Integral Fast Reactor Program. Annual progress report, FY 1992

Energy Technology Data Exchange (ETDEWEB)

Chang, Y.I.; Walters, L.C.; Laidler, J.J.; Pedersen, D.R.; Wade, D.C.; Lineberry, M.J.

1993-06-01

This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1992. Technical accomplishments are presented in the following areas of the IFR technology development activities: (1) metal fuel performance, (2) pyroprocess development, (3) safety experiments and analyses, (4) core design development, (5) fuel cycle demonstration, and (6) LMR technology R&D.

Annual Status Report (FY2016) Performance Assessment for the Environmental Restoration Disposal Facility

Energy Technology Data Exchange (ETDEWEB)

Casbon, M. A. [CH2M HILL Plateau Remediation Company, Richland, WA (United States); Nichols, W. E. [CH2M HILL Plateau Remediation Company, Richland, WA (United States)

2017-03-15

DOE O 435.1, Radioactive Waste Management, and DOE M 435.1-1, Radioactive Waste Management Manual, require that a determination of continued adequacy of the performance assessment (PA), composite analysis (CA), and disposal authorization statement (DAS) be made on an annual basis, and it must consider the results of data collection and analysis from research, field studies, and monitoring. Annual summaries of low-level waste (LLW) disposal operations must be prepared with respect to the conclusions and recommendations of the PA and CA, and a determination of the need to revise the PA or CA must be made. The annual summary requirement provides a structured approach for demonstrating the continued adequacy of the PA and CA in demonstrating a reasonable expectation that the performance objectives will be met. This annual summary addresses only the status of the Environmental Restoration Disposal Facility (ERDF) PA (CP-60089, Performance Assessment for the Environmental Restoration Disposal Facility, Hanford Site, Washington, formerly WCH-520 Rev. 1)1. The CA for ERDF is supported by DOE/RL-2016-62, Annual Status Report (FY 2016): Composite Analysis of Low Level Waste Disposal in the Central Plateau at the Hanford Site. The ERDF PA portion of the CA document is found in Section 3.1.4, and the ERDF operations portion is found in Section 3.3.3.2 of that document.

FY2013 Energy Storage R&D Progress Report

Energy Technology Data Exchange (ETDEWEB)

none,

2014-02-01

The FY 2013 Progress Report for Energy Storage R&D focuses on advancing the development of batteries to enable a large market penetration of hybrid and electric vehicles. Program targets focus on overcoming technical barriers to enable market success including: (1) significantly reducing battery cost, (2) increasing battery performance (power, energy, durability), (3) reducing battery weight & volume, and (4) increasing battery tolerance to abusive conditions such as short circuit, overcharge, and crush.

Integral Fast Reactor Program annual progress report, FY 1991

International Nuclear Information System (INIS)

1992-06-01

This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1991. Technical accomplishments are presented in the following areas of the IFR technology development activities: (1) metal fuel performance, (2) pyroprocess development, (3) safety experiments and analyses, (4) core design development, (5) fuel cycle demonstration, and (6) LMR technology R ampersand D

Integral Fast Reactor Program. Annual progress report, FY 1993

Energy Technology Data Exchange (ETDEWEB)

Chang, Y.I.; Walters, L.C.; Laidler, J.J.; Pedersen, D.R.; Wade, D.C.; Lineberry, M.J.

1994-10-01

This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1993. Technical accomplishments are presented in the following areas of the IFR technology development activities: (1) metal fuel performance, (2) pyroprocess development, (3) safety experiments and analyses, (4) core design development, (5) fuel cycle demonstration, and (6) LMR technology R and D.

Integral Fast Reactor Program. Annual progress report, FY 1993

International Nuclear Information System (INIS)

Chang, Y.I.; Walters, L.C.; Laidler, J.J.; Pedersen, D.R.; Wade, D.C.; Lineberry, M.J.

1994-10-01

This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1993. Technical accomplishments are presented in the following areas of the IFR technology development activities: (1) metal fuel performance, (2) pyroprocess development, (3) safety experiments and analyses, (4) core design development, (5) fuel cycle demonstration, and (6) LMR technology R and D

Advanced evaporator technology progress report FY 1992

Energy Technology Data Exchange (ETDEWEB)

Chamberlain, D.; Hutter, J.C.; Leonard, R.A. [and others

1995-01-01

This report summarizes the work that was completed in FY 1992 on the program {open_quotes}Technology Development for Concentrating Process Streams.{close_quotes} The purpose of this program is to evaluate and develop evaporator technology for concentrating radioactive waste and product streams such as those generated by the TRUEX process. Concentrating these streams and minimizing the volume of waste generated can significantly reduce disposal costs; however, equipment to concentrate the streams and recycle the decontaminated condensates must be installed. LICON, Inc., is developing an evaporator that shows a great deal of potential for this application. In this report, concepts that need to be incorporated into the design of an evaporator operated in a radioactive environment are discussed. These concepts include criticality safety, remote operation and maintenance, and materials of construction. Both solubility and vapor-liquid equilibrium data are needed to design an effective process for concentrating process streams. Therefore, literature surveys were completed and are summarized in this report. A model that is being developed to predict vapor phase compositions is described. A laboratory-scale evaporator was purchased and installed to study the evaporation process and to collect additional data. This unit is described in detail. Two new LICON evaporators are being designed for installation at Argonne-East in FY 1993 to process low-level radioactive waste generated throughout the laboratory. They will also provide operating data from a full-sized evaporator processing radioactive solutions. Details on these evaporators are included in this report.

Advanced evaporator technology progress report FY 1992

International Nuclear Information System (INIS)

Chamberlain, D.; Hutter, J.C.; Leonard, R.A.

