

2012-03-14

... 20005. STATUS: Open. CONTACT PERSON: Erica Hall, Assistant Corporate Secretary, (202) 220- 2376; ehall... Directors Meeting Minutes IV. Approval of the Audit Committee Meeting Minutes V. Approval of the Finance, Budget and Program Committee Meeting Minutes VI. Approval of the Corporate Administration Committee...

Report on the long-term interim storage of spent fuels and vitrified wastes; Gutachten zur Langzeitzwischenlagerung abgebrannter Brennelemente und verglaster Abfaelle

Energy Technology Data Exchange (ETDEWEB)

NONE

2015-12-03

Long-term interim storage for several hundred years is an option on the management of high-level radioactive wastes. The decision on final disposal is postponed. Worldwide the long-term interim storage is not part of the disposal concept - a geologic final repository is the ultimate aim. Using today's technology the interim storage over several hundred years is supposed to be uncritical. Aging management is the most important challenge - the renewal of the facilities would have to be expected. Possible social change and their impact on the interim storage problem has not been considered.

Important points not mentioned in 'interim report' of nuclear regulation authority

International Nuclear Information System (INIS)

Sato, Satoshi

2014-01-01

The Nuclear Regulation Authority (NRA) published the investigation and examination report on the unexplained issues raised by the National Diet Investigation Commission; 'Analysis of the TEPCO Fukushima Daiichi NPS Accident-Interim Report' in October 2014. The NRA had analyzed seven unexplained issues raised in the National Diet Investigation Commission report, and compiled the results. The author insisted the report should include related views and lessons learned and not just explain investigated and examined phenomena in order to contribute to ensuring nuclear safety in the world. As an example, the author selected the fifth of seven issues; 'operating status of the Isolation Condenser of Unit 1 (IC)'. The report concluded 'the AC-driven valve was closed since the AC power supply kept working even after DC power supply for the IC rupture detection circuit was lost. The isolation valves (2A and 2B) outside the PCV were closed, but isolation valves (1B and 4B) of the IC (system 'B') in the PCV remained open. However, the operating status (open/close) of isolation valves (1A and 4A) of the IC (system 'A') in the PCV is not clear. It is therefore necessary to continue analyses of this issue.' As related important points not mentioned in the report, the author described five points; (1) timing of functional losses of IC system, (2) obsolete aspect of equipment arrangement design (system separation), (3) single failure vulnerability, (4) rolling out issue of IC system to RCIC system (horizontal deployment) and (5) lessons learned from risk-informed 'black swan event'. (T. Tanaka)

76 FR 29727 - Sunshine Act Meeting-Change of Time

Science.gov (United States)

2011-05-23

... meetings on the following dates: May 20, 2011; May 27, 2011.\\1\\ \\1\\ These meetings were announced... Lafayette Center, 1155 21st St., NW., Washington, DC, 9th Floor Commission Conference Room. STATUS: Closed...

46 CFR 308.303 - Amounts insured under interim binder.

Science.gov (United States)

2010-10-01

... 308.303 Shipping MARITIME ADMINISTRATION, DEPARTMENT OF TRANSPORTATION EMERGENCY OPERATIONS WAR RISK INSURANCE Second Seamen's War Risk Insurance § 308.303 Amounts insured under interim binder. The amounts insured are the amounts specified in the Second Seamen's War Risk Policy (1955) or as modified by shipping...

Proceedings of the Water Reactor Fuel Performance Meeting - WRFPM / Top Fuel 2009

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-06-15

SFEN, ENS, SNR, ANS, AESJ, CNS KNS, IAEA and NEA are jointly organizing the 2009 International Water Reactor Fuel Performance / TopFuel 2009 Meeting following the 2008 KNS Water Reactor Performance Meeting held during October 19-23, 2008 in Seoul, Korea. This meeting is held annually on a tri-annual rotational basis in Europe, USA and Asia. In 2009, this meeting will be held in Paris, September 6-10, 2009 in coordination with the Global 2009 Conference at the same date and place. That would lead to a common opening session, some common technical presentations, a common exhibition and common social events. The technical scope of the meeting includes all aspects of nuclear fuel from fuel rod to core design as well as manufacturing, performance in commercial and test reactors or on-going and future developments and trends. Emphasis will be placed on fuel reliability in the general context of nuclear 'Renaissance' and recycling perspective. The meeting includes selectively front and/or back end issues that impact fuel designs and performance. In this frame, the conference track devoted to 'Concepts for transportation and interim storage of spent fuels and conditioned waste' will be shared with 'GLOBAL' conference. Technical Tracks: - 1. Fuel Performance, Reliability and Operational Experience: Fuel operating experience and performance; experience with high burn-up fuels; water side corrosion; stress corrosion cracking; MOX fuel performance; post irradiation data on lead fuel assemblies; radiation effects; water chemistry and corrosion counter-measures. - 2. Transient Fuel Behaviour and Safety Related Issues: Transient fuel behavior and criteria (RIA, LOCA, ATWS, Ramp tests..). Fuel safety-related issues such as PCI (pellet cladding interaction), transient fission gas releases and cladding bursting/ballooning during transient events - Advances in fuel performance modeling and core reload methodology, small and large-scale fuel testing

Proceedings of the Water Reactor Fuel Performance Meeting - WRFPM / Top Fuel 2009

International Nuclear Information System (INIS)

2009-06-01

SFEN, ENS, SNR, ANS, AESJ, CNS KNS, IAEA and NEA are jointly organizing the 2009 International Water Reactor Fuel Performance / TopFuel 2009 Meeting following the 2008 KNS Water Reactor Performance Meeting held during October 19-23, 2008 in Seoul, Korea. This meeting is held annually on a tri-annual rotational basis in Europe, USA and Asia. In 2009, this meeting will be held in Paris, September 6-10, 2009 in coordination with the Global 2009 Conference at the same date and place. That would lead to a common opening session, some common technical presentations, a common exhibition and common social events. The technical scope of the meeting includes all aspects of nuclear fuel from fuel rod to core design as well as manufacturing, performance in commercial and test reactors or on-going and future developments and trends. Emphasis will be placed on fuel reliability in the general context of nuclear 'Renaissance' and recycling perspective. The meeting includes selectively front and/or back end issues that impact fuel designs and performance. In this frame, the conference track devoted to 'Concepts for transportation and interim storage of spent fuels and conditioned waste' will be shared with 'GLOBAL' conference. Technical Tracks: - 1. Fuel Performance, Reliability and Operational Experience: Fuel operating experience and performance; experience with high burn-up fuels; water side corrosion; stress corrosion cracking; MOX fuel performance; post irradiation data on lead fuel assemblies; radiation effects; water chemistry and corrosion counter-measures. - 2. Transient Fuel Behaviour and Safety Related Issues: Transient fuel behavior and criteria (RIA, LOCA, ATWS, Ramp tests..). Fuel safety-related issues such as PCI (pellet cladding interaction), transient fission gas releases and cladding bursting/ballooning during transient events - Advances in fuel performance modeling and core reload methodology, small and large-scale fuel testing facilities. - 3. Advances in Water

Overview of the plant risk status information management system

International Nuclear Information System (INIS)

Kirchner, J.R.; Campbell, D.J.

1987-01-01

The Plant Risk Status Information Management System (PRISIM) is a personal computer program that presents PRA results and related information for use by decision-makers. The program was originally developed for NRC inspectors, but now an expanded version of the program with more potential applications is complete. Prototypes of both versions have been developed for Arkansas Nuclear One - Unit 1, and the inspection-related version is currently being field-tested. Interim results of these field tests are favorable. The PRISIM database contains both pre-processed information that is useful for long-term planning and a plant risk model for assessing the risk implications of the current plant status. The program provides rapid access to specific information by making extensive use of menus. Development of PRISIM programs for Peach Bottom-Unit 2 is underway, and there are plans to create programs for other plants

Meeting of the ITER CTA Project Board

International Nuclear Information System (INIS)

Vlasenkov, V.

2002-01-01

The meeting of the ITER CTA Project Board (PB) took place in Toronto, Canada on 16 September 2002 on the occasion of the fifth Negotiations Meeting (N-5). Thirteen participants, PB members and experts from Canada, EU, Japan, RF and the International Team (IT) attended the meeting chaired by Acad. E. Velikhov. PB heard progress reports of the participating parties and the comments concerning the status of participants team (PT) and the IT were presented

Retrievable surface storage: interim storage of solidified high-level waste

International Nuclear Information System (INIS)

LaRiviere, J.R.; Nelson, D.C.

1976-01-01

Studies have been conducted on retrievable-surface-storage concepts for the interim storage of solidified high-level wastes. These studies have been reviewed by the Panel on Engineered Storage, convened by the Committee on Radioactive Waste Management of the National Research Council-National Academy of Sciences. The Panel has concluded that ''retrievable surface storage is an acceptable interim stage in a comprehensive system for managing high-level radioactive wastes.'' The scaled storage cask concept, which was recommended by the Panel on Engineered Storage, consists of placing a canister of waste inside a carbon-steel cask, which in turn is placed inside a thick concrete cylinder. The waste is cooled by natural convection air flow through an annulus between the cask and the inner wall of the concrete cylinder. The complete assembly is placed above ground in an outdoor storage area

Interim analysis: A rational approach of decision making in clinical trial.

Science.gov (United States)

Kumar, Amal; Chakraborty, Bhaswat S

2016-01-01

Interim analysis of especially sizeable trials keeps the decision process free of conflict of interest while considering cost, resources, and meaningfulness of the project. Whenever necessary, such interim analysis can also call for potential termination or appropriate modification in sample size, study design, and even an early declaration of success. Given the extraordinary size and complexity today, this rational approach helps to analyze and predict the outcomes of a clinical trial that incorporate what is learned during the course of a study or a clinical development program. Such approach can also fill the gap by directing the resources toward relevant and optimized clinical trials between unmet medical needs and interventions being tested currently rather than fulfilling only business and profit goals.

Interim analysis: A rational approach of decision making in clinical trial

Directory of Open Access Journals (Sweden)

Amal Kumar

2016-01-01

Full Text Available Interim analysis of especially sizeable trials keeps the decision process free of conflict of interest while considering cost, resources, and meaningfulness of the project. Whenever necessary, such interim analysis can also call for potential termination or appropriate modification in sample size, study design, and even an early declaration of success. Given the extraordinary size and complexity today, this rational approach helps to analyze and predict the outcomes of a clinical trial that incorporate what is learned during the course of a study or a clinical development program. Such approach can also fill the gap by directing the resources toward relevant and optimized clinical trials between unmet medical needs and interventions being tested currently rather than fulfilling only business and profit goals.

75 FR 12583 - Sunshine Act; Meeting Notice

Science.gov (United States)

2010-03-16

...: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. Status: Public and Closed. Week of..., 301-415-3152). This meeting will be webcast live at the Web address-- http://www.nrc.gov . Week of...) (Contact: Jose Ibarra, 301-415-2581). This meeting will be webcast live at the Web address-- http://www.nrc...

Development of dual-purpose metal cask for interim storage of spent nuclear fuel (1). Outline of cask structure

International Nuclear Information System (INIS)

Shimizu, Masashi; Hayashi, Makoto; Kashiwakura, Jun

2003-01-01

Spent fuels discharged from nuclear power plants in Japan are planed to be reprocessed at the nuclear fuel recycle plant under construction at Rokkasho-mura. Since the amount of the spent fuels exceeds that of recycled fuel, the spent fuels have to be properly stored and maintained as recycle fuel resource until the beginning of the reprocessing. For that sake, interim storage installations are being constructed outside the nuclear power plants by 2010. The storage dry casks have been practically used as the interim storage in the nuclear power plants. From this reason, the storage system using the storage dry casks is promising as the interim storage installations away form the reactors, which are under discussion. In the interim storage facilities, the storage using the dry cask of the storage metal cask with business showings, having the function of transportation is now under discussion. By employing transportation and storage dual-purpose cask, the repack equipments can be exhausted, and the reliability of the interim storage installations can be increased. Hitachi, Ltd. has been developing the high reliable and economical transportation and storage dry metal cask. In this report, the outline of our developing transportation and storage dry cask is described. (author)

Success of Two-Stage Reimplantation in Patients Requiring an Interim Spacer Exchange.

Science.gov (United States)

George, Jaiben; Miller, Evan M; Curtis, Gannon L; Klika, Alison K; Barsoum, Wael K; Mont, Michael A; Higuera, Carlos A

2018-03-23

Some patients undergoing a 2-stage revision for a periprosthetic joint infection require a repeat spacer in the interim (removal of existing spacer with insertion of a new spacer or spacer exchange) due to persistent infection. The objectives of this study are to (1) determine the factors associated with patients who receive a repeat spacer and (2) compare the infection-free survival (overall and stratified by joint type) of reimplantation in patients who did or did not receive a repeat spacer. From 2001 to 2014, 347 hip or knee 2-stage revisions that finally underwent reimplantation and had a minimum 2-year follow-up were identified. An interim spacer exchange was performed in 59 (17%) patients (exchange cohort). Patient-related and organism-related factors were compared between the exchange and non-exchange cohorts. Kaplan-Meier survival curves were performed to assess the success (absence of signs of infection, reoperation for infection, periprosthetic joint infection-related mortality) of both cohorts. Patients in the exchange group had higher comorbidity score (P = .020), prolonged time to reimplantation (P exchange cohort, and 78% (knee 77%, hip 78%) in the non-exchange cohort (P = .020). Patients requiring an interim spacer exchange were found to have more comorbidities, prolonged treatment period, and were more likely to be infected with a resistant organism. About one-third of such patients became reinfected within 5 years compared to only one-fifth of the patients without an interim spacer exchange. Copyright © 2018 Elsevier Inc. All rights reserved.

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

Sixth meeting of the ITPA Topical Group on Diagnostics

International Nuclear Information System (INIS)

Donne, A.J.H.; Costley, A.E.

2004-01-01

The Sixth Meeting of the International Tokamak Physics Activities (ITPA) Topical Group (TG) on Diagnostics was held at JAERI, Naka from 19-21 February 2004. This meeting was combined with a Progress Meeting on ITER/BPX (burning plasma experiment) relevant diagnostic developments on-going in Japan. For the first time, ITPA members from China, as well as observers from South Korea, attended. In addition, an associated sub-meeting was held at General Atomics, San Diego, 23-24 April, immediately after the 15th Topical Conference on High Temperature Plasma Diagnostics. At the sub-meeting a special one-day session was devoted to issues related to beam-aided spectroscopy. In total more than 50 participants attended the meetings and all ITER partners were represented. The key topics reviewed and discussed at the TG meeting were: (i) the overall status of diagnostics developments for ITER, (ii) the progress in the research on the designated high priority topics, (iii) the progress with some key ITER/BPX-relevant diagnostic developments ongoing in the ITPA participant laboratories, (iv) the progress and plans for the work of the specialist working groups, (v) the status and plans for the International Diagnostic Database

7 CFR 1710.109 - Reimbursement of general funds and interim financing.

Science.gov (United States)

2010-01-01

... LOANS AND GUARANTEES Loan Purposes and Basic Policies § 1710.109 Reimbursement of general funds and... replace interim financing used to finance equipment and facilities that were included in an RUS-approved...

Public School Finance Problems in Texas. An Interim Report.

Science.gov (United States)

Texas Research League, Austin.

The U.S. District Court ruling in Rodriguez vs San Antonio Independent School District, which struck down Texas' school finance system as inequitable and unconstitutional, provided the impetus for publishing this interim report. The report documents the growing cost of State-supported public school programs--the primary concern prior to the…

Interim supply in the electricity industry

Energy Technology Data Exchange (ETDEWEB)

Strassburg, W

1977-06-01

The interim supply or the so-called 'condition without a contract' can occur within the framework of energy supply in the relationship between 1) public utility and tariff customer, 2) public utility and the special last-in-line consumer, 3) supplying and distributing public utility, 4) public utility and territorial administrative body. The present contribution deals with the cases named under (3) and (4). Cases (1) and (2) were dealt with in a previous article. Relevant contract clauses and laws and their effects on contracting partners are discussed.

Interim supply in the electricity industry

Energy Technology Data Exchange (ETDEWEB)

Strassburg, W

1977-05-01

The interim supply or the so-called 'condition without a contract' can occur within the framework of energy supply in the relationship between: 1) public utility and tariff customer, 2) public utility and the special last-in-line consumer, 3) supplying and distributing public utility, 4) public utility and territorial administrative body. The contribution at hand deals with the cases under 1) and 2); cases 3) and 4) are dealt with in an article to be published. Relevant contract clauses and laws and their effects on contracting partners are discussed. 41 references.