1995-01-01

This report summarizes the work that was completed in FY 1992 on the program open-quotes Technology Development for Concentrating Process Streams.close quotes The purpose of this program is to evaluate and develop evaporator technology for concentrating radioactive waste and product streams such as those generated by the TRUEX process. Concentrating these streams and minimizing the volume of waste generated can significantly reduce disposal costs; however, equipment to concentrate the streams and recycle the decontaminated condensates must be installed. LICON, Inc., is developing an evaporator that shows a great deal of potential for this application. In this report, concepts that need to be incorporated into the design of an evaporator operated in a radioactive environment are discussed. These concepts include criticality safety, remote operation and maintenance, and materials of construction. Both solubility and vapor-liquid equilibrium data are needed to design an effective process for concentrating process streams. Therefore, literature surveys were completed and are summarized in this report. A model that is being developed to predict vapor phase compositions is described. A laboratory-scale evaporator was purchased and installed to study the evaporation process and to collect additional data. This unit is described in detail. Two new LICON evaporators are being designed for installation at Argonne-East in FY 1993 to process low-level radioactive waste generated throughout the laboratory. They will also provide operating data from a full-sized evaporator processing radioactive solutions. Details on these evaporators are included in this report

FUNDING ALTERNATIVES FOR LOW-LEVEL WASTE DISPOSAL

International Nuclear Information System (INIS)

Becker, Bruce D.; Carilli, Jhon

2003-01-01

For 13 years, low-level waste (LLW) generator fees and disposal volumes for the U.S. Department of Energy (DOE) National Nuclear Security Administration Nevada Operations Office (NNSA/NV) Radioactive Waste Management Sites (RWMSs) had been on a veritable roller coaster ride. As forecast volumes and disposal volumes fluctuated wildly, generator fees were difficult to determine and implement. Fiscal Year (FY) 2000 forecast projections were so low, the very existence of disposal operations at the Nevada Test Site (NTS) were threatened. Providing the DOE Complex with a viable, cost-effective disposal option, while assuring the disposal site a stable source of funding, became the driving force behind the development of the Waste Generator Access Fee at the NTS. On September 26, 2000, NNSA/NV (after seeking input from DOE/Headquarters [HQ]), granted permission to Bechtel Nevada (BN) to implement the Access Fee for FY 2001 as a two-year Pilot Program. In FY 2001 (the first year the Access Fee was implemented), the NTS Disposal Operations experienced a 90 percent increase in waste receipts from the previous year and a 33 percent reduction in disposal fee charged to the waste generators. Waste receipts for FY 2002 were projected to be 63 percent higher than FY 2001 and 15 percent lower in cost. Forecast data for the outyears are just as promising. This paper describes the development, implementation, and ultimate success of this fee strategy

FY2011 Progress Report for Energy Storage Research & Development

Energy Technology Data Exchange (ETDEWEB)

none,

2012-01-31

The FY 2011 Progress Report for Energy Storage R&D focuses on advancing the development of batteries to enable a large market penetration of hybrid and electric vehicles. Program targets focus on overcoming technical barriers to enable market success including: (1) significantly reducing battery cost, (2) increasing battery performance (power, energy, durability), (3) reducing battery weight & volume, and (4) increasing battery tolerance to abusive conditions such as short circuit, overcharge, and crush.

Technology development, evaluation, and application (TDEA) FY 1997 progress report

Energy Technology Data Exchange (ETDEWEB)

Hoffman, L.G.

1998-05-01

The public expects that the Los Alamos National Laboratory (LANL) will operate in a manner that prevents negative impacts to the environment and protects the safety and health of its employees and the public. To achieve this goal within budget, the Department of Energy (DOE) and LANL must develop new and improved environment, safety, and health (ES and H) technologies and implement innovative, more cost-effective ES and H approaches to operations. In FY95, the Environment, Safety, and Health (ESH) Division initiated a Technology Development, Evaluation, and Application (TDEA) program. The purpose of this unique program is to test and develop technologies that solve LANL ES and H problems and improve the safety of LANL operations. This progress report presents the results of 10 projects funded in FY97 by the TDEA Committee of the Environment, Safety, and Health Division. Products generated from the projects funded in FY97 included implementation of radiation worker dosimetric monitoring systems (two); evaluation and validation of cost-effective animal-tracking systems for environmental studies (two); evaluation of personal protective equipment (two); and development of a method for optimal placement of continuous air monitors in the workplace.

Technology development, evaluation, and application (TDEA) FY 1997 progress report

International Nuclear Information System (INIS)

Hoffman, L.G.

1998-05-01

The public expects that the Los Alamos National Laboratory (LANL) will operate in a manner that prevents negative impacts to the environment and protects the safety and health of its employees and the public. To achieve this goal within budget, the Department of Energy (DOE) and LANL must develop new and improved environment, safety, and health (ES and H) technologies and implement innovative, more cost-effective ES and H approaches to operations. In FY95, the Environment, Safety, and Health (ESH) Division initiated a Technology Development, Evaluation, and Application (TDEA) program. The purpose of this unique program is to test and develop technologies that solve LANL ES and H problems and improve the safety of LANL operations. This progress report presents the results of 10 projects funded in FY97 by the TDEA Committee of the Environment, Safety, and Health Division. Products generated from the projects funded in FY97 included implementation of radiation worker dosimetric monitoring systems (two); evaluation and validation of cost-effective animal-tracking systems for environmental studies (two); evaluation of personal protective equipment (two); and development of a method for optimal placement of continuous air monitors in the workplace

Hydrologic resources management program, FY 1998 progress report; FINAL

International Nuclear Information System (INIS)

Benedict, F.C.; Criss, R.E.; Davisson, M.L.; Eaton, G.F.; Hudson, G.B.; Kenneally, J.M.; Rose, T.P.; Smith, D.

1999-01-01

This report presents the results from FY 1998 technical studies conducted by Lawrence Livermore National Laboratory (LLNL) as part of the Hydrology and Radionuclide Migration Program (HRMP) and Underground Test Area (UGTA) project. The HRMP is sponsored by Defense Programs (DP) of the U.S. Department of Energy, Nevada Operations Office (DOE/NV), and supports DP operations at the Nevada Test Site (NTS) through studies of radiochemistry and resource management related to the defense programs mission. Other participating organizations include the Los Alamos National Laboratory (LANL), the United States Geological Survey (USGS), the Desert Research Institute (DRI) of the University of Nevada, the United States Environmental Protection Agency (EPA), and Bechtel-Nevada (BN). The UGTA project is an Environmental Management (EM) activity of DOE/NV that supports a Federal Facilities Agreement and Consent Order between the Department of Energy, the Department of Defense, and the State of Nevada. UGTA's primary function is to address the legacy release of hazardous constituents at the Nevada Test Site, the Tonopah Test Range, and off-Nevada Test Site underground nuclear testing areas. Participating contractors include LLNL (Earth and Environmental Sciences Directorate, Analytical and Nuclear Chemistry Division), LANL, DRI, USGS, BN, HSI-GeoTrans, and IT Corporation. The FY 1998 HRMP and UGTA annual progress report follows the organization and contents of our FY 1997 report (Smith et al., 1998), and includes our results from CY 1997-1998 technical studies of radionuclide migration and isotope hydrology at the Nevada Test Site. During FY 1998, LLNL continued its efforts under the HRMP to pursue a technical agenda relevant to the science-based stockpile stewardship program at DOE/NV. Support to UGTA in FY 1998 included efforts to quantitatively define the radionuclide source term residual from underground nuclear weapons testing and the derivative solution, or hydrologic source