Central waste complex interim safety basis

International Nuclear Information System (INIS)

Cain, F.G.

1995-01-01

This interim safety basis provides the necessary information to conclude that hazards at the Central Waste Complex are controlled and that current and planned activities at the CWC can be conducted safely. CWC is a multi-facility complex within the Solid Waste Management Complex that receives and stores most of the solid wastes generated and received at the Hanford Site. The solid wastes that will be handled at CWC include both currently stored and newly generated low-level waste, low-level mixed waste, contact-handled transuranic, and contact-handled TRU mixed waste

33 CFR 96.360 - Interim Safety Management Certificate: what is it and when can it be used?

Science.gov (United States)

2010-07-01

...? § 96.360 Interim Safety Management Certificate: what is it and when can it be used? (a) A responsible... 33 Navigation and Navigable Waters 1 2010-07-01 2010-07-01 false Interim Safety Management Certificate: what is it and when can it be used? 96.360 Section 96.360 Navigation and Navigable Waters COAST...

Status of the spent fuel dry storage programme for Cernavoda NPP

International Nuclear Information System (INIS)

Radu, M.

1999-01-01

The Cernavoda NPP Unit 1 (600 MWe Standard type) is in operation since December 1996. Within the framework of the R and D Radioactive Waste and Spent Fuel Management Programme, investigations, studies and research are carried out on site identification and conceptual designs for both a Spent Fuel Interim Storage Facility and a Spent Fuel Disposal Facility. The status of the work performed in the framework of this programme as well as the situation of the spent fuel resulting from the Research Institutes will be presented in the paper. (author)

Interim geotechnical data report

International Nuclear Information System (INIS)

1986-01-01

This issue, the Interim Geotechnical Field Data Report, presents information obtained from the geotechnical activities at the WIPP site underground facilities since the last quarterly report. It also includes cumulative plots which contain all previous data. Finally, it continues the geotechnical analyses and interpretations of the data. The GFDR is organized into two principal parts. The first part, Geotechnical Field Data, presents in graphical form all the data collected since April 1982 from the geomechanical instruments. Presented in the second part, Evaluation and Analyses, are preliminary interpretations and analyses of the data. In this report, continuing geotechnical assessment of all the facility features is presented. Also included in the second part are separate sections on evaluation and interpretation of the instrumentation measurements, and an updated description and evaluation of observed behavior of the underground openings

Status and prospects for gas cooled reactor fuels. Proceedings of two IAEA meetings held in June 2004 and June 2005

International Nuclear Information System (INIS)

2009-04-01

Recently, efforts to develop high temperature gas cooled reactors with an aim to building futuristic nuclear energy systems with advanced nuclear fuel cycles in the context of the Generation IV International Forum have increased significantly. In addition, several development projects are ongoing, focusing on the burning of weapons grade plutonium, including civil plutonium and other transuranic elements using the 'deep-burn concept', or 'inert matrix fuels', especially in the form of coated particles in gas cooled reactor systems. There is also considerable global interest in developing 'nuclear hydrogen' energy systems using high temperature gas cooled reactors. Apart from these developments, the value of preserving the large technology base developed in Germany, the United Kingdom and the United States of America, as well as information developed in other countries, has also been a subject of interest to the IAEA. At the second annual meeting of the 'technical working group on nuclear fuel cycles options and spent fuel management' (TWG-NFCO), held in Vienna from 28-30 May 2003, it was recommended to hold a technical meeting on Current Status and Future Prospects of Gas Cooled Reactor Fuels. The meeting should cover the technological progress that has been made in the last three years and plan future fabrication and qualification facilities for GCR/HTR fuel. TWG-NFCO considered it timely that this progress should be presented and discussed in the interested community. Recognizing the numerous activities being pursued in many Member States, the IAEA convened the technical meeting on this topic in June 2004 in Vienna. Consequently, an update meeting was held in June 2005, which was hosted by the Kharkov Institute of Physics and Technology of Ukraine to review and integrate the latest developments. This publication combines the results of the technical meeting of June 2004 and the meeting of June 2005. The proceedings presented here contain 25 in depth papers on the

Eight meeting of the ITER diagnostic expert group

International Nuclear Information System (INIS)

Costley, A.E.; Young, K.M.

1998-01-01

The 8. Meeting of the ITER Diagnostics Expert Group which was held in San Diego, February 1998 had two main technical goals: to discuss the status and plans for developing kinetic control, and to review the current status of the design of the magnetic system

76 FR 79754 - Twelfth Meeting: RTCA Special Committee 220, Automatic Flight Guidance and Control

Science.gov (United States)

2011-12-22

... technologies Administrative items (meeting schedule, location, and next meeting agenda) Any other business... 2 status--progress, issues and plan Review of WG 3 status--progress, issues and plans Review action.... Issued in Washington, DC, on December 15, 2011. Robert L. Bostiga, Manager, Business Operations Branch...

Interim Stabilization Equipment Essential and Support Drawing Plan

International Nuclear Information System (INIS)

KOCH, M.R.

1999-01-01

The purpose of this document is to list the Interim Stabilization equipment drawings that are classified as Essential or Support drawings. Essential Drawings: Those drawings identified by the facility staff as necessary to directly support the safe operation of the facility or equipment. Support Drawings: Those drawings identified by the facility staff that further describe the design details of structures, systems or components shown on essential drawings

Effectiveness Monitoring Report, MWMF Tritium Phytoremediation Interim Measures.

Energy Technology Data Exchange (ETDEWEB)

Hitchcock, Dan; Blake, John, I.

2003-02-10

This report describes and presents the results of monitoring activities during irrigation operations for the calendar year 2001 of the MWMF Interim Measures Tritium Phytoremediation Project. The purpose of this effectiveness monitoring report is to provide the information on instrument performance, analysis of CY2001 measurements, and critical relationships needed to manage irrigation operations, estimate efficiency and validate the water and tritium balance model.

Sampling and analysis plan for Wayne Interim Storage Site (WISS), Wayne, New Jersey

International Nuclear Information System (INIS)

Brown, K.S.; Murray, M.E.; Rodriguez, R.E.

1998-10-01

This field sampling plan describes the methodology to perform an independent radiological verification survey and chemical characterization of a remediated area of the subpile at the Wayne Interim Storage Site, Wayne, New Jersey.Data obtained from collection and analysis of systematic and biased soil samples will be used to assess the status of remediation at the site and verify the final radiological status. The objective of this plan is to describe the methods for obtaining sufficient and valid measurements and analytical data to supplement and verify a radiological profile already established by the Project Remediation Management Contractor (PMC). The plan describes the procedure for obtaining sufficient and valid analytical data on soil samples following remediation of the first layer of the subpile. Samples will be taken from an area of the subpile measuring approximately 30 m by 80 m from which soil has been excavated to a depth of approximately 20 feet to confirm that the soil beneath the excavated area does not exceed radiological guidelines established for the site or chemical regulatory limits for inorganic metals. After the WISS has been fully remediated, the Department of Energy will release it for industrial/commercial land use in accordance with the Record of Decision. This plan provides supplemental instructions to guidelines and procedures established for sampling and analysis activities. Procedures will be referenced throughout this plan as applicable, and are available for review if necessary

Environmental survey of two interim dumpsites, Middle Atlantic Bight from 05 November 1973 to 10 November 1973 (NODC Accession 7501280)

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — A second oceanographic survey cruise was made to an interim municipal sludge dumpsite and initially to an interim dumpsite for the disposal of industrial acid waste...

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)

Status of national programmes on fast breeder reactors

International Nuclear Information System (INIS)

1990-09-01

The present document contains information on the status of fast breeder reactor development and on worldwide activities in this advanced nuclear power technology during 1989 as reported at the 23rd meeting of the IWGFR in Vienna, April 1990. The publication is intended to provide information regarding the current status of LMFBR development in IAEA Member States. A separate abstract was prepared for each of the 11 papers presented by the participants of this meeting. Refs, figs and tabs

Safety aspects of long-term dry interim storage of type-B spent fuel and HLW transport casks

International Nuclear Information System (INIS)

Wolff, D.; Probst, U.; Voelzke, H.; Droste, B.; Roedel, R.

2004-01-01

Based on the German decision to minimise transports of spent fuel casks between nuclear power plants, reprocessing plants and central storage facilities several on-site storage facilities have been licensed till the end of 2003. Because of the large amount of type-B transport casks which are going to be used for long-term interim storage the question of time limited type-B license maintenance during the storage period of up to 40 years has been discussed under different aspects. This paper describes present technical aspects of the discussion. A main aspect of transport cask qualification for interim storage is the long-term behaviour of the metallic seal lid system. Concerning this results from current experimental long-term tests with metallic ''Helicoflex''-seals in which pool water is enclosed are presented. The test series has been performed by the Federal Institute for Materials Research and Testing (BAM) on behalf of the Federal Office for Radiation Protection (BfS) since 2001. Finally, the paper presents a German concept for an authorities' and technical experts' exchange of experience, know-how and state of the art referring to cask dispatch in nuclear facilities. BAM has taken over a central role in this so-called ''co-ordinating institution for cask dispatching information'' (''KOBAF'') which contains an online data base and a technical working group meeting twice a year. The goal is to keep comparable technical standards for all nuclear sites and storage facilities which are going to load and dispatch casks of the same or similar types under the responsibility of different German state governments for the next decades

Final hazard classification and auditable safety analysis for the 105-C Reactor Interim Safe Storage Project

International Nuclear Information System (INIS)

Rodovsky, T.J.; Larson, A.R.; Dexheimer, D.

1996-12-01

This document summarizes the inventories of radioactive and hazardous materials present in the 105-C Reactor Facility and the operations associated with the Interim Safe Storage Project which includes decontamination and demolition and interim safe storage of the remaining facility. This document also establishes a final hazard classification and verifies that appropriate and adequate safety functions and controls are in place to reduce or mitigate the risk associated with those operations

Meeting of the ITER CTA project board

International Nuclear Information System (INIS)

Vlasenkov, V.

2002-01-01

This is information about meeting of the ITER CTA project board, which took place in Moscow, Russian Federation on 22 April 2002 on the occasion of the Third Negotiators Meeting (N3). Thirteen participants, representing PB members and experts from Canada (CA), the European Union (EU), Japan(JA), the Russian federation (RF) and the International Team (IT) attended the meeting chaired by Acad. E. Velikhov. The Project Board took note of the comments made concerning the status of the Participants Teams(PTs)

78 FR 79076 - Minority Depository Institutions Advisory Committee; Meeting

Science.gov (United States)

2013-12-27

...] Minority Depository Institutions Advisory Committee; Meeting AGENCY: Office of the Comptroller of the... Office of the Comptroller of the Currency (OCC) announces a meeting of the Minority Depository..., DC 20219. Agenda items include a discussion of the status of the minority depository institution...

Surface Water Interim Measures/Interim Remedial Action Plan/ Environmental and Decision Document, South Walnut Creek Basin, Operable Unit No.2

International Nuclear Information System (INIS)

1991-01-01

Water quality investigations have identified the presence of volatile organic compound (VOC) and radionuclide contamination of surface water at the Rocky Flats Plant (RFP). The subject interim Measures/Interim Remedial Action Plan/Environmental Assessment (IM/IRAP/EA) addresses contaminated surface water in a portion of the South Walnut Creek drainage basin located within an area identified as Operable Unit No. 2 (OU 2). There is no immediate threat to public health and the environment posed by this surface water contamination. The affected surface water is contained within the plant boundary by existing detention ponds, and is treated prior to discharge for removal of volatile contaminants and suspended particulates to which radionuclides, if present, are likely to absorb. However, there is a potential threat and the Department of Energy (DOE) is implementing this Surface Water IM/IRAP at the request of the US Environmental Protection Agency (EPA) and Colorado Department of Health (CDH). Implementation of the Surface Water IM/IRA will enhance the DOE's efforts towards containing and managing contaminated surface water, and will mitigate downgradient migration of contaminants. Another factor in implementing this IM/IRA is the length of time it will take to complete the investigations and engineering studies necessary to determine the final remedy for OU 2. 44 refs., 23 figs., 14 tabs

Current status of fusion-relevant covariance data

International Nuclear Information System (INIS)

Muir, D.W.

1994-01-01

The following review of the current status of formatted data covariance files and their multigroup processing is a contribution to the IAEA Advisory Group Meeting on ''Improved Evaluations and Integral Data Testing for FENDL,'' to be held at the Max-Planck-Institut fuer Plasmaphysik, Garching, Germany, 12--16 September 1994. The draft agenda of this meeting lists as Item 6 the ''assessment of present status and role of uncertainty files, their processing and sensitivity studies related to FENDL.'' We conclude that this is an important and timely topic and recommend needed actions in this field

[Physical activity levels among Colombian adults: inequalities by gender and socioeconomic status].

Science.gov (United States)

González, Silvia; Lozano, Óscar; Ramírez, Andrea; Grijalba, Carlos

2014-01-01

Worldwide studies show inequalities in physical activity levels related to socio-demographic characteristics. In Colombia, among the countries in Latin America with the highest inequality, the evidence related to inequalities in physical activity is limited. It is imperative to identify disparities in physical activity in the country, to guide the design of public policies aimed at promoting physical activity. 1) To estimate the prevalence and associated factors of meeting physical activity recommendations; 2) to assess inequalities by gender and socioeconomic status in meeting physical activity recommendations, and 3) to assess the trends in physical activity prevalence within a five-year period. A secondary analysis of data from the 2010 National Nutrition Survey was conducted. The sample included 27,243 adults. The International Physical Activity Questionnaire was used to measure leisure time and transport domains. Socioeconomic status was measured by the Sisben level. Compared to men, women were less likely to meet physical activity recommendations in all domains. Compared to adults from high socioeconomic-status households, low socioeconomic-status adults had a lower prevalence of meeting physical activity recommendations during leisure time and the highest prevalence of using a bicycle for transport. The factors associated with meeting physical activity recommendations differed by gender and physical activity domain. Household and individual variables explained 13.6% of the inequalities observed by gender, and 23.2% of the inequalities by socioeconomic status. In a five-year period, the prevalence of physical activity in leisure time decreased, while the physical activity of walking for transport increased and biking for transport did not change. Future interventions to increase physical activity levels in Colombia must consider inequalities by gender and socioeconomic status. Of special concern is the low prevalence of meeting physical activity

Early rehabilitation of facial defects using interim removable prostheses: A clinical case report

Directory of Open Access Journals (Sweden)

Vivekanandhan Ramkumar

2013-01-01

Full Text Available Surgical resection of neoplasms or malformations of the face may result in defects that are not amenable to immediate surgical reconstruction. Such defects can have a severe adverse effect on patient perceptions of body image and self-esteem. In these cases, the use of an interim removable facial prosthesis can offer a rapid alternative treatment solution. The patient may then resume social interactions more comfortably while permitting easy access to the facial defect to observe tissue healing while awaiting definitive rehabilitation. This article presents a case report describing the use of interim nasal prostheses to provide rapid patient rehabilitation of facial defects.

Basis for Interim Operation for the K-Reactor in Cold Standby

Energy Technology Data Exchange (ETDEWEB)

Shedrow, B.

1998-10-19

The Basis for Interim Operation (BIO) document for K Reactor in Cold Standby and the L- and P-Reactor Disassembly Basins was prepared in accordance with the draft DOE standard for BIO preparation (dated October 26, 1993).

Basis for Interim Operation for the K-Reactor in Cold Standby

International Nuclear Information System (INIS)

Shedrow, B.

1998-01-01

The Basis for Interim Operation (BIO) document for K Reactor in Cold Standby and the L- and P-Reactor Disassembly Basins was prepared in accordance with the draft DOE standard for BIO preparation (dated October 26, 1993)

Interim report on the meteorological database

International Nuclear Information System (INIS)

Stage, S.A.; Ramsdell, J.V.; Simonen, C.A.; Burk, K.W.

1993-01-01

The Hanford Environmental Dose Reconstruction (HEDR) Project is estimating radiation doses that individuals may have received from operations at Hanford from 1944 to the present. An independent Technical Steering Panel (TSP) directs the project, which is being conducted by the Battelle, Pacific Northwest Laboratories in Richland, Washington. The goals of HEDR, as approved by the TSP, include dose estimates and determination of confidence ranges for these estimates. This letter report describes the current status of the meteorological database. The report defines the meteorological data available for use in climate model calculations, describes the data collection procedures and the preparation and control of the meteorological database. This report also provides an initial assessment of the data quality. The available meteorological data are adequate for atmospheric calculations. Initial checks of the data indicate the data entry accuracy meets the data quality objectives

CAST Status Report to the SPSC for the 119th Meeting

CERN Document Server

Karuza, Marin

2015-01-01

A status report for the CAST experiment in the year 2015 is presented. It includes the current status of the experiment concerning the detection of solar axions as well as the status of the proposed activities concerning relic axions and chameleons as a candidate particles invented to solve the mystery of the dark energy.

Lessons learned from the Siting Process of an Interim Storage Facility in Spain - 12024

Energy Technology Data Exchange (ETDEWEB)

Lamolla, Meritxell Martell [MERIENCE Strategic Thinking, 08734 Olerdola, Barcelona (Spain)

2012-07-01

On 29 December 2009, the Spanish government launched a site selection process to host a centralised interim storage facility for spent fuel and high-level radioactive waste. It was an unprecedented call for voluntarism among Spanish municipalities to site a controversial facility. Two nuclear municipalities, amongst a total of thirteen municipalities from five different regions, presented their candidatures to host the facility in their territories. For two years the government did not make a decision. Only in November 30, 2011, the new government elected on 20 November 2011 officially selected a non-nuclear municipality, Villar de Canas, for hosting this facility. This paper focuses on analysing the factors facilitating and hindering the siting of controversial facilities, in particular the interim storage facility in Spain. It demonstrates that involving all stakeholders in the decision-making process should not be underestimated. In the case of Spain, all regional governments where there were candidate municipalities willing to host the centralised interim storage facility, publicly opposed to the siting of the facility. (author)

System Specification for Immobilized High-Level Waste Interim Storage

International Nuclear Information System (INIS)

CALMUS, R.B.

2000-01-01

This specification establishes the system-level functional, performance, design, interface, and test requirements for Phase 1 of the IHLW Interim Storage System, located at the Hanford Site in Washington State. The IHLW canisters will be produced at the Hanford Site by a Selected DOE contractor. Subsequent to storage the canisters will be shipped to a federal geologic repository

78 FR 42111 - National Science Board; Sunshine Act Meetings; Notice

Science.gov (United States)

2013-07-15

...'s badge. All visitors must report to the NSF visitor desk located in the lobby at the 9th and N... information. Meeting information and updates (time, place, subject matter or status of meeting) may be found...

Application of Spatial Data Modeling Systems, Geographical Information Systems (GIS), and Transportation Routing Optimization Methods for Evaluating Integrated Deployment of Interim Spent Fuel Storage Installations and Advanced Nuclear Plants

International Nuclear Information System (INIS)

Mays, Gary T.; Belles, Randy; Cetiner, Mustafa Sacit; Howard, Rob L.; Liu, Cheng; Mueller, Don; Omitaomu, Olufemi A.; Peterson, Steven K.; Scaglione, John M.

2012-01-01

The objective of this siting study work is to support DOE in evaluating integrated advanced nuclear plant and ISFSI deployment options in the future. This study looks at several nuclear power plant growth scenarios that consider the locations of existing and planned commercial nuclear power plants integrated with the establishment of consolidated interim spent fuel storage installations (ISFSIs). This research project is aimed at providing methodologies, information, and insights that inform the process for determining and optimizing candidate areas for new advanced nuclear power generation plants and consolidated ISFSIs to meet projected US electric power demands for the future.

Application of Spatial Data Modeling Systems, Geographical Information Systems (GIS), and Transportation Routing Optimization Methods for Evaluating Integrated Deployment of Interim Spent Fuel Storage Installations and Advanced Nuclear Plants

Energy Technology Data Exchange (ETDEWEB)

Mays, Gary T [ORNL; Belles, Randy [ORNL; Cetiner, Sacit M [ORNL; Howard, Rob L [ORNL; Liu, Cheng [ORNL; Mueller, Don [ORNL; Omitaomu, Olufemi A [ORNL; Peterson, Steven K [ORNL; Scaglione, John M [ORNL

2012-06-01

The objective of this siting study work is to support DOE in evaluating integrated advanced nuclear plant and ISFSI deployment options in the future. This study looks at several nuclear power plant growth scenarios that consider the locations of existing and planned commercial nuclear power plants integrated with the establishment of consolidated interim spent fuel storage installations (ISFSIs). This research project is aimed at providing methodologies, information, and insights that inform the process for determining and optimizing candidate areas for new advanced nuclear power generation plants and consolidated ISFSIs to meet projected US electric power demands for the future.

78 FR 59425 - Minority Depository Institutions Advisory Committee Meeting

Science.gov (United States)

2013-09-26

...] Minority Depository Institutions Advisory Committee Meeting AGENCY: Office of the Comptroller of the... Office of the Comptroller of the Currency (OCC) announces a meeting of the Minority Depository... discussion of the status of the minority depository institution industry and current topics of interest to...

Interim safety basis compliance matrix for Trenches 31 and 34

International Nuclear Information System (INIS)

Ames, R.R.

1994-01-01

The tables provided in this document identify the specific requirements and basis for the administrative controls established in the Westinghouse Hanford Company (WHC) Solid Waste Burial Ground (SWBG) Interim Safety Basis (ISB) for operation of the Project W-025, Mixed Waste Lined Landfill (Trenches 31 and 34). The tables document the necessary controls and implementing procedures to ensure compliance with the requirements of the ISB. These requirements provide a basis for future Unreviewed Safety Questions (USQ) screening of applicable procedure changes, proposed physical modifications, tests, experiments, and occurrences. Table 1 provides the SWBG interim Operational Safety Requirements administrative controls matrix. The specific assumptions and commitments used in the safety analysis documents applicable to disposal of mixed wastes in Trenches 31 and 34 are provided in Table 2. Table 3 is provided to document the potential engineered and administrative mitigating features identified in the Preliminary Hazard Analysis (PHA) for disposal of mixed waste

How the University of Texas system responded to the need for interim storage of low-level radioactive waste materials.

Science.gov (United States)

Emery, Robert J

2012-11-01

Faced with the prospect of being unable to permanently dispose of low-level radioactive wastes (LLRW) generated from teaching, research, and patient care activities, component institutions of the University of Texas System worked collaboratively to create a dedicated interim storage facility to be used until a permanent disposal facility became available. Located in a remote section of West Texas, the University of Texas System Interim Storage Facility (UTSISF) was licensed and put into operation in 1993, and since then has provided safe and secure interim storage for up to 350 drums of dry solid LLRW at any given time. Interim storage capability provided needed relief to component institutions, whose on-site waste facilities could have possibly become overburdened. Experiences gained from the licensing and operation of the site are described, and as a new permanent LLRW disposal facility emerges in Texas, a potential new role for the storage facility as a surge capacity storage site in times of natural disasters and emergencies is also discussed.

Interim reliability evaluation program, Browns Ferry fault trees

International Nuclear Information System (INIS)

Stewart, M.E.

1981-01-01

An abbreviated fault tree method is used to evaluate and model Browns Ferry systems in the Interim Reliability Evaluation programs, simplifying the recording and displaying of events, yet maintaining the system of identifying faults. The level of investigation is not changed. The analytical thought process inherent in the conventional method is not compromised. But the abbreviated method takes less time, and the fault modes are much more visible

Repacking of Cobalt 60 spent sources in the central interim storage

International Nuclear Information System (INIS)

Zeleznik, N.

2003-01-01

After the transfer of the responsibility for the management of the Central interim storage for waste from small producers, located at the reactor centre in Brinje near Ljubljana, Slovenia, the national Agency for radwaste management (ARAO) started with most urgent activities to improve the utilization of the storage facility. One of the main tasks has also been the rearrangement of the already stored radioactive waste in order to reduce volume of the waste and to collect same radioisotopes in the containers. The latest campaign, performed in 2002/2003, was repacking of all Co-60 spent sealed sources in the storage facility and also at the producer's premises which were after conditioning put into two drums with concrete matrix and stored back to the Central interim storage. The preparation works together with the implementation are described in the paper. (author)

Evaluation of Hose in Hose Transfer Line Service Life for Hanford's Interim Stabilization Program

International Nuclear Information System (INIS)

TORRES, T.D.

2000-01-01

RPP-6153, Engineering Task Plan for Hose-in-Hose Transfer System for the Interim Stabilization Program, defines the programmatic goals, functional requirements, and technical criteria for the development and subsequent installation of transfer line equipment to support Hanford's Interim Stabilization Program. RPP-6028, Specification for Hose in Hose Transfer Lines for Hanford's Interim Stabilization Program, has been issued to define the specific requirements for the design, manufacture, and verification of transfer line assemblies for specific waste transfer applications. Included in RPP-6028 are tables defining the chemical constituents of concern to which transfer lines will be exposed. Current Interim Stabilization Program planning forecasts that the at-grade transfer lines will be required to convey pumpable waste for as much as three years after commissioning. Prudent engineering dictates that the equipment placed in service have a working life in excess of this forecasted time period, with some margin to allow for future adjustments to the planned schedule. This document evaluates the effective service life of the Hose-in-Hose Transfer Lines, based on information submitted by the manufacturer and published literature. The effective service life of transfer line assemblies is a function of several factors. Foremost among these are process fluid characteristics, ambient environmental conditions, and the manufacturer's stated shelf life. This evaluation examines the manufacturer's certification of shelf life, the manufacturer's certifications of chemical compatibility with waste, and published literature on the effects of exposure to ionizing radiation on the mechanical properties of elastomeric materials to evaluate transfer line service life

Original : English STANDING CONCERTATION COMMITTEE ORDINARY MEETING ON 28 MARCH 2001

CERN Multimedia

2001-01-01

This meeting was mainly devoted to follow-up from the Finance Committee in March, to preparation for TREF in May and to discussion of status reports from several Sub-Groups of the SCC. 1. Follow-up from the meeting of the Finance Committee in March and preparation for the meeting of TREF in May As agreed at the Finance Committee in March, the Management will prepare an explanatory document on the discrepancy of -0.3% in the net salary adjustment applied as a result of the 5-yearly Review. This document will be presented at the next meeting of TREF on 18 May, and then to the Finance Committee on 13 June. Other items on TREF's Draft Agenda include a status report on preparation for implementing the new career structure in September, together with modifications of the Staff Rules and Regulations, and a status report on implementation of detailed provisions concerning Long-Term Care. The Staff Association suggested that the subject of staffing levels should also be included in the agenda for TREF. The Management ...

Evaluation of Dynamic Behavior of Pile Foundations for Interim Storage Facilities Through Geotechnical Centrifuge Tests

International Nuclear Information System (INIS)

Shizuo Tsurumaki; Hiroyuki Watanabe; Akira Tateishi; Kenichi Horikoshi; Shunichi Suzuki

2002-01-01

In Japan, there is a possibility that interim storage facilities for recycled nuclear fuel resources may be constructed on quaternary layers, rather than on hard rock. In such a case, the storage facilities need to be supported by pile foundations or spread foundations to meet the required safety level. The authors have conducted a series of experimental studies on the dynamic behavior of storage facilities supported by pile foundations. A centrifuge modeling technique was used to satisfy the required similitude between the reduced size model and the prototype. The centrifuge allows a high confining stress level equivalent to prototype deep soils to be generated (which is considered necessary for examining complex pile-soil interactions) as the soil strength and the deformation are highly dependent on the confining stress. The soil conditions were set at as experimental variables, and the results are compared. Since 2000, the Nuclear Power Engineering Corporation (NUPEC) has been conducting these research tests under the auspices on the Ministry of Economy, Trade and Industry of Japan. (authors)

MANAGEMENT BOARD MEETING OF 30 SEPTEMBER 1999

CERN Multimedia

1999-01-01

For informationOutcome of the September meetings of the Scientific Policy Committee, Finance Committee and Committee of Council.The Management Board's September meeting was mainly devoted to a review of the recent meetings of the Scientific Policy Committee, Finance Committee and Committee of Council. The Director-General reported on the following highlights:LHC Status ReportStatus reports on the LHC machine presented by L. Evans, the LHC Project Leader, had been well received by the Scientific Policy Committee and Committee of Council, which had expressed satisfaction at the progress made. Informing them of an accident that had occurred during the testing of the first long LHC dipole as an illustration of problems encountered and successfully overcome, Dr Evans had explained that sparking in the 15-m dipole had resulted in significant external damage and an unprotected quench. After re-tuning, however, the magnet had been successfully re-powered to reach well above the nominal field at first quench, thus dem...

Status of liquid metal fast reactor development. Proceedings of the 27. meeting of the International Working Group on Fast Reactors held in Vienna, 17-19 May 1994

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-03-01

These proceedings contain updated and new information on the status of fast reactor development and on activities in the field of advanced nuclear power technology during 1993, as reported at the 27th meeting of the IWGFR held in Vienna, from 17 to 19 May 1994. Refs, figs and tabs.

Status of liquid metal fast reactor development. Proceedings of the 27. meeting of the International Working Group on Fast Reactors held in Vienna, 17-19 May 1994

International Nuclear Information System (INIS)

1995-03-01

These proceedings contain updated and new information on the status of fast reactor development and on activities in the field of advanced nuclear power technology during 1993, as reported at the 27th meeting of the IWGFR held in Vienna, from 17 to 19 May 1994. Refs, figs and tabs

Immobilized High-Level Waste (HLW) Interim Storage Alternative Generation and analysis and Decision Report - second Generation Implementing Architecture

International Nuclear Information System (INIS)

CALMUS, R.B.

2000-01-01

Two alternative approaches were previously identified to provide second-generation interim storage of Immobilized High-Level Waste (IHLW). One approach was retrofit modification of the Fuel and Materials Examination Facility (FMEF) to accommodate IHLW. The results of the evaluation of the FMEF as the second-generation IHLW interim storage facility and subsequent decision process are provided in this document

Cost studies concerning decontamination and dismantling. The interim store for spent fuel at Studsvik

International Nuclear Information System (INIS)

Sjoeblom, Rolf; Sjoeoe, Cecilia; Lindskog, Staffan; Cato, Anna

2006-04-01

The interim store for spent fuel at Studsvik was designed and constructed in 1962-64. It has been used for wet storage of fuel from the Aagesta Nuclear Power Plant as well as the R2 reactor at Studsvik. The interim store comprises three cylindrical pools for fuel storage as well as equipment for handling and decontamination. The purpose of the present work is to develop methodology for calculation of future costs for decontamination and dismantling of nuclear research facilities. The analysis is based on information from Studsvik as well as results from information searches. The requirements on precision of cost calculations is high, also at early stages. The reason for this is that the funds are to be collected now but are to be used some time in the future. At the same time they should neither be insufficient nor superfluous. It is apparent from the compilation and analysis that when methodology that has been developed for the purpose of cost calculations for power reactors is applied to research facilities certain drawbacks become apparent, e.g. difficulties to carry out variation analyses. Generally, feedback of data on incurred costs for the purpose of cost calculations can be achieved by using one or more scaling factors together with weighing factors which are established based on e.g. expert judgement. For development and utilisation of such tools it is necessary to have access to estimated costs together with incurred ones. In the report, the following combination of aspects is identified as being of primary significance for achieving a high precision: Calculations with the possibility to calibrate against incurred costs; Radiological surveying tailored to the needs for calculations; Technical planning including selection of techniques to be used; Identification of potential sources for systematic deviations. In the case of the interim store, some of the sources of uncertainty are as follows: Damaged surface layers in the pools; Maintenance status for the

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)

Meeting of the Technical Working Group on Fast Reactors (TWG-FR) (41st Annual Meeting). Working Material

International Nuclear Information System (INIS)

2008-01-01

The objectives of the meeting were to: - Exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); - Review the progress since the 40th TWG-FR Annual Meeting, including the status of the actions; - Consider meeting arrangements for 2008, 2009, 2010 and beyond; - Review the IAEA’s ongoing information exchange and coordinated research activities in the technical fields relevant to the TWG-FR (FRs and ADS), as well as coordination of the TWG-FR’s activities with other organizations and international initiatives; - Discuss future joint activities in view of IAEA’s Programme and Budget Cycles beyond 2008-2009

94TH ACCU MEETING

CERN Multimedia

PH Department

2011-01-01

DRAFT Agenda for the meeting to be held on Wednesday 7 December 2011 at 9:15 a.m. in room 60-6-002   Chairperson's remarks Adoption of the agenda      Minutes of the previous meeting Matters arising       News from the CERN Management Report on services from GS department Users’ Office news Report on new CHIS rules Creche status Report on Summer Students Users Organization in the U.S. (US LUO) Reports from ACCU representatives on other Committees Accommodation Facilities Working Group Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 13 is invited to send them to the Chairperson in writing or by e-mail to mailto:Michael.Hauschild@cern.ch subject = Next ACCU meeting.   Michael Hauschild (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review th...