StreamNet: FY 1999 annual progress report

International Nuclear Information System (INIS)

Columbia River Inter-Tribal Fish Commission

2000-01-01

This report was funded by the Bonneville Power Administration (BPA), US Department of Energy, as part of BPA's program to protect, mitigate, and enhance fish and wildlife affected by the development and operation of hydroelectric facilities on the Columbia River and its tributaries. The views of this report are the author's and do not necessarily represent the views of BPA. This annual report covers progress made by: Columbia River Inter-Tribal Fish Commission Idaho; Department of Fish and Game; Montana Department of Fish, Wildlife and Parks; Oregon Department of Fish and Wildlife; Pacific States Marine Fisheries Commission; Shoshone-Bannock Tribes; US Fish and Wildlife Service; Washington Department of Fish and Wildlife; and FY1999 StreamNet Quickplan

FY2012 Progress Report for Energy Storage Research & Development

Energy Technology Data Exchange (ETDEWEB)

none,

2013-01-01

FY 2012 annual report of the energy storage research and development effort within the VT Office. An important step for the electrification of the nation’s light duty transportation sector is the development of more cost-effective, long lasting, and abuse-tolerant PEV batteries. In fiscal year 2012, battery R&D work continued to focus on the development of high-energy batteries for PEVs and very high power devices for hybrid vehicles. This document provides a summary and progress update of the VTP battery R&D projects that were supported in 2012.

Annual Progress Report FY-82. Volume I.

Science.gov (United States)

1982-01-01

Comparison of Binaural Versus 316 Monaural Amplification. (FY-81PI) 2535 Development of Method for Generating 318 Individualized Aural Rehabilitation...Oncology Group. 428 (FY-74 I ) 4116 The Evaluation of Petal Systolic Time Intervals 429 and Beat interval Variation in Fetal heart Rate as Early

FY 1997 Progress report on tube propagation testing of tank waste using the PRSST

International Nuclear Information System (INIS)

Bechtold, D.B.

1997-01-01

The subject of this FY 1997 progress report is tube propagation tests of actual, dried tank waste to verify the contact temperature ignition (CTI) criterion for point-source ignition in the Hanford Site waste tanks. Testing is in support of the Organic Tanks Safety Project and will help resolve safety issues with waste containing organic constituents. In FY 1997, improvements were made to the laboratory apparatus and procedures for conducting the testing, and the final testing strategy was formulated. The strategy lays out details of the tests to be performed, samples to be tested, and modes of reporting results

Solid secondary waste testing for maintenance of the Hanford Integrated Disposal Facility Performance Assessment - FY 2017

Energy Technology Data Exchange (ETDEWEB)

Nichols, Ralph L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Seitz, Roger R. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Dixon, Kenneth L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2017-08-01

The Waste Treatment and Immobilization Plant (WTP) at Hanford is being constructed to treat 56 million gallons of radioactive waste currently stored in underground tanks at the Hanford site. Operation of the WTP will generate several solid secondary waste (SSW) streams including used process equipment, contaminated tools and instruments, decontamination wastes, high-efficiency particulate air filters (HEPA), carbon adsorption beds, silver mordenite iodine sorbent beds, and spent ion exchange resins (IXr) all of which are to be disposed in the Integrated Disposal Facility (IDF). An applied research and development program was developed using a phased approach to incrementally develop the information necessary to support the IDF PA with each phase of the testing building on results from the previous set of tests and considering new information from the IDF PA calculations. This report contains the results from the exploratory phase, Phase 1 and preliminary results from Phase 2. Phase 3 is expected to begin in the fourth quarter of FY17.

Commercial waste treatment program annual progress report for FY 1983

Energy Technology Data Exchange (ETDEWEB)

McElroy, J.L.; Burkholder, H.C. (comps.)

1984-02-01

This annual report describes progress during FY 1983 relating to technologies under development by the Commercial Waste Treatment Program, including: development of glass waste form and vitrification equipment for high-level wastes (HLW); waste form development and process selection for transuranic (TRU) wastes; pilot-scale operation of a radioactive liquid-fed ceramic melter (LFCM) system for verifying the reliability of the reference HLW treatment proces technology; evaluation of treatment requirements for spent fuel as a waste form; second-generation waste form development for HLW; and vitrification process control and product quality assurance technologies.

Annual Status Report (FY2009) Composite Analysis of Low-Level Waste Disposal in the Central Plateau at the Hanford Site

Energy Technology Data Exchange (ETDEWEB)

Nichols, W. E. [CH2M HILL Plateau Remediation Company, Richland, WA (United States)

2010-02-10

In accordance with the U.S. Department of Energy (DOE) requirements in DOE O 435.1, Radioactive Waste Management, and implemented by DOE/RL-2000-29, Maintenance Plan for the Composite Analysis of the Hanford Site, Southeast Washington, the DOE Richland Operations Office has prepared this annual status report for fiscal year (FY) 2009 of PNNL-11800, Composite Analysis for the Low-Level Waste Disposal in the 200-Area Plateau of the Hanford Site, hereafter referred to as the Composite Analysis.

International Collaboration on Spent Fuel Disposition in Crystalline Media: FY17 Progress Report

Energy Technology Data Exchange (ETDEWEB)

Wang, Yifeng [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hadgu, Teklu [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Kainina, Elena [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Jove-Colon, Carlos [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2017-09-01

Active participation in international R&D is crucial for achieving the Spent Fuel Waste Science & Technology (SFWST) long-term goals of conducting “experiments to fill data needs and confirm advanced modeling approaches” and of having a “robust modeling and experimental basis for evaluation of multiple disposal system options” (by 2020). DOE’s Office of Nuclear Energy (NE) has developed a strategic plan to advance cooperation with international partners. The international collaboration on the evaluation of crystalline disposal media at Sandia National Laboratories (SNL) in FY17 focused on the collaboration through the Development of Coupled Models and their Validation against Experiments (DECOVALEX-2019) project. The DECOVALEX project is an international research and model comparison collaboration, initiated in 1992, for advancing the understanding and modeling of coupled thermo-hydro-mechanical-chemical (THMC) processes in geological systems. SNL has been participating in three tasks of the DECOVALEX project: Task A. Modeling gas injection experiments (ENGINEER), Task C. Modeling groundwater recovery experiment in tunnel (GREET), and Task F. Fluid inclusion and movement in the tight rock (FINITO).

[Shippingport Station Decommissioning Project]: FY 1987 annual progress report, October 1, 1986-September 30, 1987

International Nuclear Information System (INIS)

1988-01-01

This report presents progress on the Shippingport Station Decommissioning Project for FY 1987. There are two main topics: Project Management and Decommissioning Project Activities. Changes from technical and managerial concepts developed in the original Decommissioning Plan are presented with the related technical, economic, or schedule considerations. 3 refs., 9 figs., 4 tabs

Shippingport Station Decommissioning Project: FY 1988 annual progress report, October 1, 1987--September 30, 1988

International Nuclear Information System (INIS)

1989-01-01

This report presents progress on the Shippingport Station Decommissioning Project for FY 1988. There are two main topics: Project Management and Decommissioning Project Activities. Changes from technical and managerial concepts developed in the original Decommissioning Plan are presented with the related technical, economic, or schedular considerations. 4 refs., 17 figs., 2 tabs

Laboratory Directed Research and Development FY 1998 Progress Report

Energy Technology Data Exchange (ETDEWEB)

John Vigil; Kyle Wheeler

1999-04-01

This is the FY 1998 Progress Report for the Laboratory Directed Research and Development (LDRD) Program at Los Alamos National Laboratory. It gives an overview of the LDRD Program, summarizes work done on individual research projects, relates the projects to major Laboratory program sponsors, and provides an index to the principle investigators. Project summaries are grouped by their LDRD component: Competency Development, Program Development, and Individual Projects. Within each component, they are further grouped into nine technical categories: (1) materials science, (2) chemistry, (3) mathematics and computational science, (4) atomic, molecular, optical, and plasma physics, fluids, and particle beams, (5) engineering science, (6) instrumentation and diagnostics, (7) geoscience, space science, and astrophysics, (8) nuclear and particle physics, and (9) bioscience.

Laboratory directed research and development: FY 1997 progress report

Energy Technology Data Exchange (ETDEWEB)

Vigil, J.; Prono, J. [comps.

1998-05-01

This is the FY 1997 Progress Report for the Laboratory Directed Research and Development (LDRD) program at Los Alamos National Laboratory. It gives an overview of the LDRD program, summarizes work done on individual research projects, relates the projects to major Laboratory program sponsors, and provides an index to the principal investigators. Project summaries are grouped by their LDRD component: Competency Development, Program Development, and Individual Projects. Within each component, they are further grouped into nine technical categories: (1) materials science, (2) chemistry, (3) mathematics and computational science, (4) atomic and molecular physics and plasmas, fluids, and particle beams, (5) engineering science, (6) instrumentation and diagnostics, (7) geoscience, space science, and astrophysics, (8) nuclear and particle physics, and (9) bioscience.

Subseabed disposal safety analysis

International Nuclear Information System (INIS)

Koplick, C.M.; Kabele, T.J.

1982-01-01

This report summarizes the status of work performed by Analytic Sciences Corporation (TASC) in FY'81 on subseabed disposal safety analysis. Safety analysis for subseabed disposal is divided into two phases: pre-emplacement which includes all transportation, handling, and emplacement activities; and long-term (post-emplacement), which is concerned with the potential hazard after waste is safely emplaced. Details of TASC work in these two areas are provided in two technical reports. The work to date, while preliminary, supports the technical and environmental feasibility of subseabed disposal of HLW

Technical reliability of geological disposal for high-level radioactive wastes in Japan. The second progress report. An extra issue: background of the geological disposal

International Nuclear Information System (INIS)

1999-11-01

Based on the Advisory Committee Report on Nuclear Fuel Cycle Backend Policy submitted to the Japanese Government in 1997, JNC documents the progress of research and development program in the form of the second progress report (the first one published in 1992). It summarizes an evaluation of the technical reliability and safety of the geological disposal concept for high-level radioactive wastes (HLW) in Japan. The present document, an extra issue of the progress report, was prepared for the expected readers of the report to have background information on the geological disposal. Thus it gives information about (1) generation of high-level radioactive wastes, (2) history of plans proposed for HLW disposal in Japan, and (3) procedure until the geological disposal plan is finally adopted and basic future schedules. It further discusses on such problems in HLW treatment and disposal, as for example a problem of reliable safety for a very long period. (Ohno, S.)

Annual Status Report (FY2010) Composite Analysis of Low-Level Waste Disposal in the Central Plateau at the Hanford Site

Energy Technology Data Exchange (ETDEWEB)

Nichols, W. E. [CH2M HILL Plateau Remediation Company, Richland, WA (United States)

2011-01-11

In accordance with the U.S. Department of Energy (DOE) requirements in DOE O 435.1 Chg 1, Radioactive Waste Management, and implemented by DOE/RL-2000-29, Maintenance Plan for the Composite Analysis of the Hanford Site, Southeast Washington, the DOE Richland Operations Office (DOE-RL), also known as RL, has prepared this annual status report for fiscal year (FY) 2010 of PNNL-11800, Composite Analysis for Low-Level Waste Disposal in the 200 Area Plateau of the Hanford Site, hereafter referred to as the Composite Analysis.

Nuclear waste treatment program: Annual report for FY 1987

International Nuclear Information System (INIS)

Brouns, R.A.; Powell, J.A.