In-situ storage: An approach to interim remedial action - recent case studies in Canada

International Nuclear Information System (INIS)

Zelmer, R.L.

1991-01-01

The Low-Level Radioactive Waste Management Office (LLRWMO) acts on behalf of the federal government to manage historic low-level radioactive wastes. Recent interim remedial work in the Town of Port Hope, Ontario has included the consolidation of radium and uranium contaminated soils into temporary storage facilities on two sites to await final disposal elsewhere. Simple containments constructed and sited on already contaminated sites have been found effective as part of an interim remedial strategy. The approach has been accepted and supported by the local public. Lessons have been learned from a project management, environmental remediation and engineering design point of view

Both Mother and Infant Require a Vitamin D Supplement to Ensure That Infants' Vitamin D Status Meets Current Guidelines.

Science.gov (United States)

Aghajafari, Fariba; Field, Catherine J; Weinberg, Amy R; Letourneau, Nicole

2018-03-29

We examined the association between maternal vitamin D intake during breastfeeding with their infants' vitamin D status in infants who did or did not receive vitamin D supplements to determine whether infant supplementation was sufficient. Using plasma from a subset of breastfed infants in the APrON (Alberta Pregnant Outcomes and Nutrition) cohort, vitamin D status was measured by liquid chromatography-tandem mass spectrometry. Maternal and infants' dietary data were obtained from APrON's dietary questionnaires. The median maternal vitamin D intake was 665 International Units (IU)/day, while 25% reported intakes below the recommended 400 IU/day. Of the 224 infants in the cohort, 72% were exclusively breastfed, and 90% were receiving vitamin D supplements. Infants' median 25(OH)D was 96.0 nmol/L (interquartile ranges (IQR) 77.6-116.2), and 25% had 25(OH)D < 75 nmol/L. An adjusted linear regression model showed that, with a 100 IU increase in maternal vitamin D intake, infants' 25(OH)D increased by 0.9 nmol/L controlling for race, season, mid-pregnancy maternal 25(OH)D, birthweight, and whether the infant received daily vitamin D supplement (β = 0.008, 95% confidence interval (CI) 0.002, 0.13). These results suggest that, to ensure infant optimal vitamin D status, not only do infants require a supplement, but women also need to meet current recommended vitamin D intake during breastfeeding.

ACCU MEETING

CERN Document Server

Chris Onions

2007-01-01

DRAFT Agenda for the meeting to be held on Wednesday 13 June 2007 at 9:15 a.m. in room 60-6-002 Chairman's remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management Dosimetry at CERN Status of collaborative tools at CERN Reports from ACCU representatives on other committees Users' Office newss Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 10 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Belgium G. Wilquet (74664) Bulgaria Czech Republic P. Závada (75877) Denmark J.B. Hansen (75941) Finland K. Lassila-Perini (7935...

Interim status of vertical calciner testing through calendar year 1996

International Nuclear Information System (INIS)

Compton, J.A.

1998-01-01

A prototype vertical calciner was constructed and tested for use in converting plutonium solutions to dry plutonium dioxide in the Hanford Plutonium Finishing Plant. Six non-radioactive runs were completed in June and July, 1995. Fourteen runs with plutonium nitrate solutions were completed between September, 1995 and August, 1996. Equipment modifications were made following those runs. The test runs with plutonium have converted 62.3 L of feed solution containing 11.1 kg of plutonium into dry plutonium dioxide containing 8.5 kg of plutonium. The decrease in product plutonium content is primarily due to plutonium accumulation within the calciner powder bed from particle compaction. Nine of the eleven product batches have had Losses On Ignition that met the storage criterion of less than 0.5 weight percent at 950 C. The highest Loss On Ignition found was 0.718 weight percent. Initial problems with agitator shaft binding and breakage of bushings have been eliminated. A feed pump control problem has been found and the pump replaced. Improvement in scrubber efficiency is needed. Future runs are planned to confirm that (1) the remainder of product meets the Loss On Ignition criterion, (2) the replacement feedpump works as needed, and (3) the scrubber efficiency improves. The operating staff for the production calciner may also be observing the prototype's runs to gain familiarity with the process and equipment

Conceptual design report for regional low-level waste interim storage site

International Nuclear Information System (INIS)

Bird, M.V.; Thompson, J.D.

1981-08-01

An interim storage site design concept was developed for receiving 100,000 ft 3 low-level waste per year, in the form of solidified wastes in 55-gallon drums with a dose rate of < 200 mrem per hour at contact

77 FR 28626 - Sunshine Act Meetings

Science.gov (United States)

2012-05-15

..., Tucson, Arizona 85745. STATUS: This meeting will be open to the public, unless it is necessary for the... governance and (6) personnel matters. PORTIONS OPEN TO THE PUBLIC: All agenda items except as noted below...

Interim Design Report

CERN Document Server

Choubey, S.; Goswami, S.; Berg, J.S.; Fernow, R.; Gallardo, J.C.; Gupta, R.; Kirk, H.; Simos, N.; Souchlas, N.; Ellis, M.; Kyberd, P.; Benedetto, E.; Fernandez-Martinez, E.; Efthymiopoulos, I.; Garoby, R.; Gilardoni, S.; Martini, M.; Prior, G.; Ballett, P.; Pascoli, S.; Bross, A.; Geer, S.; Johnstone, C.; Kopp, J.; Mokhov, N.; Morfin, J.; Neuffer, D.; Parke, S.; Popovic, M.; Strait, J.; Striganov, S.; Blondel, A.; Dufour, F.; Laing, A.; Soler, F.J.P; Lindner, M.; Schwetz, T.; Alekou, A.; Apollonio, M.; Aslaninejad, M.; Bontoiu, C.; Dornan, P.; Eccleston, R.; Kurup, A.; Long, K.; Pasternak, J.; Pozimski, J.; Bogacz, A.; Morozov, V.; Roblin, Y.; Bhattacharya, S.; Majumdar, D.; Mori, Y.; Planche, T.; Zisman, M.; Cline, D.; Stratakis, D.; Ding, X.; Coloma, P.; Donini, A.; Gavela, B.; Lopez Pavon, J.; Maltoni, M.; Bromberg, C.; Bonesini, M.; Hart, T.; Kudenko, Y.; Mondal, N.; Antusch, S.; Blennow, M.; Ota, T.; Abrams, R.J.; Ankenbrandt, C.M.; Beard, K.B.; Cummings, M.A.C.; Flanagan, G.; Johnson, R.P.; Roberts, T.J.; Yoshikawa, C.Y.; Migliozzi, P.; Palladino, V.; de Gouvea, A.; Graves, V.B.; Kuno, Y.; Peltoniemi, J.; Blackmore, V.; Cobb, J.; Witte, H.; Mezzetto, M.; Rigolin, S.; McDonald, K.T.; Coney, L.; Hanson, G.; Snopok, P.; Tortora, L.; Andreopoulos, C.; Bennett, J.R.J.; Brooks, S.; Caretta, O.; Davenne, T.; Densham, C.; Edgecock, R.; Kelliher, D.; Loveridge, P.; McFarland, A.; Machida, S.; Prior, C.; Rees, G.; Rogers, C.; Thomason, J.W.G.; Booth, C.; Skoro, G.; Karadzhov, Y.; Matev, R.; Tsenov, R.; Samulyak, R.; Mishra, S.R.; Petti, R.; Dracos, M.; Yasuda, O.; Agarwalla, S.K.; Cervera-Villanueva, A.; Gomez-Cadenas, J.J.; Hernandez, P.; Li, T.; Martin-Albo, J.; Huber, P.; Back, J.; Barker, G.; Harrison, P.; Meloni, D.; Tang, J.; Winter, W.

2011-01-01

The International Design Study for the Neutrino Factory (the IDS-NF) was established by the community at the ninth "International Workshop on Neutrino Factories, super-beams, and beta- beams" which was held in Okayama in August 2007. The IDS-NF mandate is to deliver the Reference Design Report (RDR) for the facility on the timescale of 2012/13. In addition, the mandate for the study [3] requires an Interim Design Report to be delivered midway through the project as a step on the way to the RDR. This document, the IDR, has two functions: it marks the point in the IDS-NF at which the emphasis turns to the engineering studies required to deliver the RDR and it documents baseline concepts for the accelerator complex, the neutrino detectors, and the instrumentation systems. The IDS-NF is, in essence, a site-independent study. Example sites, CERN, FNAL, and RAL, have been identified to allow site-specific issues to be addressed in the cost analysis that will be presented in the RDR. The choice of example sites shou...

Interim FEP report for the safety assessment SR-Can

Energy Technology Data Exchange (ETDEWEB)

Skagius, Kristina (ed.) [Kemakta Konsult AB, Stockholm (Sweden)

2004-08-01

This report describes the work with identification and structuring of features, events and processes (FEPs) that has been carried out within the scope of the SR-Can safety assessment up to the time of the interim reporting of the project. The overall objective of the work is to develop a database of features, events and processes in a format that would facilitate both a systematic analysis of FEPs and documentation of the FEP analysis as well as facilitate revisions and updates to be made in connection with new safety assessments. This overall objective also includes the development of procedures for a systematic FEP analysis as well as to apply these procedures in order to arrive at an SR-Can version of the FEP database. The work started by implementing the content of the SR 97 Process report into a database format suitable for import and processing of FEP information from other sources. The SR 97 version of the database was systematically audited against the NEA database with Project FEPs, version 1.2. In addition, an earlier audit of the SR 97 process report against the interaction matrices developed for a deep repository of the KBS-3 type was revisited and updated. Relevant FEPs from the audit were sorted into three main categories in the SR-Can database i) FEPs related to the initial states of the repository system, ii) FEPs related to internal processes of the repository system, and iii) FEPs related to external impacts on the repository system. These groups of FEPs were further processed for making decisions on how to handle these FEPs in the assessment. Biosphere processes were not included in the SR 97 Process report and there is thus not the same basis for updating these descriptions as for the engineered barriers and the geosphere. All biosphere FEPs from the audit have therefore been compiled in a single category in the database, but remain to be further handled. FEPs were also categorised as irrelevant or as being related to methodology on a general

Interim FEP report for the safety assessment SR-Can

International Nuclear Information System (INIS)

Skagius, Kristina

2004-08-01

This report describes the work with identification and structuring of features, events and processes (FEPs) that has been carried out within the scope of the SR-Can safety assessment up to the time of the interim reporting of the project. The overall objective of the work is to develop a database of features, events and processes in a format that would facilitate both a systematic analysis of FEPs and documentation of the FEP analysis as well as facilitate revisions and updates to be made in connection with new safety assessments. This overall objective also includes the development of procedures for a systematic FEP analysis as well as to apply these procedures in order to arrive at an SR-Can version of the FEP database. The work started by implementing the content of the SR 97 Process report into a database format suitable for import and processing of FEP information from other sources. The SR 97 version of the database was systematically audited against the NEA database with Project FEPs, version 1.2. In addition, an earlier audit of the SR 97 process report against the interaction matrices developed for a deep repository of the KBS-3 type was revisited and updated. Relevant FEPs from the audit were sorted into three main categories in the SR-Can database i) FEPs related to the initial states of the repository system, ii) FEPs related to internal processes of the repository system, and iii) FEPs related to external impacts on the repository system. These groups of FEPs were further processed for making decisions on how to handle these FEPs in the assessment. Biosphere processes were not included in the SR 97 Process report and there is thus not the same basis for updating these descriptions as for the engineered barriers and the geosphere. All biosphere FEPs from the audit have therefore been compiled in a single category in the database, but remain to be further handled. FEPs were also categorised as irrelevant or as being related to methodology on a general

Proceedings of the seventh annual participants' information meeting. DOE Low-Level Waste Management Program

International Nuclear Information System (INIS)

1986-02-01

The Seventh Annual Department of Energy (DOE) Low-Level Waste Management Program (LLWMP) Participants' Information Meeting was held September 10-13, 1985 in Las Vegas, Nevada. The purpose of the meeting was to provide a forum for exchange of information on low-level radioactive waste management activities, requirements, and plans. Attendees included representatives from the DOE Nuclear Energy and Defense Low-Level Waste Management Programs, interim operations offices and their contractor operators; representatives from the US Nuclear Regulatory Commission, US Environmental Protection Agency, US Geological Survey, and their contractors; representatives of states and regions responsible for development of new commercial low-level waste disposal facilities; representatives of Great Britain, France, and Canada; representatives of utilities, private contractors, and parties concerned with low-level waste management issues. The meeting was organized by topical areas to allow for the exchange of information and the promotion of discussion on specific aspects of low-level waste management. Plenary sessions were held at the start and conclusion of the meeting while seven concurrent topical sessions were held during the intervening day and a half. Session chairmen from each of these concurrent sessions presented a summary of the discussion and conclusions resulting from their respective sessions at the final plenary session

Safety aspects of long-term dry interim storage of Type B spent fuel and high-level transport casks

International Nuclear Information System (INIS)

Wolff, D.; Probst, U.; Voelzke, H.; Droste, B.; Roedel, R.

2004-01-01

Based on the German decision to minimise transport of spent fuel casks between nuclear power plants, reprocessing plants and central storage facilities several on-site storage facilities were licensed until the end of 2003. Because of the large amount of Type B(U) transport casks which are going to be used for long-term interim storage the question of time-limited Type B(U) licence maintenance during the storage period of up to 40 years has been discussed under different aspects. This paper describes present technical aspects of the discussion. A main aspect of qualification of transport casks for interim storage is the long-term behaviour of the metallic seal-lid system. Here we present results from current long-term experimental tests with metallic 'Helicoflex' seals in which pool water is enclosed. This series of tests has been performed by the Federal Institute for Materials Research and Testing (BAM) on behalf of the Federal Office for Radiation Protection (BfS) since 2001. Finally, the paper presents a German concept for an exchange of experience, know-how and state-of-the-art between authorities and technical experts with regard to cask dispatch in nuclear facilities. BAM has taken over a central role in this so-called 'coordinating institution for cask dispatching information' ('KOBAF') which entails management of an online database of cask-specific documents and a technical working group meeting twice a year. The goal is to keep comparable technical standards for all nuclear sites and storage facilities which are going to load and dispatch casks of the same or similar types under the responsibility of different German state governments for the coming decades. (author)

40 CFR 57.302 - Performance level of interim constant controls.

Science.gov (United States)

2010-07-01

... correction of the effects of any serious deficiencies in the system. For the purpose of this paragraph, at... system if the smelter owner has not upgraded serious deficiencies in the constant control system in... 40 Protection of Environment 5 2010-07-01 2010-07-01 false Performance level of interim constant...

Status of environmental technology; Interim Report to the sector study 'Petroleum and Energy', the integrated management plan for North Sea. Mapping of available environmental technology; Statusrapport for miljoeteknologi

Energy Technology Data Exchange (ETDEWEB)

2011-03-15

The purpose of this report is to provide an overview of the current status of environmental technology that may help to prevent and reduce / prevent environmental pollution. The report is a foundation report to the management plan for the North Sea. The report was prepared based on the NPD's knowledge and with good input from the PSA, and resource persons in the oil companies. The following is given a summary of the various disciplines and the technological challenges the industry has managed to meet and which ones remain. (Author)

FRACTIONAL CRYSTALLIZATION TESTING WITH INTERIM PRETREATMENT SYSTEM FEEDS

International Nuclear Information System (INIS)

HERTING DL

2008-01-01

The fractional crystallization process was developed as a pretreatment method for saltcake waste retrieved from Hanford single-shell tanks (SST). The process separates the retrieved SST waste into a high-level waste stream containing the bulk of the radionuclides and a low-activity waste stream containing the bulk of the nonradioactive sodium salts. The Interim Pretreatment System project shifted the focus on pretreatment planning from SST waste to double-shell tank waste

Dry storage of spent fuel elements: interim facility

International Nuclear Information System (INIS)

Quihillalt, O.J.