1988-09-01

Two of the US Department of Energy's (DOE) nuclear waste management-related goals are to ensure that waste management is not an obstacle to the further development of light-water reactors and the closure of the nuclear fuel cycle and to fulfill its institutional responsibility for providing safe storage and disposal of existing and future nuclear wastes. As part of its approach to achieving these goals, the Office of Remedial Action and Waste Technology of DOE established what is now called the Nuclear Waste Treatment Program (NWTP) at the Pacific Northwest Laboratory during the second half of FY 1982. To support DOE's attainment of its goals, the NWTP is to provide technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management system and problem-specific treatment approaches, waste form and treatment process adaptations, equipment designs, and trouble-shooting assistance, as required to treat existing wastes. This annual report describes progress during FY 1987 towards meeting these two objectives. 24 refs., 59 figs., 24 tabs

Shippingport Station Decommissioning Project: FY 1986 annual progress report, October 1, 1985 through September 30, 1986

International Nuclear Information System (INIS)

1987-01-01

This report presents progress on the Shippingport Station Decommissioning Project for FY 1986. There are two main topics: Project Management and Decommissioning Project Activities. Changes from technical and managerial concepts developed in the original Decommissioning Plan are presented with the related technical, economic, or schedule considerations. 9 refs., 4 figs., 3 tabs

Waste Tank Organic Safety Program: Analytical methods development. Progress report, FY 1994

International Nuclear Information System (INIS)

Campbell, J.A.; Clauss, S.A.; Grant, K.E.

1994-09-01

The objectives of this task are to develop and document extraction and analysis methods for organics in waste tanks, and to extend these methods to the analysis of actual core samples to support the Waste Tank organic Safety Program. This report documents progress at Pacific Northwest Laboratory (a) during FY 1994 on methods development, the analysis of waste from Tank 241-C-103 (Tank C-103) and T-111, and the transfer of documented, developed analytical methods to personnel in the Analytical Chemistry Laboratory (ACL) and 222-S laboratory. This report is intended as an annual report, not a completed work

Progress report for the Office of Safeguards and Security for FY 1982

International Nuclear Information System (INIS)

Smith, D.H.; McKown, H.S.; Walker, R.L.; Sherman, R.L.; Pritchard, C.A.; Carter, J.A.

1982-12-01

Progress in various areas funded by, or of interest to, the Office of Safeguards and Security during FY 1982 is reported. The quadrupole mass spectrometer and its mobile laboratory visited several sites; results were uniformly excellent. We designed, built, and evaluated a new ion source for this instrument; as a result, performance is considerably enhanced. We have completed initial evaluation of lutetium for use as a double spike in calibrating holding tanks or other vessels of indeterminate volume. Precisions and accuracies of about 0.1% were obtained. Two uranium standards have been evaluated using NBS isotopic standards and SALE samples

GNEP Material Transportation, Storage and Disposal Analysis FY-08 Summary Report

Energy Technology Data Exchange (ETDEWEB)

Halsey, W

2009-01-15

This report provides a summary for FY-2008 of activities, analyses and products from the Material Transportation, Storage and Disposal (M-TSD) sub-task of Systems Analysis within the Advanced Fuel Cycle Research & Development area of the Global Nuclear Energy Partnership. The objective of this work is to evaluate near-term material management requirements for initial GNEP facilities and activities, long-term requirements for large-scale GNEP technology deployment, and alternatives and paths forward to meet these needs. For FY-08, the work expanded to include the Integrated Waste Management Strategy as well as integration with the newly formed Waste Forms Campaign. The M-TSD team was expanded with the addition of support from Savannah River National Lab (SRNL) to the existing team of Lawrence Livermore National Lab (LLNL), Argonne National Lab (ANL), Idaho National Lab (INL), Sandia National Lab (SNL) and University of Nevada - Reno (UN-R). During the first half of the year, analysis was focused on providing supporting technical analysis and documentation to support anticipated high-level decisions on program direction. A number of analyses were conducted and reports prepared as program deliverables. This work is briefly summarized in this report. Analyses provided informally to other program efforts are included in this report to provide documentation. This year-end summary was planned primarily as a compilation of activities following the anticipated programmatic decisions. These decisions were deferred beyond the end of the year, and funds were reallocated in a number of areas, thus reducing the M-TSD activities. This report summarizes the miscellaneous 'ad-hoc' work conducted during the later part of the year, such as support to the draft Programmatic Environmental Impact Statement (PEIS), and support to other program studies. Major programmatic contributions from the M-TSD team during the year included: (1) Completion of the IWMS in March 2008 as the

GNEP Material Transportation, Storage and Disposal Analysis FY-08 Summary Report

International Nuclear Information System (INIS)

Halsey, W.

2009-01-01

This report provides a summary for FY-2008 of activities, analyses and products from the Material Transportation, Storage and Disposal (M-TSD) sub-task of Systems Analysis within the Advanced Fuel Cycle Research and Development area of the Global Nuclear Energy Partnership. The objective of this work is to evaluate near-term material management requirements for initial GNEP facilities and activities, long-term requirements for large-scale GNEP technology deployment, and alternatives and paths forward to meet these needs. For FY-08, the work expanded to include the Integrated Waste Management Strategy as well as integration with the newly formed Waste Forms Campaign. The M-TSD team was expanded with the addition of support from Savannah River National Lab (SRNL) to the existing team of Lawrence Livermore National Lab (LLNL), Argonne National Lab (ANL), Idaho National Lab (INL), Sandia National Lab (SNL) and University of Nevada - Reno (UN-R). During the first half of the year, analysis was focused on providing supporting technical analysis and documentation to support anticipated high-level decisions on program direction. A number of analyses were conducted and reports prepared as program deliverables. This work is briefly summarized in this report. Analyses provided informally to other program efforts are included in this report to provide documentation. This year-end summary was planned primarily as a compilation of activities following the anticipated programmatic decisions. These decisions were deferred beyond the end of the year, and funds were reallocated in a number of areas, thus reducing the M-TSD activities. This report summarizes the miscellaneous 'ad-hoc' work conducted during the later part of the year, such as support to the draft Programmatic Environmental Impact Statement (PEIS), and support to other program studies. Major programmatic contributions from the M-TSD team during the year included: (1) Completion of the IWMS in March 2008 as the baseline

Progress in developing new commercial LLRW disposal facilities and DOE assistance

International Nuclear Information System (INIS)

Tait, T.D.; Hinschberger, S.T.

1988-01-01

This paper reports state and regional progress in developing new commercial low-level radioactive waste disposal facilities. Specifically the paper addresses DOE determination of state and regional compliance with the 1988 milestone requirements of the Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA). In addition, the paper summarizes the assistance provided by the Department of Energy (DOE) to the states and regions in their efforts to develop new disposal facilities as mandated in the LLRWPAA

Development of new low level radioactive waste disposal sites: A progress report

International Nuclear Information System (INIS)

Anderson, Robert T.; Antonucci, George J.; Ryan, Michael T.

1992-01-01

The status of the development of three new low level radioactive waste disposal facilities for the Central Midwest (Illinois), Southeastern (North Carolina) and Appalachian (Pennsylvania) compacts is presented. These three sites will dispose of about 50-65 percent of the commercial low-level waste (LLW) generated in the U.S. annually. Chem-Nuclear, as developer and proposed operator of all three sites has used a common approach to site development. This approach has been based on their twenty-plus years of operating experience and a standard technical approach. The technology employed is an above-grade, multiple engineered barrier design. The paper also contrasts actual progress at each site with a generalized project schedule. Areas of schedule delays are noted along with the steps being taken to accelerate schedule. Finally, we note that continued progress and timely start-up of operations of these new sites is critical on a national basis. This is due to the possibility of near-term closure of the existing LLW disposal sites. (author)

Progress of work in the FY1993 on the subject-2. Study on the validation of assessment models used in an environmental consequence assessment methodology for nuclear accidents

International Nuclear Information System (INIS)

1994-01-01

Concerning the above subject, in this report, the progress of work in FY 1993 and the working plan for the remaining period are described. The summaries of the progress are given in the Appendix. This is the copy of the report presented at the second steering conference. The progress of work carried out by JAERI in FY 1993 were the analysis of data handed over from CHECIR, and the development of data bases. In the remaining period of FY1993, Dr. Ponomarev of CHECIR will visit JAERI for 15 days in March, 1994. The various kinds of data which must be prepared for the implementation of the above subject, and the data that have been handed over so far from CHECIR are shown. The analysis of the site-specific input data for OSCAAR such as source terms, meteorological data and topographical data, and the data for being compared with the model prediction such as the spectrometry analysis of soil samples in each layer, γ ray dose rate and others are described. The data which were installed into the data base management system are shown. The working plan for FY 1994 on the above subject is added. (K.I.)

Electronics Engineering Research. Final report, FY 1979

International Nuclear Information System (INIS)

Weissenberger, S.

1980-01-01

Accomplishments in Electronics Engineering Research (EER) during FY79 spanned a broad range of technologies, from high-speed microelectronics to digital image enhancement; from underground probing with electromagnetic waves to detecting neutrons with a small solid-state device; and from computer systems to aid engineers, to software tools to aid programmers. This report describes the overall EER program and its objectives, summarizes progress made in FY79, and outlines plans for FY80

Technical reliability of geological disposal for high-level radioactive wastes in Japan. The second progress report. Part 2. Engineering technology for geological disposal

International Nuclear Information System (INIS)

1999-11-01

Based on the Advisory Committee Report on Nuclear Fuel Cycle Backend Policy submitted to the Japanese Government in 1997, JNC documents the progress of research and development program in the form of the second progress report (the first one published in 1992). It summarizes an evaluation of the technical reliability and safety of the deep geological disposal concept for high-level radioactive wastes (HLW) in Japan. The present document, part 2 of the progress report, concerns engineering aspect with reference to Japanese geological disposal plan, according to which the vitrified HLW will be disposed of into a deep, stable rock mass with thick containers and surrounding buffer materials at the depth of several hundred meters. It discusses on multi-barrier systems consisting of a series of engineered and natural barriers that will isolate radioactive nuclides effectively and retard their migrations to the biosphere environment. Performance of repository components, including specifications of containers for vitrified HLW and their overpacks under design as well as buffer material such as Japanese bentonite to be placed in between are described referring also to such possible problems as corrosion arising from the supposed system. It also presents plans and designs for underground disposal facilities, and the presumed management of the underground facilities. (Ohno, S.)

FY-1981 project status for the Transuranic Waste Treatment Facility

International Nuclear Information System (INIS)

Benedetti, R.L.; Tait, T.D.

1981-11-01

The primary objective of the Transuranic Waste Treatment Facility (TWTF) Project is to provide a facility to process low-level transuranic waste stored at the Idaho National Engineering Laboratory (INEL) into a form acceptable for disposal at the Waste Isolation Pilot Plant. This report provides brief summary descriptions of the project objectives and background, project status through FY-1981, planned activities for FY-1982, and the EG and G TWTF Project office position on processing INEL transuranic waste

Photovoltaic Subcontract Program, FY 1990

Energy Technology Data Exchange (ETDEWEB)

Summers, K.A. (ed.)

1991-03-01

This report summarizes the progress of the subcontracted photovoltaic (PV) research and development (R D) performed under the Photovoltaics Program at the Solar Energy Research Institute (SERI). The SERI subcontracted PV research and development represents most of the subcontracted R D that is funded by the US Department of Energy (DOE) National Photovoltaics Program. This report covers fiscal year (FY) 1990: October 1, 1989 through September 30, 1990. During FY 1990, the SERI PV program started to implement a new DOE subcontract initiative, entitled the Photovoltaic Manufacturing Technology (PVMaT) Project.'' Excluding (PVMaT) because it was in a start-up phase, in FY 1990 there were 54 subcontracts with a total annualized funding of approximately $11.9 million. Approximately two-thirds of those subcontracts were with universities, at a total funding of over $3.3 million. Cost sharing by industry added another $4.3 million to that $11.9 million of SERI PV subcontracted R D. The six technical sections of this report cover the previously ongoing areas of the subcontracted program: the Amorphous Silicon Research Project, Polycrystalline Thin Films, Crystalline Silicon Materials Research, High-Efficiency Concepts, the New Ideas Program, and the University Participation Program. Technical summaries of each of the subcontracted programs discuss approaches, major accomplishments in FY 1990, and future research directions. Another section introduces the PVMaT project and reports the progress since its inception in FY 1990. Highlights of technology transfer activities are also reported.

Isotope and nuclear chemistry division. Annual report, FY 1987. Progress report, October 1986-September 1987

International Nuclear Information System (INIS)

Barr, D.W.; Heiken, J.H.