1993-01-01

Apart from the existing facilities to storage nuclear fuel elements at Argentina's nuclear power stations, a new interim storage facility has been planned and projected by the Argentinean Atomic Energy Commission (CNEA) that will be constructed by private group. This article presents the developments and describes the activities undertaken until the national policy approach to the final decision for the most suitable alternative to be adopted. (B.C.A.). 09 refs, 01 fig, 09 tabs

Interim Stabilization Equipment Essential and Support Drawing Plan

International Nuclear Information System (INIS)

HORNER, T.M.

2000-01-01

The purpose of this document is to list the Interim Stabilization equipment drawings that are classified as Essential or Support drawings. Essential Drawings are those drawings identified by the facility staff as necessary to directly support the safe operation of the facility or equipment. [CHG 2000a]. Support Drawings are those drawings identified by the facility staff that further describe the design details of structures, systems or components shown on essential drawings. [CHG 2000a

Functions and requirements document for interim store solidified high-level and transuranic waste

Energy Technology Data Exchange (ETDEWEB)

Smith-Fewell, M.A., Westinghouse Hanford

1996-05-17

The functions, requirements, interfaces, and architectures contained within the Functions and Requirements (F{ampersand}R) Document are based on the information currently contained within the TWRS Functions and Requirements database. The database also documents the set of technically defensible functions and requirements associated with the solidified waste interim storage mission.The F{ampersand}R Document provides a snapshot in time of the technical baseline for the project. The F{ampersand}R document is the product of functional analysis, requirements allocation and architectural structure definition. The technical baseline described in this document is traceable to the TWRS function 4.2.4.1, Interim Store Solidified Waste, and its related requirements, architecture, and interfaces.

Financial compensation for municipalities hosting interim or final disposal facilities for radioactive waste

International Nuclear Information System (INIS)

Barboza, Alex; Vicente, Roberto

2005-01-01

Brazilian Law No. 10308 issued November 20, 2001, establishes in its 34th article that 'those municipalities hosting interim or final disposal facilities for radioactive waste are eligible to receive a monthly payment as compensation'. The values of due payments depend on parameters such as volume of wastes and activity and half-lives of the radionuclides. The method to calculating those values was established by the National Commission on Nuclear Energy, the Brazilian regulatory authority, by Resolution No. 10, issued in the August 18, 2003. In this paper we report the application of that method to a low- and intermediate-level radioactive waste interim storage facility at the Nuclear Energy Research Institute. (author)

F/H area high level waste tank status report

International Nuclear Information System (INIS)

Hayes, C.R. Jr.; Wells, M.N.

1997-03-01

Section IX.E.3 of the SRS Federal Facility Agreement requires the DOE to submit to EPA and SCDHEC, an annual report on the status of tanks being removed from service. Tanks that are slated for removal from service either do not meet secondary containment standards or have leak sites. The attached document is intended to meet this annual report requirement. An updated status of relevant portions of the Waste Removal Plan and Schedule is also included

ETF interim design review

International Nuclear Information System (INIS)

Steiner, D.; Rutherford, P.H.

1980-01-01

A three-day ETF Interim Design Review was conducted on July 23-25, 1980, at the Sheraton Potomac Inn in Rockville, Maryland. The intent of the review was to provide a forum for an in-depth assessment and critique of all facets of the ETF design by members of the fusion community. The review began with an opening plenary session at which an overview of the ETF design was presented by D. Steiner, manager of the ETF Design Center, complemented by a physics overview by P.H. Rutherford, chairman of the ETF/INTOR Physics Committee. This was followed by six concurrent review sessions over the next day and a half. The review closed with a plenary session at which the Design Review Board presented its findings. This document consists of the viewgraphs for the opening plenary session and an edited version of the presentations made by Steiner and Rutherford

Annex D-200 Area Interim Storage Area Final Safety Analysis Report [FSAR] [Section 1 & 2

Energy Technology Data Exchange (ETDEWEB)

CARRELL, R D

2002-07-16

The 200 Area Interim Storage Area (200 Area ISA) at the Hanford Site provides for the interim storage of non-defense reactor spent nuclear fuel (SNF) housed in aboveground dry cask storage systems. The 200 Area ISA is a relatively simple facility consisting of a boundary fence with gates, perimeter lighting, and concrete and gravel pads on which to place the dry storage casks. The fence supports safeguards and security and establishes a radiation protection buffer zone. The 200 Area ISA is nominally 200,000 ft{sup 2} and is located west of the Canister Storage Building (CSB). Interim storage at the 200 Area ISA is intended for a period of up to 40 years until the materials are shipped off-site to a disposal facility. This Final Safety Analysis Report (FSAR) does not address removal from storage or shipment from the 200 Area ISA. Three different SNF types contained in three different dry cask storage systems are to be stored at the 200 Area ISA, as follows: (1) Fast Flux Test Facility Fuel--Fifty-three interim storage casks (ISC), each holding a core component container (CCC), will be used to store the Fast Flux Test Facility (FFTF) SNF currently in the 400 Area. (2) Neutron Radiography Facility (NRF) TRIGA'--One Rad-Vault' container will store two DOT-6M3 containers and six NRF TRIGA casks currently stored in the 400 Area. (3) Commercial Light Water Reactor Fuel--Six International Standards Organization (ISO) containers, each holding a NAC-I cask4 with an inner commercial light water reactor (LWR) canister, will be used for commercial LWR SNF from the 300 Area. An aboveground dry cask storage location is necessary for the spent fuel because the current storage facilities are being shut down and deactivated. The spent fuel is being transferred to interim storage because there is no permanent repository storage currently available.

Release of radionuclides following severe accident in interim storage facility. Source term determination

International Nuclear Information System (INIS)

Morandi, S.; Mariani, M.; Giacobbo, F.; Covini, R.

2006-01-01

Among the severe accidents that can cause the release of radionuclides from an interim storage facility, with a consequent relevant radiological impact on the population, there is the impact of an aircraft on the facility. In this work, a safety assessment analysis for the case of an aircraft crash into an interim storage facility is tackled. To this aim a methodology, based upon DOE, IAEA and NUREG standard procedures and upon conservative yet realistic hypothesis, has been developed in order to evaluate the total radioactivity, source term, released to the biosphere in consequence of the impact, without recurring to the use of complicated numerical codes. The procedure consists in the identification of the accidental scenarios, in the evaluation of the consequent damage to the building structures and to the waste packages and in the determination of the total release of radionuclides through the building-atmosphere interface. The methodology here developed has been applied to the case of an aircraft crash into an interim storage facility currently under design. Results show that in case of perforation followed by a fire incident the total released activity would be greater of some orders of magnitude with respect to the case of mere perforation. (author)

Experience with the licensing of the interim spent fuel storage facility modification

International Nuclear Information System (INIS)

Bezak, S.; Beres, J.

1999-01-01

After political and economical changes in the end of eighties, the utility operating the nuclear power plants in the Slovak Republic (SE, a.s.) decided to change the original scheme of the back-end of the nuclear fuel cycle; instead of reprocessing in the USSR/Russian Federation spent fuel will be stored in an interim spent fuel storage facility until the time of the final decision. As the best solution, a modification of the existing interim spent fuel storage facility has been proposed. Due to lack of legal documents for this area, the Regulatory Authority of the Slovak Republic (UJD SR) performed licensing procedures of the modification on the basis of recommendations by the IAEA, the US NRC and the relevant parts of the US CFR Title 10. (author)

Safety of Long-term Interim Storage Facilities - Workshop Proceedings

International Nuclear Information System (INIS)

2014-01-01

The objective of this workshop was to discuss and review current national activities, plans and regulatory approaches for the safety of long term interim storage facilities dedicated to spent nuclear fuel (SF), high level waste (HLW) and other radioactive materials with prolonged storage regimes. It was also intended to discuss results of experiments and to identify necessary R and D to confirm safety of fuel and cask during the long-term storage. Safety authorities and their Technical Support Organisation (TSO), Fuel Cycle Facilities (FCF) operating organisations and international organisations were invited to share information on their approaches, practices and current developments. The workshop was organised in an opening session, three technical sessions, and a conclusion session. The technical sessions were focused on: - National approaches for long term interim storage facilities; - Safety requirements, regulatory framework and implementation issues; - Technical issues and operational experience, needs for R and D. Each session 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 as well as a summary of the results of the workshop with the text of the papers given and presentations made

Interim sanitary landfill groundwater monitoring report. 1996 Annual report

International Nuclear Information System (INIS)

Bagwell, L.A.

1997-01-01

Eight wells of the LFW series monitor groundwater quality in the Steed Pond Aquifer (Water Table) beneath the Interim Sanitary Landfill at the Savannah River Site. These wells are sampled semiannually to comply with the South Carolina Department of Health and Environmental Control Modified Municipal Solid Waste Permit 025500-1120 and as part of the SRS Groundwater Monitoring Program. Trichlorofluoromethane and 1,1,1-trichloroethane were elevated in one sidegradient well and one downgradient well during 1996. Zinc was elevated in three downgradient wells and also was detected in the associated laboratory blanks for two of those wells. Specific conductance was elevated in one background well and one sidegradient well. Barium and copper exceeded standards in one sidegradient well, and dichloromethane (a common laboratory contaminant) was elevated in another sidegradient well. Barium, copper, and dichloromethane were detected in the associated blanks for these wells, also. The groundwater flow direction in the Steed Pond Acquifer (Water Table) beneath the Interim Sanitary Landfill was to the southeast (universal transverse Mercator coordinates). The flow rate in this unit was approximately 210 ft/year during first quarter 1996 and 180 ft/yr during third quarter 1996

Interim Reliability Evaluation Program procedures guide

International Nuclear Information System (INIS)

Carlson, D.D.; Gallup, D.R.; Kolaczkowski, A.M.; Kolb, G.J.; Stack, D.W.; Lofgren, E.; Horton, W.H.; Lobner, P.R.

1983-01-01

This document presents procedures for conducting analyses of a scope similar to those performed in Phase II of the Interim Reliability Evaluation Program (IREP). It documents the current state of the art in performing the plant systems analysis portion of a probabilistic risk assessment. Insights gained into managing such an analysis are discussed. Step-by-step procedures and methodological guidance constitute the major portion of the document. While not to be viewed as a cookbook, the procedures set forth the principal steps in performing an IREP analysis. Guidance for resolving the problems encountered in previous analyses is offered. Numerous examples and representative products from previous analyses clarify the discussion

Application of NUREG/CR-5999 interim fatigue curves to selected nuclear power plant components

International Nuclear Information System (INIS)

Ware, A.G.; Morton, D.K.; Nitzel, M.E.

1995-03-01

Recent test data indicate that the effects of the light water reactor (LWR) environment could significantly reduce the fatigue resistance of materials used in the reactor coolant pressure boundary components of operating nuclear power plants. Argonne National Laboratory has developed interim fatigue curves based on test data simulating LWR conditions, and published them in NUREG/CR-5999. In order to assess the significance of these interim fatigue curves, fatigue evaluations of a sample of the components in the reactor coolant pressure boundary of LWRs were performed. The sample consists of components from facilities designed by each of the four U.S. nuclear steam supply system vendors. For each facility, six locations were studied, including two locations on the reactor pressure vessel. In addition, there are older vintage plants where components of the reactor coolant pressure boundary were designed to codes that did not require an explicit fatigue analysis of the components. In order to assess the fatigue resistance of the older vintage plants, an evaluation was also conducted on selected components of three of these plants. This report discusses the insights gained from the application of the interim fatigue curves to components of seven operating nuclear power plants

Interim safety evaluation report related to operation of Enrico Fermi Atomic Power Plant, Unit 2, Detroit Edison Company

International Nuclear Information System (INIS)

1977-09-01

This interim report summarizes the scope and results of the radiological safety review performed to date by the NRC staff with respect to the operating license phase for the Enrico Fermi Atomic Power Plant, Unit 2. The major effort was the review of the facility design and proposed operating procedures described in applicant's Final Safety Analysis Report. In the course of the review, several meetings were held with representatives of the applicant to discuss plant design, construction and proposed operation. Additional information was requested, which the applicant provided through Amendment 7 to the Final Safety Analysis Report. A chronology of the principal actions relating to the review of the application is attached as Appendix A to the report. The Final Safety Analysis Report and amendments thereto are available for public inspection at the Nuclear Regulatory Commission Public Document Room, 1717 H Street, N. W., Washington, D.C. and at Monroe County Library System, 3700 South Custer Road, Monroe, Michigan 48161

Development of a road materials database: Interim Report: 1st draft

CSIR Research Space (South Africa)

Jones, DJ

2003-03-01

Full Text Available The data required for a road materials database has been identified and a basic structure formulated. A set of Excel workbooks and associated worksheets has been developed as a foundation for the database and as an interim means of gathering test...

Interim Restorative Approach for the Management of Congenitally Missing Permanent Mandibular Incisors: Presentation of Three Cases

Directory of Open Access Journals (Sweden)

Prashanth Prakash

2011-01-01

Full Text Available Congenital missing of mandibular permanent incisors with retained primary incisors may jeopardize the esthetic appearance and psychological development of children, especially during the years of transition into adolescence. The retained primary teeth are necessary for the maintenance and normal development of alveolar bone, which in turn is essential for future definitive rehabilitation. In such situations, an interim restoration may be provided before any definitive treatment is given to comfort the young patient during this transition period. Interim restorations may include resin-modified additions to the existing teeth as well as more sophisticated restorations such as resin-retained bridge and removable partial dentures. However, this restoration differs for different clinical situations based on various factors such as age and patient compliance, and also consideration has to be given for the growth changes of the child. The aim of this present paper is to discuss the esthetic management of three cases with bilateral agenesis of permanent mandibular incisors and retained primary incisors with composite interim restoration.

Proceedings of the meeting on uranium exploration, mining and extraction

International Nuclear Information System (INIS)

1996-01-01

Meeting on uranium exploration, mining, and extraction is aimed to expedite information exchange among researchers from the National Atomic Energy Agency (BATAN), their international colleagues, the higher education institutions,and other interested scientific communities on the latest development on Kalan uranium minerals exploration, mining, and extraction. Nuclear Minerals Development Centre (PPBGN) roles in nuclear energy provision, the theme of the meeting, reflect current advancements of the Centre in fulfilling its major tasks and responsibilities. In order to assist PPBGN better to assume its roles and responsibilities, the meeting is expected to bring forth essential solutions for problems and difficulties relevant to PPBGN's activities. Hence, the scope of the meeting will be limited to discussion on the status of nuclear minerals exploration, mining, and extraction technologies in Indonesia as well as the related environmental and workplace safeties in uranium mining and milling. Ten technical papers were presented in meeting, including four topics on exploration status and technology, three subject matter on mining, two presentations on milling, and one paper on environmental and workplace safeties

Interim Sanitary Landfill Groundwater Monitoring Report. 1997 Annual Report

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-01-01

Eight wells of the LFW series monitor groundwater quality in the Steed Pond Aquifer (Water Table) beneath the Interim Sanitary Landfill at the Savannah River Site (SRS). These wells are sampled semiannually to comply with the South Carolina Department of Health and Environmental Control Modified Municipal Solid Waste Permit 025500-1120 (formerly dWP-087A) and as part of the SRS Groundwater Monitoring Program.

Landsat Science Team: 2017 Winter Meeting Summary

Science.gov (United States)

Schroeder, Todd A.; Loveland, Thomas; Wulder, Michael A.; Irons, James R.

2017-01-01

The summer meeting of the joint U.S. Geological Survey (USGS)-NASA Landsat Science Team (LST) was held July 26-28, 2016, at South Dakota State University (SDSU) in Brookings, SD. LST co-chair Tom Loveland [USGS’s Earth Resources Observation and Science Center (EROS)] and Kevin Kephart [SDSU] welcomed more than 80 participants to the three-day meeting. That attendance at such meetings continues to increase—likely due to the development of new data products and sensor systems—further highlights the growing interest in the Landsat program. The main objectives of this meeting were to provide a status update on Landsat 7 and 8, review team member research activities, and to begin identifying priorities for future Landsat missions.

Hazardous waste management programs; Florida: authorization for interim authorization phase I--Environmental Protection Agency. Notice of final determination.

Science.gov (United States)

1982-05-07

The State of Florida has applied for interim Authorization Phase I. EPA has reviewed Florida's application for Phase I and has determined that Florida's hazardous waste program is substantially equivalent to the Federal program covered by Phase I. The State of Florida is, hereby, granted Interim Authorization for Phase I to operate the State 's hazardous waste program, in lieu of the Federal program.

Students' interim literacies as a dynamic resource for teaching and ...

African Journals Online (AJOL)

This article explores the notion of 'interim literacies'by drawing on data from a research project which used linguistic and intertextual analysis of first year student writing in economics to investigate the intersection of academic discourse and student voice. This research has provided a rich set of data to illustrate the ways in ...

Summary report of consultants' meeting on IAEA international database on irradiated nuclear graphite properties

International Nuclear Information System (INIS)

Humbert, D.; Wickham, A.J.

2007-06-01

The '9th Meeting of the Technical Steering Committee for the International Database on Irradiated Nuclear Graphite Properties' was held on 26-27 March 2007 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)

Service level status-a new real-time status display for IT services

Energy Technology Data Exchange (ETDEWEB)

Lopienski, S [IT Department, FIO group CERN, European Organization for Nuclear Research, 1211 Geneve 23 (Switzerland)], E-mail: Sebastian.Lopienski@cern.ch

2008-07-15

Nowadays, IT departments provide, and people use, computing services of an increasingly heterogeneous nature. There is thus a growing need for a status display that groups these different services and reports their status and availability in a uniform way. The Service Level Status (SLS) system addresses these needs by providing a web-based display that dynamically shows availability, basic information and statistics about various IT services, as well as the dependencies between them. This paper first introduces the requirements SLS had to meet, and the main concepts behind it, like service availability and status, Key Performance Indicators (KPIs), sub/meta-services, and service dependencies. It then describes the SLS system architecture, and some interesting implementation details, such as the usage of XML Schemas. Since clear visualization of service availability and status is one of the main goals of SLS, emphasis is put on describing the intuitive web-based user interface.

Service level status-a new real-time status display for IT services

International Nuclear Information System (INIS)

Lopienski, S

2008-01-01

Nowadays, IT departments provide, and people use, computing services of an increasingly heterogeneous nature. There is thus a growing need for a status display that groups these different services and reports their status and availability in a uniform way. The Service Level Status (SLS) system addresses these needs by providing a web-based display that dynamically shows availability, basic information and statistics about various IT services, as well as the dependencies between them. This paper first introduces the requirements SLS had to meet, and the main concepts behind it, like service availability and status, Key Performance Indicators (KPIs), sub/meta-services, and service dependencies. It then describes the SLS system architecture, and some interesting implementation details, such as the usage of XML Schemas. Since clear visualization of service availability and status is one of the main goals of SLS, emphasis is put on describing the intuitive web-based user interface

Failsafe automation of Phase II clinical trial interim monitoring for stopping rules.

Science.gov (United States)

Day, Roger S

2010-02-01

In Phase II clinical trials in cancer, preventing the treatment of patients on a study when current data demonstrate that the treatment is insufficiently active or too toxic has obvious benefits, both in protecting patients and in reducing sponsor costs. Considerable efforts have gone into experimental designs for Phase II clinical trials with flexible sample size, usually implemented by early stopping rules. The intended benefits will not ensue, however, if the design is not followed. Despite the best intentions, failures can occur for many reasons. The main goal is to develop an automated system for interim monitoring, as a backup system supplementing the protocol team, to ensure that patients are protected. A secondary goal is to stimulate timely recording of patient assessments. We developed key concepts and performance needs, then designed, implemented, and deployed a software solution embedded in the clinical trials database system. The system has been in place since October 2007. One clinical trial tripped the automated monitor, resulting in e-mails that initiated statistician/investigator review in timely fashion. Several essential contributing activities still require human intervention, institutional policy decisions, and institutional commitment of resources. We believe that implementing the concepts presented here will provide greater assurance that interim monitoring plans are followed and that patients are protected from inadequate response or excessive toxicity. This approach may also facilitate wider acceptance and quicker implementation of new interim monitoring algorithms.

77 FR 76078 - Regular Board of Directors Sunshine Act Meeting

Science.gov (United States)

2012-12-26

..., DC 20005. STATUS: Open. CONTACT PERSON FOR MORE INFORMATION: Erica Hall, Assistant Corporate... Regular Board of Directors Meeting Minutes IV. Approval of the Finance, Budget & Program Committee Meeting... Corporate Secretary. [FR Doc. 2012-31163 Filed 12-21-12; 4:15 pm] BILLING CODE 7570-02-P ...

Both Mother and Infant Require a Vitamin D Supplement to Ensure That Infants’ Vitamin D Status Meets Current Guidelines

Directory of Open Access Journals (Sweden)

Fariba Aghajafari

2018-03-01

Full Text Available We examined the association between maternal vitamin D intake during breastfeeding with their infants’ vitamin D status in infants who did or did not receive vitamin D supplements to determine whether infant supplementation was sufficient. Using plasma from a subset of breastfed infants in the APrON (Alberta Pregnant Outcomes and Nutrition cohort, vitamin D status was measured by liquid chromatography-tandem mass spectrometry. Maternal and infants’ dietary data were obtained from APrON’s dietary questionnaires. The median maternal vitamin D intake was 665 International Units (IU/day, while 25% reported intakes below the recommended 400 IU/day. Of the 224 infants in the cohort, 72% were exclusively breastfed, and 90% were receiving vitamin D supplements. Infants’ median 25(OHD was 96.0 nmol/L (interquartile ranges (IQR 77.6–116.2, and 25% had 25(OHD < 75 nmol/L. An adjusted linear regression model showed that, with a 100 IU increase in maternal vitamin D intake, infants’ 25(OHD increased by 0.9 nmol/L controlling for race, season, mid-pregnancy maternal 25(OHD, birthweight, and whether the infant received daily vitamin D supplement (β = 0.008, 95% confidence interval (CI 0.002, 0.13. These results suggest that, to ensure infant optimal vitamin D status, not only do infants require a supplement, but women also need to meet current recommended vitamin D intake during breastfeeding.

Both Mother and Infant Require a Vitamin D Supplement to Ensure That Infants’ Vitamin D Status Meets Current Guidelines

Science.gov (United States)

Weinberg, Amy R.; Letourneau, Nicole

2018-01-01

We examined the association between maternal vitamin D intake during breastfeeding with their infants’ vitamin D status in infants who did or did not receive vitamin D supplements to determine whether infant supplementation was sufficient. Using plasma from a subset of breastfed infants in the APrON (Alberta Pregnant Outcomes and Nutrition) cohort, vitamin D status was measured by liquid chromatography-tandem mass spectrometry. Maternal and infants’ dietary data were obtained from APrON’s dietary questionnaires. The median maternal vitamin D intake was 665 International Units (IU)/day, while 25% reported intakes below the recommended 400 IU/day. Of the 224 infants in the cohort, 72% were exclusively breastfed, and 90% were receiving vitamin D supplements. Infants’ median 25(OH)D was 96.0 nmol/L (interquartile ranges (IQR) 77.6–116.2), and 25% had 25(OH)D < 75 nmol/L. An adjusted linear regression model showed that, with a 100 IU increase in maternal vitamin D intake, infants’ 25(OH)D increased by 0.9 nmol/L controlling for race, season, mid-pregnancy maternal 25(OH)D, birthweight, and whether the infant received daily vitamin D supplement (β = 0.008, 95% confidence interval (CI) 0.002, 0.13). These results suggest that, to ensure infant optimal vitamin D status, not only do infants require a supplement, but women also need to meet current recommended vitamin D intake during breastfeeding. PMID:29596362

Scientific criteria document for the development of an interim provincial water quality objective for aniline

Energy Technology Data Exchange (ETDEWEB)

Angelow, R.V.; Bazinet, N.

1996-11-01

The purpose of this document is to develop an interim provincial water quality objective for aniline for the protection of aquatic life in Ontario. It reviews the sources of aniline in the environment, its environmental fate and properties, acute and chronic toxicity as determined from results reported in the literature on toxicity tests using vertebrates and invertebrates, the bioaccumulation of aniline in the environment, mutagenic effects, and threshold aniline concentrations affecting fish odour and taste. The document then explains the derivation of the interim water quality objective. Water quality criteria for aniline developed in other jurisdictions are noted.

Continuous Covariate Imbalance and Conditional Power for Clinical Trial Interim Analyses

Science.gov (United States)

Ciolino, Jody D.; Martin, Renee' H.; Zhao, Wenle; Jauch, Edward C.; Hill, Michael D.; Palesch, Yuko Y.

2014-01-01

Oftentimes valid statistical analyses for clinical trials involve adjustment for known influential covariates, regardless of imbalance observed in these covariates at baseline across treatment groups. Thus, it must be the case that valid interim analyses also properly adjust for these covariates. There are situations, however, in which covariate adjustment is not possible, not planned, or simply carries less merit as it makes inferences less generalizable and less intuitive. In this case, covariate imbalance between treatment groups can have a substantial effect on both interim and final primary outcome analyses. This paper illustrates the effect of influential continuous baseline covariate imbalance on unadjusted conditional power (CP), and thus, on trial decisions based on futility stopping bounds. The robustness of the relationship is illustrated for normal, skewed, and bimodal continuous baseline covariates that are related to a normally distributed primary outcome. Results suggest that unadjusted CP calculations in the presence of influential covariate imbalance require careful interpretation and evaluation. PMID:24607294

Reinforcement of a PMMA resin for fixed interim prostheses with nanodiamonds.

Science.gov (United States)

Protopapa, Popi; Kontonasaki, Eleana; Bikiaris, Dimitrios; Paraskevopoulos, Konstantinos M; Koidis, Petros

2011-01-01

The aim of this study was to investigate the possible reinforcement of Nanodiamonds (ND) in a PMMA resin for fixed interim restorations. The fracture toughness (K(Ic)), impact strength and the dynamic thermomechanical properties (T(g), E´, E´´, tanδ) of a series of PMMA-ND nanocomposites with different amounts of ND were evaluated. The fracture toughness increased as the ND percentage increased up to 0.38% wt but a greater amount of ND induced a decrease in K(Ic). Impact strength and Young's modulus were also increased by increasing nanoparticles content, indicating the reinforcing effect of ND. Dynamic mechanical properties were also affected. By increasing the ND content an increase of storage modulus was recorded, while glass transition was shifted at higher temperatures. Under the limitations of this study, it can be suggested that reinforcing PMMA with ND nanoparticles -especially at low concentrations- may increase the overall performance of fixed interim prostheses.

Interim reliability evaluation program (IREP)

International Nuclear Information System (INIS)

Carlson, D.D.; Murphy, J.A.

1981-01-01

The Interim Reliability Evaluation Program (IREP), sponsored by the Office of Nuclear Regulatory Research of the US Nuclear Regulatory Commission, is currently applying probabilistic risk analysis techniques to two PWR and two BWR type power plants. Emphasis was placed on the systems analysis portion of the risk assessment, as opposed to accident phenomenology or consequence analysis, since the identification of risk significant plant features was of primary interest. Traditional event tree/fault tree modeling was used for the analysis. However, the study involved a more thorough investigation of transient initiators and of support system faults than studies in the past and substantially improved techniques were used to quantify accident sequence frequencies. This study also attempted to quantify the potential for operator recovery actions in the course of each significant accident

Interim Measures Work Plan Expanded Bioventing System SWMU 55 (IRP Site FT-03)

National Research Council Canada - National Science Library

1997-01-01

This interim measures work plan (IMWP) presents the scope for an expanded bioventing system to conduct in situ treatment of the remaining fuel-contaminated soils at solid waste management unit (SWMU...

Climate change : we are at risk : interim report

International Nuclear Information System (INIS)

Oliver, D.; Wiebe, J.

2003-06-01

Between November 2002 and May 2003 the Standing Senate Committee on Agriculture and Forestry travelled across Canada to hear the views of farmer organizations, rural associations, ecotourism groups and environmental organizations regarding concerns about climate change and the impact it may have on the agriculture and forestry sectors and rural communities. The Committee also examined potential adaptation strategies focusing on primary production, practices, technologies, ecosystems and other related areas. Farmers and forest operators are already facing changes in market conditions, domestic regulations, trade policies and technology. This interim report expressed the concerns of farmers and forest operators. It includes a review of the Saguenay flood of 1996, the Red River flood of 1997, the ice storm of 1998, and droughts since 1999. It also includes a discussion on climate change and its biophysical and economic effects on agriculture, forestry, water resources, rural communities, and Aboriginal communities. This interim report also briefly outlines the Kyoto Protocol, the emissions trading system, and the decarbonization of global energy systems. It emphasized the need for integrated research and government policies and programs that encourage adaptation to climate change. The final report will be released in October 2003 and will provide specific recommendations to ensure that Canada responds to the concerns of farmers and forest operators and to ensure continued prosperity in these sectors. refs., figs

Climate change : we are at risk : interim report

Energy Technology Data Exchange (ETDEWEB)

Oliver, D.; Wiebe, J.

2003-06-01

Between November 2002 and May 2003 the Standing Senate Committee on Agriculture and Forestry travelled across Canada to hear the views of farmer organizations, rural associations, ecotourism groups and environmental organizations regarding concerns about climate change and the impact it may have on the agriculture and forestry sectors and rural communities. The Committee also examined potential adaptation strategies focusing on primary production, practices, technologies, ecosystems and other related areas. Farmers and forest operators are already facing changes in market conditions, domestic regulations, trade policies and technology. This interim report expressed the concerns of farmers and forest operators. It includes a review of the Saguenay flood of 1996, the Red River flood of 1997, the ice storm of 1998, and droughts since 1999. It also includes a discussion on climate change and its biophysical and economic effects on agriculture, forestry, water resources, rural communities, and Aboriginal communities. This interim report also briefly outlines the Kyoto Protocol, the emissions trading system, and the decarbonization of global energy systems. It emphasized the need for integrated research and government policies and programs that encourage adaptation to climate change. The final report will be released in October 2003 and will provide specific recommendations to ensure that Canada responds to the concerns of farmers and forest operators and to ensure continued prosperity in these sectors. refs., figs.

MANAGEMENT BOARD MEETING OF 28 MAY 2001

CERN Multimedia

2001-01-01

Report on the Outcome of TREF's May Meeting J. van der Boon, Director of Administration, briefly reported on the outcome of TREF's first meeting of the year on 18 May. In the framework of follow-up to the 2000 five-yearly review, the Forum had heard status reports on preparations for the implementation of the new career structure on 1 September 2001 and on the introduction of long-term care provisions, and had examined an information document concerning the 0.3% discrepancy in the net salary adjustment on 1 January 2001. Following discussion, it had recommended that a proposal to correct the discrepancy, backdated to 1 January, be submitted to the Finance Committee at its next meeting on 13 June. The Forum had also discussed a set of proposed amendments to the tenth edition of the Staff Rules and Regulations, essentially relating to the implementation of the new career structure and to terminology, as well as a status report on voluntary programmes (Saved Leave, Progressive Retirement and Part-Time Work as a ...

On the pathway towards disposal. The need for long-term interim storage of high-level nuclear waste

International Nuclear Information System (INIS)

Budelmann, Harald; Koehnke, Dennis; Reichardt, Manuel

2017-01-01

The disposal of spent nuclear fuel is a still unsolved problem with social, ethical, economical, ecological and political dimensions. The stagnating decision process on the final repository concept in several countries has the consequence of the inclusion of long-term interim storage into the disposal concept. The contribution discusses several approaches. This opens the question whether the long-term interim storage is a matter of delaying tactic or a pragmatic solution on the way to a final repository.

IAEA International Database on Irradiated Nuclear Graphite Properties. 7th meeting of the Technical Steering Committee

International Nuclear Information System (INIS)

Humbert, D.; Wickham, A.J.

2005-06-01

This report summarizes the Consultant Meeting '7th Meeting of the Technical Steering Committee for the International Database on Irradiated Nuclear Graphite Properties' held on 16-17 March 2005 at the IAEA Headquarters, Vienna, Austria. 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 to make recommendations for actions for the next year. The purposes of the meeting were fully met. This report contains the current status of the identified actions as well as a summary of the recommendations on enhancements to the database. (author)

IAEA International Database on Irradiated Nuclear Graphite Properties. 6th meeting of the Technical Steering Committee

International Nuclear Information System (INIS)

Humbert, D.; Wickham, A.J.