1988-05-01

This report describes progress in the major research and development programs carried out in FY 1987 by the Isotope and Nuclear Chemistry Division. The report includes articles on radiochemical weapons diagnostics and research and development; other unclassified weapons research; stable and radioactive isotope production and separation; chemical biology and nuclear medicine; element and isotope transport and fixation; actinide and transition metal chemistry; structural chemistry, spectroscopy, and applications; nuclear structure and reactions; irradiation facilities; advanced concepts and technology; and atmospheric chemistry

2nd Quarter Transportation Report FY 2014

Energy Technology Data Exchange (ETDEWEB)

Gregory, L. [National Security Technologies, LLC, Las Vegas, NV (United States) (United States)

2014-07-01

This report satisfies the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO) commitment to prepare a quarterly summary report of radioactive waste shipments to the Nevada National Security Site (NNSS) Radioactive Waste Management Complex (RWMC) at Area 5. There were no shipments sent for offsite treatment and returned to the NNSS this quarter. This report summarizes the second quarter of fiscal year (FY) 2014 low-level radioactive waste (LLW) and mixed low-level radioactive waste (MLLW) shipments. This report also includes annual summaries for FY 2014 in Tables 4 and 5. Tabular summaries are provided which include the following: Sources of and carriers for LLW and MLLW shipments to and from the NNSS; Number and external volume of LLW and MLLW shipments; Highway routes used by carriers; and Incident/accident data applicable to LLW and MLLW shipments. In this report shipments are accounted for upon arrival at the NNSS, while disposal volumes are accounted for upon waste burial. The disposal volumes presented in this report do not include minor volumes of non-radioactive materials that were approved for disposal. Volume reports showing cubic feet (ft3) generated using the Low-Level Waste Information System may vary slightly due to differing rounding conventions.

Status of UFD Campaign International Activities in Disposal Research

Energy Technology Data Exchange (ETDEWEB)

Birkholzer, Jens [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

2012-09-01

While the United States research program for geologic disposal of high-level radioactive waste over the past decades focused solely on an open tunnel emplacement in unsaturated densely fractured tuff, several international organizations have made significant progress in the characterization and performance evaluation of other disposal design options and host rock characteristics, most of which were very different from those studied in the U.S. As a result, areas of direct collaboration between the U.S. Department of Energy’s (DOE) and international geologic disposal programs were quite limited during that time. Recently, the decision by DOE to no longer pursue the geologic disposal of high-level radioactive waste and spent fuel at the Yucca Mountain site has shifted the nation’s focus to disposal design options and geologic environments similar to those being investigated by other nations. DOE started to recognize that close international collaboration is a beneficial and costeffective strategy for advancing disposal science and, in FY12, embarked on a comprehensive effort to identify international collaboration opportunities, to interact with international organizations and advance promising collaborations, and to plan/develop specific R&D activities in cooperation with international partners. This report describes the active collaboration opportunities available to U.S. researchers as a result of this effort, and presents specific cooperative research activities that have been recently initiated within DOE’s disposal research program. The focus in this report is on those opportunities that provide access to field data (and respective interpretation/modeling), and/or may allow participation in ongoing and planned field experiments.

The Abbott Districts in 2005-06: Progress and Challenges, Spring 2006

Science.gov (United States)

Hirsch, Lesley

2006-01-01

New Jersey's urban--or "Abbott"--schools have improved at the preschool and elementary school level, but lag when it comes to middle and high school performance. These are the key findings of an Abbott Indicators Project report entitled, "The Abbott Districts in 2005-06: Progress and Challenges." The report was prepared by…

E-Area Performance Assessment Interim Measures Assessment FY2005

Energy Technology Data Exchange (ETDEWEB)

Stallings, M

2006-01-31

After major changes to the limits for various disposal units of the E-Area Low Level Waste Facility (ELLWF) last year, no major changes have been made during FY2005. A Special Analysis was completed which removes the air pathway {sup 14}C limit from the Intermediate Level Vault (ILV). This analysis will allow the disposal of reactor moderator deionizers which previously had no pathway to disposal. Several studies have also been completed providing groundwater transport input for future special analyses. During the past year, since Slit Trenches No.1 and No.2 were nearing volumetric capacity, they were operationally closed under a preliminary closure analysis. This analysis was performed using as-disposed conditions and data and showed that concrete rubble from the demolition of 232-F was acceptable for disposal in the STs even though the latest special analysis for the STs had reduced the tritium limits so that the inventory in the rubble exceeded limits. A number of special studies are planned during the next years; perhaps the largest of these will be revision of the Performance Assessment (PA) for the ELLWF. The revision will be accomplished by incorporating special analyses performed since the last PA revision as well as revising analyses to include new data. Projected impacts on disposal limits of more recent studies have been estimated. No interim measures will be applied during this year. However, it is being recommended that tritium disposals to the Components-in-Grout (CIG) Trenches be suspended until a limited Special Analysis (SA) currently in progress is completed. This SA will give recommendations for optimum placement of tritiated D-Area tower waste. Further recommendations for tritiated waste placement in the CIG Trenches will be given in the upcoming PA revision.

Analyses in Support of Z-IFE LLNL Progress Report for FY-05

International Nuclear Information System (INIS)

Moir, R W; Abbott, R P; Callahan, D A; Latkowski, J F; Meier, W R; Reyes, S

2005-01-01

The FY04 LLNL study of Z-IFE [1] proposed and evaluated a design that deviated from SNL's previous baseline design. The FY04 study included analyses of shock mitigation, stress in the first wall, neutronics and systems studies. In FY05, the subject of this report, we build on our work and the theme of last year. Our emphasis continues to be on alternatives that hold promise of considerable improvements in design and economics compared to the base-line design. Our key results are summarized here

Present status of refining and conversion facility dismantling. Progress in first half of 2010FY

International Nuclear Information System (INIS)

Kado, Kazumi; Sugitsue, Noritake; Morimoto, Yasuyuki; Ikegami, Sohei; Tanaka, Yoshio; Takahashi, Nobuo; Tokuyasu, Takashi

2011-06-01

The Refining and Conversion Facility located in the Ningyo-toge Environmental Engineering Center had the natural uranium conversion process and reprocessed uranium conversion process. The construction of this facility was started in 1979 and completed in October 1981. Dismantling of equipments in radiation controlled area of this facility was started from 2008, and all equipments in radiation controlled area will be dismantled by the 2011 fiscal year. This report describes the master plan of this decommissioning and shows as the progress in first half year of 2010FY, the actual time schedule, the method of decommissioning, the decommissioning progress appearance with photographs, work rates of each room / each worker class, and the quantity of dismantled materials and secondary wastes. (author)