2004-12-01

This report summarizes the Consultant Meeting 6th Meeting of the Technical Steering Committee for the International Database on Irradiated Nuclear Graphite Properties' held on 16-17 September 2004 at Plas Tan-Y-Bwlch, Maentwrog, Gwynedd, UK. 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 to make recommendations for actions for the next year. The purposes of the meeting were fully met. This report contains the current status of the identified actions as well as a summary of the recommendations on enhancements to the database. (author)

High Temperature Materials Interim Data Qualification Report

International Nuclear Information System (INIS)

Lybeck, Nancy

2010-01-01

Projects for the very high temperature reactor (VHTR) Technology Development Office provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR program has established the NGNP Data Management and Analysis System (NDMAS) to ensure that VHTR data are qualified for use, stored in a readily accessible electronic form, and analyzed to extract useful results. This document focuses on the first NDMAS objective. It describes the High Temperature Materials characterization data stream, the processing of these data within NDMAS, and reports the interim FY2010 qualification status of the data. Data qualification activities within NDMAS for specific types of data are determined by the data qualification category assigned by the data generator. The High Temperature Materials data are being collected under NQA-1 guidelines, and will be qualified data. For NQA-1 qualified data, the qualification activities include: (1) capture testing, to confirm that the data stored within NDMAS are identical to the raw data supplied, (2) accuracy testing to confirm that the data are an accurate representation of the system or object being measured, and (3) documenting that the data were collected under an NQA-1 or equivalent Quality Assurance program. Currently, data from two test series within the High Temperature Materials data stream have been entered into the NDMAS vault: (1) Tensile Tests for Sm (i.e., Allowable Stress) Confirmatory Testing - 1,403,994 records have been inserted into the NDMAS database. Capture testing is in process. (2) Creep-Fatigue Testing to Support Determination of Creep-Fatigue Interaction Diagram - 918,854 records have been processed and inserted into the NDMAS database. Capture testing is in process.

ACCU MEETING

CERN Multimedia

2007-01-01

DRAFT Agenda for the meeting to be held on Wednesday 13 June 2007 at 9:15 a.m. in room 60-6-002 1.\tChairman’s remarks 6.\tDosimetry at CERN 2.\tAdoption of the agenda 7.\tStatus of collaborative tools at CERN 3.\tMinutes of the previous meeting 8.\tReports from ACCU representatives on other committees 4.\tMatters arising 9.\tUsers’ Office newss 5.\tNews from the CERN Management 10.\tAny Other Business 11.\tAgenda for the next meeting Anyone wishing to raise any points under item 10 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Norway G. Løvhøiden (73176) Belgium G. Wilquet (74664) Poland M. Witek (78967) Bulgaria Portugal...

Interim Hanford Waste Management Technology Plan

International Nuclear Information System (INIS)

1985-09-01

The Interim Hanford Waste Management Technology Plan (HWMTP) is a companion document to the Interim Hanford Waste Management Plan (HWMP). A reference plan for management and disposal of all existing and certain projected future radioactive Hanford Site Defense Wastes (HSDW) is described and discussed in the HWMP. Implementation of the reference plan requires that various open technical issues be satisfactorily resolved. The principal purpose of the HWMTP is to present detailed descriptions of the technology which must be developed to close each of the technical issues associated with the reference plan identified in the HWMP. If alternative plans are followed, however, technology development efforts including costs and schedules must be changed accordingly. Technical issues addressed in the HWMTP and HWMP are those which relate to disposal of single-shell tank wastes, contaminated soil sites, solid waste burial sites, double-shell tank wastes, encapsulated 137 CsCl and 90 SrF 2 , stored and new solid transuranic (TRU) wastes, and miscellaneous wastes such as contaminated sodium metal. Among the high priority issues to be resolved are characterization of various wastes including early determination of the TRU content of future cladding removal wastes; completion of development of vitrification (Hanford Waste Vitrification Plant) and grout technology; control of subsidence in buried waste sites; and development of criteria and standards including performance assessments of systems proposed for disposal of HSDW. Estimates of the technology costs shown in this report are made on the basis that all identified tasks for all issues associated with the reference disposal plan must be performed. Elimination of, consolidation of, or reduction in the scope of individual tasks will, of course, be reflected in corresponding reduction of overall technology costs

Interim Policy Options for Commercialization of Solar Heating and Cooling Systems.

Science.gov (United States)

Bezdek, Roger

This interim report reviews the major incentive policy options available to accelerate market penetration of solar heating and cooling (SHAC) systems. Feasible policy options designed to overcome existing barriers to commercial acceptance and market penetration are identified and evaluated. The report is divided into seven sections, each dealing…

Safety evaluation for the interim stabilization of Tank 241-C-103

Energy Technology Data Exchange (ETDEWEB)

Geschke, G.R.

1995-03-01

This document provides the basis for interim stabilization of tank 241-C-103. The document covers the removal of the organic liquid layer and the aqueous supernatant from tank 241-C-103. Hazards are identified, consequences are calculated and controls to mitigate or prevent potential accidents are developed.

Safety evaluation for the interim stabilization of Tank 241-C-103

International Nuclear Information System (INIS)

Geschke, G.R.

1995-03-01

This document provides the basis for interim stabilization of tank 241-C-103. The document covers the removal of the organic liquid layer and the aqueous supernatant from tank 241-C-103. Hazards are identified, consequences are calculated and controls to mitigate or prevent potential accidents are developed

76 FR 40365 - Sunshine Act Meeting

Science.gov (United States)

2011-07-08

... Room, Washington, DC. STATUS: Part of the meeting will be in Open Session and the remainder of the... Financial Responsibility Requirements (Performance). Closed Session 1. Discussion of Transpacific... Discussion of the Reconstruction Proceedings and Chapter 15 Bankruptcy Petition of The Containership Company...

400-MWe Consolidated Nuclear Steam System (CNSS). 1200-MWt Phase 2A interim studies

International Nuclear Information System (INIS)

1978-09-01

The Phase 2A interim studies of the Consolidated Nuclear Steam System (CNSS) consisted of a number of separate task studies addressing the design concepts developed during the Phase 1 study reported in BAW--1445. The purpose of the interim studies was to better establish overall concept feasibility from both a hardware and economic standpoint, to make modification and additions to the design where appropriate, and to understand and reduce the technical risks in critical areas of the design. The work on these task studies included input from Barberton, Mt. Vernon, and the Alliance Research Center as well as United Engineers and Constructors (UE and C). The UE and C work was carried out under a separate DOE contract

Annex D-200 Area Interim Storage Area Final Safety Analysis Report [FSAR] [Section 1 and 2

International Nuclear Information System (INIS)

CARRELL, R.D.

2002-01-01

The 200 Area Interim Storage Area (200 Area ISA) at the Hanford Site provides for the interim storage of non-defense reactor spent nuclear fuel (SNF) housed in aboveground dry cask storage systems. The 200 Area ISA is a relatively simple facility consisting of a boundary fence with gates, perimeter lighting, and concrete and gravel pads on which to place the dry storage casks. The fence supports safeguards and security and establishes a radiation protection buffer zone. The 200 Area ISA is nominally 200,000 ft 2 and is located west of the Canister Storage Building (CSB). Interim storage at the 200 Area ISA is intended for a period of up to 40 years until the materials are shipped off-site to a disposal facility. This Final Safety Analysis Report (FSAR) does not address removal from storage or shipment from the 200 Area ISA. Three different SNF types contained in three different dry cask storage systems are to be stored at the 200 Area ISA, as follows: (1) Fast Flux Test Facility Fuel--Fifty-three interim storage casks (ISC), each holding a core component container (CCC), will be used to store the Fast Flux Test Facility (FFTF) SNF currently in the 400 Area. (2) Neutron Radiography Facility (NRF) TRIGA'--One Rad-Vault' container will store two DOT-6M3 containers and six NRF TRIGA casks currently stored in the 400 Area. (3) Commercial Light Water Reactor Fuel--Six International Standards Organization (ISO) containers, each holding a NAC-I cask4 with an inner commercial light water reactor (LWR) canister, will be used for commercial LWR SNF from the 300 Area. An aboveground dry cask storage location is necessary for the spent fuel because the current storage facilities are being shut down and deactivated. The spent fuel is being transferred to interim storage because there is no permanent repository storage currently available

Data Analysis of GPM Constellation Satellites-IMERG and ERA-Interim precipitation products over West of Iran

Science.gov (United States)

Sharifi, Ehsan; Steinacker, Reinhold; Saghafian, Bahram

2016-04-01

Precipitation is a critical component of the Earth's hydrological cycle. The primary requirement in precipitation measurement is to know where and how much precipitation is falling at any given time. Especially in data sparse regions with insufficient radar coverage, satellite information can provide a spatial and temporal context. Nonetheless, evaluation of satellite precipitation is essential prior to operational use. This is why many previous studies are devoted to the validation of satellite estimation. Accurate quantitative precipitation estimation over mountainous basins is of great importance because of their susceptibility to hazards. In situ observations over mountainous areas are mostly limited, but currently available satellite precipitation products can potentially provide the precipitation estimation needed for meteorological and hydrological applications. One of the newest and blended methods that use multi-satellites and multi-sensors has been developed for estimating global precipitation. The considered data set known as Integrated Multi-satellitE Retrievals (IMERG) for GPM (Global Precipitation Measurement) is routinely produced by the GPM constellation satellites. Moreover, recent efforts have been put into the improvement of the precipitation products derived from reanalysis systems, which has led to significant progress. One of the best and a worldwide used model is developed by the European Centre for Medium Range Weather Forecasts (ECMWF). They have produced global reanalysis daily precipitation, known as ERA-Interim. This study has evaluated one year of precipitation data from the GPM-IMERG and ERA-Interim reanalysis daily time series over West of Iran. IMERG and ERA-Interim yield underestimate the observed values while IMERG underestimated slightly and performed better when precipitation is greater than 10mm. Furthermore, with respect to evaluation of probability of detection (POD), threat score (TS), false alarm ratio (FAR) and probability

Interim Storage of Spent Nuclear Fuel before Final Disposal in Germany - Regulator's view

International Nuclear Information System (INIS)

Arens, G.; Goetz, Ch.; Geupel, Sandra; Gmal, B.; Mester, W.

2014-01-01

For spent nuclear fuel management in Germany the concept of dry interim storage in dual purpose casks before direct disposal is applied. The Federal Office for Radiation Protection (BfS) is the competent authority for licensing of interim storage facilities. The competent authority for surveillance of operation is the responsible authority of the respective federal state (Land). Currently operation licenses for storage facilities have been granted for a storage time of 40 years and are based on safety demonstrations for all safety issues as safe enclosure, shielding, sub-criticality and decay heat removal under consideration of operation conditions. In addition, transportability of the casks for the whole storage period has to be provided. Due to current delay in site selection and exploration of a disposal site, an extension of the storage time beyond 40 years could be needed. This will cause appropriate actions by the licensee and the competent authorities as well. A brief description of the regulatory base of licensing and surveillance of interim storage is given from the regulators view. Furthermore the current planning for final disposal of spent nuclear fuel and high level waste and its interconnections between storage and disposal concepts are shortly explained. Finally the relevant aspects for licensing of extended storage time beyond 40 years will be discussed. Current activities on this issue, which have been initiated by the Federal Government, will be addressed. On the regulatory side a review and amendment of the safety guideline for interim storage of spent fuel has been performed and the procedure of periodic safety review is being implemented. A guideline for implementing an ageing management programme is available in a draft version. Regarding safety of long term storage a study focussing on the identification and evaluation of long term effects as well as gaps of knowledge has been finished in 2010. A continuation and update is currently underway

Technical minutes of the eighth INDC meeting, Vienna, 6 - 10 October 1975

International Nuclear Information System (INIS)

Benzi, V.

1977-01-01

Neutron nuclear data (report on 11th four centre meeting; additional information from neutron data centres other than NDS; two years publication cycle of CINDA; international exchange and assessment of use of evaluated data); non-neutron nuclear data (progress reports on activities, services and coordination of ''non-neutron'' nuclear data centres and groups; report on meeting on charged particle nuclear data (CPND) for applications; discussion on recommendations from ''non-neutron'' nuclear data meetings April/May 1974, including plans for 1976 meetings); coordination of nuclear data activities (status of development of regional nuclear data centres and national data committees; neutron data for reactor dosimetry; FPND newsletter; WRENDA for fission, fusion and safeguards; nuclear data measurements in developing countries; status and NDS targets and samples program); progress reports on nuclear data measurements, facilities and evaluations (additions to submitted progress reports; reports on nuclear data activities in countries not represented on INDC); reports of Technical and Ad-hoc sub-committees; reports of policy sub-committees; meetings

STANDING CONCERTATION COMMITTEE ORDINARY MEETING HELD ON 26 MAY AND 2 JUNE 1999

CERN Multimedia

1999-01-01

Original: FrenchThe meeting was devoted essentially to examining the various items listed below:TREF meeting on 28 May 1999The items on this meeting's agenda were: a status report on the voluntary programmes, the Forum's work planning and in particular preparation for the five-yearly review of financial conditions, and the scope of application of Article R IV 1.25 of the Staff Regulations concerning the reimbursement of taxes to certain categories of students and associates.At the SCC's meeting on 26 May, the Committee members finalised the documents to be submitted to TREF, in particular the Forum's work planning and preparation for the five-yearly review.At its meeting on 2 June, the SCC took note of the results of TREF's meeting and the preparations for the next Finance Committee meeting and Council session in June:Status report on the voluntary programmesThe Forum had regarded the results of these programmes as very positive, especially those of the RSL Programme, which had made it possible to open 36 pos...

Proposed plan for interim remedial measures at the 100-KR-1 Operable Unit. Revision 1

International Nuclear Information System (INIS)

1995-09-01

This proposed plan identifies the preferred alternative for interim remedial measures for remedial action of radioactive liquid waste disposal sites that include contaminated soils and structures at the 100-KR-1 Operable Unit, located at the Hanford Site. It also summarizes other remedial alternatives evaluated for interim remedial measures in this Operable Unit. The intent of interim remedial measures is to speed up actions to address contaminated areas that pose potential threats to human health and the environment. This proposed plan is being issued by the US Environmental Protection Agency (EPA), the lead regulatory agency; the Washington State Department of Ecology (Ecology), the support regulatory agency; and the US Department of Energy (DOE), the responsible agency. The EPA, Ecology, and the DOE are issuing this proposed plan as part of their public participation responsibilities under Section 117(a) of the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA), commonly known as the ''Superfund Law.'' This proposed plan is intended to be a fact sheet for public review which briefly describes the remedial alternatives analyzed, identifies a preferred alternative, and summarizes the information relied upon to recommend the preferred alternative

Interim policy on establishment and operation of internet open, anonymous information servers and services

OpenAIRE

Acting Dean of Computer and Information Services

1995-01-01

Purpose. To establish interim NPS general policy regarding establishment and operation of Open, Anonymous Information Servers and Services, such as World Wide Web (http), Gopher, Anonymous FTP, etc...

77 FR 67860 - Sunshine Act Meeting

Science.gov (United States)

2012-11-14

.... Performance and Compensation 5. Report of the Audit, Risk, and Regulation Committee A. Assistant Corporate... management will answer questions from the news media following the Board meeting. STATUS: Open. Agenda..., Rates, and Portfolio Committee A. Financial Performance Update B. Section 13 Tax Equivalent Payments C...

77 FR 23248 - Sunshine Act Meeting

Science.gov (United States)

2012-04-18

... Financial Company. Memorandum and resolution re: Final Rule under Dodd-Frank Section 203(e) Providing for the Treatment of a Mutual Insurance Holding Company as an Insurance Company. Personnel Matters...' Meetings. Summary reports, status reports, reports of the Office of Inspector General, and reports of...

FedEx Gasoline Hybrid Electric Delivery Truck Evaluation: 6-Month Interim Report

Energy Technology Data Exchange (ETDEWEB)

Barnitt, R.

2010-05-01

This interim report presents partial (six months) results for a technology evaluation of gasoline hybrid electric parcel delivery trucks operated by FedEx in and around Los Angeles, CA. A 12 month in-use technology evaluation comparing in-use fuel economy and maintenance costs of GHEVs and comparative diesel parcel delivery trucks was started in April 2009. Comparison data was collected and analyzed for in-use fuel economy and fuel costs, maintenance costs, total operating costs, and vehicle uptime. In addition, this interim report presents results of parcel delivery drive cycle collection and analysis activities as well as emissions and fuel economy results of chassis dynamometer testing of a gHEV and a comparative diesel truck at the National Renewable Energy Laboratory's (NREL) ReFUEL laboratory. A final report will be issued when 12 months of in-use data have been collected and analyzed.

77 FR 34093 - NASA Advisory Council; Science Committee; Heliophysics Subcommittee; Meeting.

Science.gov (United States)

2012-06-08

... Division Overview and Program Status --Flight Mission Status Report --Heliophysics Science Performance... visa in addition to providing the following information no less than 10 working days prior to the meeting: Full name; gender; date/place of birth; citizenship; visa information (number, type, expiration...

T-TY Tank Farm Interim Surface Barrier Demonstration - Vadose Zone Monitoring Plan

International Nuclear Information System (INIS)

Zhang, Z.F.; Strickland, Christopher E.; Field, Jim G.; Parker, Danny L.

2010-01-01

The Hanford Site has 149 underground single-shell tanks that store hazardous radioactive waste. Many of these tanks and their associated infrastructure (e.g., pipelines, diversion boxes) have leaked. Some of the leaked waste has entered the groundwater. The largest known leak occurred from the T-106 Tank of the 241-T Tank Farm in 1973. Five tanks are assumed to have leaked in the TY Farm. Many of the contaminants from those leaks still reside within the vadose zone within the T and TY Tank Farms. The Department of Energy's Office of River Protection seeks to minimize the movement of these contaminant plumes by placing interim barriers on the ground surface. Such barriers are expected to prevent infiltrating water from reaching the plumes and moving them further. The soil water regime is monitored to determine the effectiveness of the interim surface barriers. Soil-water content and water pressure are monitored using off-the-shelf equipment that can be installed by the hydraulic hammer technique. Four instrument nests were installed in the T Farm in fiscal year (FY) 2006 and FY2007; two nests were installed in the TY Farm in FY2010. Each instrument nest contains a neutron probe access tube, a capacitance probe, and four heat-dissipation units. A meteorological station has been installed at the north side of the fence of the T Farm. This document summarizes the monitoring methods, the instrument calibration and installation, and the vadose zone monitoring plan for interim barriers in T farm and TY Farm.

78 FR 70320 - Government in the Sunshine Act Meeting Notice

Science.gov (United States)

2013-11-25

... carried over to the agenda of the following meeting. By order of the Commission: Issued: November 21, 2013. William R. Bishop, Supervisory Hearings and Information Officer. [FR Doc. 2013-28299 Filed 11-21-13; 11:15.... STATUS: Open to the public. MATTERS TO BE CONSIDERED: 1. Agendas for future meetings: None 2. Minutes...

Minutes of the fifth annual meeting of the panel on reference nuclear data

International Nuclear Information System (INIS)

Burrows, T.W.; Coyne, J.J.; Brenner, D.S.

1981-04-01

The minutes include: approval of agenda and minutes of the fourth meeting; elections; reactor physics data needs; fusion data needs; biomedical data needs; status of international and national cooperation; status and availability of data files; status of transfer of responsibilities from NDP to NNDC; status of publications; on-line data base systems; and summary of recommendations and actions

Modern trends in ion source development for low-energy accelerators. Final report of a consultants' meeting

International Nuclear Information System (INIS)

1998-01-01

The IAEA consultative meeting was held to review the status of ion source development for accelerators having output energies less than 100 MeV (low-energy accelerators). Terms of reference for the meeting were to review the status of ion source development for several different types of low-energy accelerators (Van de Graaff, cyclotron, sealed-tube neutron generator, ion implanter, etc.) and to highlight any recent advances in this field. Individual abstracts were prepared for 5 papers presented at this meeting

Evaluation of Hose in Hose Transfer Line Service Life for Hanford's Interim Stabilization Program

Energy Technology Data Exchange (ETDEWEB)

TORRES, T.D.

2000-08-24

RPP-6153, Engineering Task Plan for Hose-in-Hose Transfer System for the Interim Stabilization Program, defines the programmatic goals, functional requirements, and technical criteria for the development and subsequent installation of transfer line equipment to support Hanford's Interim Stabilization Program. RPP-6028, Specification for Hose in Hose Transfer Lines for Hanford's Interim Stabilization Program, has been issued to define the specific requirements for the design, manufacture, and verification of transfer line assemblies for specific waste transfer applications. Included in RPP-6028 are tables defining the chemical constituents of concern to which transfer lines will be exposed. Current Interim Stabilization Program planning forecasts that the at-grade transfer lines will be required to convey pumpable waste for as much as three years after commissioning. Prudent engineering dictates that the equipment placed in service have a working life in excess of this forecasted time period, with some margin to allow for future adjustments to the planned schedule. This document evaluates the effective service life of the Hose-in-Hose Transfer Lines, based on information submitted by the manufacturer and published literature. The effective service life of transfer line assemblies is a function of several factors. Foremost among these are process fluid characteristics, ambient environmental conditions, and the manufacturer's stated shelf life. This evaluation examines the manufacturer's certification of shelf life, the manufacturer's certifications of chemical compatibility with waste, and published literature on the effects of exposure to ionizing radiation on the mechanical properties of elastomeric materials to evaluate transfer line service life.

Coordination of groundwater activities in the 100 N Area

International Nuclear Information System (INIS)

Hartman, M.J.

1995-09-01

The initiation of the N Springs Expedited Response Action (ERA) in the 100 N Area will affect the groundwater monitoring networks of two Resource Conservation and Recovery Act of 1976 (RCRA) units. The 1301-N and 325-N facilities are treatment, storage, or disposal (TSD) units that have been monitored under RCRA since 1987. In September 1994, the Washington State Department of Ecology issued an action memorandum, instructing the US Department of Energy (DOE) to take the action. The planned pump-and-treat system will preclude meeting the specific objectives of interim-status RCRA groundwater monitoring representative samples and detect adverse impacts of the TSD units on. However, under RCRA final-status requirements, which will be implemented in 1999, corrective action for groundwater contamination will probably be required. The US Environmental Protection Agency (EPA) has declared parity between RCRA corrective action and Comprehensive Environmental Response, Compensation, and Liability Act of 1980 remedial action decisions. The 1301-N and 1325-N facilities are still in interim-status and therefore are not in the category of ''RCRA corrective action.'' However, DOE's position is that parity exists between RCRA and the ERA because RCRA corrective action will almost certainly be required in the future

Clinical Neuropathology practice news 1-2014: Pyrosequencing meets clinical and analytical performance criteria for routine testing of MGMT promoter methylation status in glioblastoma

Science.gov (United States)

Preusser, Matthias; Berghoff, Anna S.; Manzl, Claudia; Filipits, Martin; Weinhäusel, Andreas; Pulverer, Walter; Dieckmann, Karin; Widhalm, Georg; Wöhrer, Adelheid; Knosp, Engelbert; Marosi, Christine; Hainfellner, Johannes A.

2014-01-01

Testing of the MGMT promoter methylation status in glioblastoma is relevant for clinical decision making and research applications. Two recent and independent phase III therapy trials confirmed a prognostic and predictive value of the MGMT promoter methylation status in elderly glioblastoma patients. Several methods for MGMT promoter methylation testing have been proposed, but seem to be of limited test reliability. Therefore, and also due to feasibility reasons, translation of MGMT methylation testing into routine use has been protracted so far. Pyrosequencing after prior DNA bisulfite modification has emerged as a reliable, accurate, fast and easy-to-use method for MGMT promoter methylation testing in tumor tissues (including formalin-fixed and paraffin-embedded samples). We performed an intra- and inter-laboratory ring trial which demonstrates a high analytical performance of this technique. Thus, pyrosequencing-based assessment of MGMT promoter methylation status in glioblastoma meets the criteria of high analytical test performance and can be recommended for clinical application, provided that strict quality control is performed. Our article summarizes clinical indications, practical instructions and open issues for MGMT promoter methylation testing in glioblastoma using pyrosequencing. PMID:24359605

Nuclear waste: Is there a need for federal interim storage

International Nuclear Information System (INIS)

1989-01-01

The Congress created the Monitored Retrievable Storage Review Commission to provide a report on the need for a Federal monitored retrievable storage facility (MRS) as part of the Nation's nuclear waste management system. The Commission concludes that the MRS as presently described in the law, which links the capacity and schedule of operation of the MRS to a permanent geologic repository, cannot be justified. The Commission finds, however, that while no single factor would favor an MRS over the No-MRS option, cumulatively the advantages of an MRS would justify the building of an MRS if: there were no linkages between the MRS and the repository; the MRS could be constructed at an early date; and the opening of the repository were delayed considerably beyond its presently scheduled date of operation. The Commission therefore recommends that the Congress take the following actions: Authorize construction of a Federal Emergency Storage facility with a capacity limit of 2,000 metric tons of uranium; Authorize construction of a User-Funded Interim Storage facility with a capacity limit of 5,000 metric tons of uranium; Reconsider the subject of interim storage by the year 2000

Status Report Jilin University

Energy Technology Data Exchange (ETDEWEB)

Dong, Yang; Huo Junde, E-mail: huojd@jlu.edu.cn

2013-08-15

Status of mass chain evaluation: Jilin University (JLU) group is responsible for nuclear structure and decay data evaluation of mass chains: A=52, 53, 54, 55, 56, and 63. (1) Status of publication in Nuclear Data Sheets (NDS): 52 - NDS, 106, 773 (2007); 53 - NDS, 110, 2689 (2009); 54 - NDS, 107, 1393 (2006); 55 - NDS, 109, 787 (2008); 56 - NDS, 112, 1513 (2011); 63 - NDS, 92, 147 (2001); ENSDF (2009) (2) Evaluation since last meeting (2011). A=54 in review (since 26-Dec-2012) A=52 evaluating A=63 evaluating. Other activities are briefly presented.

77 FR 46528 - Sunshine Act Meeting

Science.gov (United States)

2012-08-03

...: Nuclear Regulatory Commission. DATES: Week of August 6, 2012. PLACE: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. ADDITIONAL ITEMS TO BE CONSIDERED: Week of... Proceeding (June 18, 2012) (Tentative). This meeting will be webcast live at the Web address--www.nrc.gov...

76 FR 50216 - Sunshine Act Meeting

Science.gov (United States)

2011-08-12

... Room, Washington, DC. STATUS: Part of the meeting will be in Open Session and the remainder of the... Draft Proposed Rule on Passenger Vessel Financial Responsibility Requirements. Closed 1. Staff Briefing... Proceedings and Chapter 15 Bankruptcy Petition of the Containership Company A/S. CONTACT PERSON FOR MORE...

Annex D 200 Area Interim Storage Area Final Safety Analysis Report Volume 5 (FSAR) (Section 1 and 2)

International Nuclear Information System (INIS)

CARRELL, R.D.

2003-01-01

The 200 Area Interim Storage Area (200 Area ISA) at the Hanford Site provides for the interim storage of non-defense reactor spent nuclear fuel (SNF) housed in aboveground dry cask storage systems. The 200 Area ISA is a relatively simple facility consisting of a boundary fence with gates, perimeter lighting, and concrete and gravel pads on which to place the dry storage casks. The fence supports safeguards and security and establishes a radiation protection buffer zone. The 200 Area ISA is nominally 200,000 ft 2 and is located west of the Canister Storage Building (CSB). Interim storage at the 200 Area ISA is intended for a period of up to 40 years until the materials are shipped offsite to a disposal facility. This Final Safety Analysis Report (FSAR) does not address removal from storage or shipment from the 200 Area ISA. Three different SNF types contained in three different dry cask storage systems are to be stored at the 200 Area ISA, as follows: (1) Fast Flux Test Facility (FFTF) Fuel--Fifty-three interim storage casks (ISC), each holding a core component container (CCC), will be used to store the FFTF SNF currently in the 400 Area. (2) Neutron Radiography Facility (NRF)TRIGA--One Rad-Vault container stores two DOT-6M 3 containers and six NRF TRIGA casks. (3) Commercial Light Water Reactor Fuel--Six International Standards Organization (ISO) containers, each holding a NAC-1 cask with an inner commercial light water reactor (LWR) canister, are used for storing commercial LWR SNF from the 300 Area. An aboveground dry cask storage location is necessary for the spent fuel because the current storage facilities are being shut down and deactivated. The spent fuel is being transferred to interim storage because there is no permanent repository storage currently available

Concepts for the interim storage of spent fuel elements from research reactors in the Federal Republic of Germany

International Nuclear Information System (INIS)

Niephaus, D.; Bensch, D.; Quaassdorff, P.; Plaetzer, S.

1997-01-01

Research reactors have been operated in the Federal Republic of Germany since the late fifties. These are Material Test Reactors (MTR) and training, Research and Isotope Facilities of General Atomic (TRIGA). A total of seven research reactors, i.e. three TRIGA and four MTR facilities were still in operation at the beginning of 1996. Provisions to apply to the back-end of the fuel cycle are required for their continued operation and for already decommissioned plants. This was ensured until the end of the eighties by the reprocessing of spent fuel elements abroad. In view of impeding uncertainties in connection with waste management through reprocessing abroad, the development of a national back-end fuel cycle concept was commissioned by the Federal Minister of Education, Science, Research and Technology in early 1990. Development work was oriented along the lines of the disposal concept for irradiated light-water reactor fuel elements from nuclear power plants. Analogously, the fuel elements from research reactors are to be interim-stored on a long-term basis in adequately designed transport and storage casks and then be directly finally disposed without reprocessing after up to forty years of interim storage. As a first step in the development of a concept for interim storage, several sites with nuclear infrastructure were examined and assessed with respect to their suitability for interim storage. A reasonably feasible reference concept for storing the research reactor fuel elements in CASTOR MTR 2 transport and storage casks at the Ahaus interim storage facility (BZA) was evaluated and the hot cell facility and AVR store of Forschungszentrum Juelich (KFA) were proposed as an optional contingency concept for casks that cannot be repaired at Ahaus. Development work was continued with detailed studies on these two conceptual variants and the results are presented in this paper. (author)

IAEA consultants' meeting: 9th meeting of atomic and molecular data centres and ALADDIN network, Vienna, September 20 and 21, 1990

International Nuclear Information System (INIS)

Janev, R.K.

1990-11-01

This Summary Report contains the proceedings and the conclusions of the IAEA Consultants' Meeting: 9th Meeting of Atomic and Molecular Data Centres and ALADDIN Network, convened on September 20 and 21, 1990, at the IAEA Headquarters in Vienna. The Progress Reports of national atomic data centres and reports on the ALADDIN status and developments are also included as appendices to the present Report. (author). Refs, figs and tabs

Implementation of the Ryan Haight Online Pharmacy Consumer Protection Act of 2008. Interim final rule with request for comments.

Science.gov (United States)

2009-04-06

The Ryan Haight Online Pharmacy Consumer Protection Act, which was enacted on October 15, 2008, amended the Controlled Substances Act and Controlled Substances Import and Export Act by adding several new provisions to prevent the illegal distribution and dispensing of controlled substances by means of the Internet. DEA is hereby issuing an interim rule to amend its regulations to implement the legislation and is requesting comments on the interim rule.

Staff meeting

CERN Multimedia

2007-01-01

Dear Colleagues, 2007 is a very special year for CERN. I would like to review the status of our activities with you, and I invite you to a presentation on Wednesday 27 June 2007 at 3:00 p.m. Main Auditorium (bldg. 500) Closed-circuit transmission of the meeting will be available in the Council Chamber and in the AB Auditorium (Meyrin), the AB Auditorium (Prévessin), the IT Auditorium (bldg. 31) and the AT Auditorium (bldg. 30). Simultaneous translation into English will be available in the Main Auditorium. Robert AYMAR

2010 Atmospheric System Research (ASR) Science Team Meeting Summary

Energy Technology Data Exchange (ETDEWEB)

Dupont, DL

2011-05-04

This document contains the summaries of papers presented in poster format at the March 2010 Atmospheric System Research Science Team Meeting held in Bethesda, Maryland. More than 260 posters were presented during the Science Team Meeting. Posters were sorted into the following subject areas: aerosol-cloud-radiation interactions, aerosol properties, atmospheric state and surface, cloud properties, field campaigns, infrastructure and outreach, instruments, modeling, and radiation. To put these posters in context, the status of ASR at the time of the meeting is provided here.