Present status of refining and conversion facility dismantling. Progress in first half of 2009FY

International Nuclear Information System (INIS)

Kado, Kazumi; Sugitsue, Noritake; Morimoto, Yasuyuki; Ikegami, Sohei; Tanaka, Yoshio; Takahashi, Nobuo; Tokuyasu, Takashi

2010-03-01

The Refining and Conversion Facility located in the Ningyo-toge Environmental Engineering Center had the natural uranium conversion process and reprocessed uranium conversion process. The construction of this facility was started in 1979 and completed in October 1981. Dismantling of equipments in radiation controlled area of this facility was started from 2008, and all equipments in radiation controlled area will be dismantled by the 2011 fiscal year. This report describes the master plan of this decommissioning and shows as the progress in first half year of 2009FY, the actual time schedule, the method of decommissioning, the decommissioning progress appearance with photographs, work rates of each room / each worker class, and the quantity of dismantled materials and secondary wastes. (author)

Present status of refining and conversion facility dismantling. Progress in latter half of 2008FY

International Nuclear Information System (INIS)

Kado, Kazumi; Sugitsue, Noritake; Morimoto, Yasuyuki; Ikegami, Sohei; Takahashi, Nobuo; Tokuyasu, Takashi

2010-01-01

The Refining and Conversion Facility located in the Ningyo-toge Environmental Engineering Center had the natural uranium conversion process and reprocessed uranium conversion process. The construction of this facility was started in 1979 and completed in October 1981. Dismantling of equipments in radiation controlled area of this facility was started from 2008, and all equipments in radiation controlled area will be dismantled by the 2011 fiscal year. This report describes the master plan of this decommissioning and shows as the progress in latter half year of 2008FY, the actual time schedule, the method of decommissioning, the decommissioning progress appearance with photographs, work rates of each room/each worker class, and the quantity of dismantled materials and secondary wastes. (author)

Technology Development, Evaluation, and Application (TDEA) FY 1998 Progress Report Environment, Safety, and Health (ESH) Division

Energy Technology Data Exchange (ETDEWEB)

Larry G. Hoffman; Kenneth Alvar; Thomas Buhl; Bruce Erdal; Philip Fresquez; Elizabeth Foltyn; Wayne Hansen; Bruce Reinert

1999-06-01

This progress report presents the results of 10 projects funded ($504K) in FY98 by the Technology Development, Evaluation, and Application (TDEA) Committee of the Environment, Safety, and Health Division. Nine projects are new for this year; two projects were completed in their third and final TDEA-funded year. As a result of their TDEA-funded projects, investigators have published 19 papers in professional journals, proceedings, or Los Alamos reports and presented their work at professional meetings. Supplemental funds and in-kind contributions, such as staff time, instrument use, and work space were also provided to the TDEA-funded projects by organizations external to ESH Division. Products generated from the projects funded in FY98 included a new extremity dosimeter that replaced the previously used finger-ring dosimeters, a light and easy-to-use detector to measure energy deposited by neutron interactions, and a device that will allow workers to determine the severity of a hazard.

Technical reliability of geological disposal for high-level radioactive wastes in Japan. The second progress report. Part 3. Safety assessment for geological disposal systems

International Nuclear Information System (INIS)

1999-11-01

Based on the Advisory Committee Report on Nuclear Fuel Cycle Backend Policy submitted to the Japanese Government in 1997, JNC documents the progress of research and development program in the form of the second progress report (the first one published in 1992). It summarizes an evaluation of the technical reliability and safety of the geological disposal concept for high-level radioactive wastes (HLW) in Japan. The present document, the part 3 of the progress report, concerns safety assessment for geological disposal systems definitely introduced in part 1 and 2 of this series and consists of 9 chapters. Chapter I concerns the methodology for safety assessment while Chapter II deals with diversity and uncertainty about the scenario, the adequate model and the required data of the systems above. Chapter III summarizes the components of the geological disposal system. Chapter IV refers to the relationship between radioactive wastes and human life through groundwater, i.e. nuclide migration. In Chapter V is made a reference case which characterizes the geological environmental data using artificial barrier specifications. (Ohno. S.)

Active sites environmental monitoring program FY 1997 annual report

International Nuclear Information System (INIS)

Morrissey, C.M.; Marshall, D.S.; Cunningham, G.R.

1998-03-01

This report summarizes the activities conducted by the Active Sites Environmental Monitoring Program (ASEMP) from October 1996 through September 1997. The purpose of the program is to provide early detection and performance monitoring at active low-level waste (LLW) disposal sites in Solid Waste Storage Area (SWSA) 6 and transuranic (TRU) waste storage sites in SWSA 5 North. This report continues a series of annual and semiannual reports that present the results of ASEMP monitoring activities. This report details monitoring results for fiscal year (FY) 1997 from SWSA 6, including the Interim Waste Management Facility (IWMF) and the Hillcut Disposal Test Facility (HDTF), and (2) TRU-waste storage areas in SWSA 5 N. This report presents a summary of the methodology used to gather data for each major area along with the FY 1997 results. Figures referenced in the text are found in Appendix A and data tables are presented in Appendix B

Idaho National Laboratory’s FY09 & FY10 Greenhouse Gas Report

Energy Technology Data Exchange (ETDEWEB)

Jennifer D. Morton

2011-06-01

A greenhouse gas (GHG) inventory is a systematic approach to account for the production and release of certain gases generated by an institution from various emission sources. The gases of interest are those that climate science has identified as related to anthropogenic global climate change. This document presents an inventory of GHGs generated during fiscal year (FY) 2009 and 2010 by Idaho National Laboratory (INL), a Department of Energy (DOE)-sponsored entity, located in southeastern Idaho. In recent years, concern has grown about the environmental impact of GHGs. This, together with a desire to decrease harmful environmental impacts, would be enough to encourage the calculation of an inventory of the total GHGs generated at INL. Additionally, INL has a desire to see how its emissions compare with similar institutions, including other DOE national laboratories. Executive Order 13514 requires that federal agencies and institutions document reductions in GHG emissions. INL's GHG inventory was calculated according to methodologies identified in federal GHG guidance documents using operational control boundaries. It measures emissions generated in three scopes: (1) INL emissions produced directly by stationary or mobile combustion and by fugitive emissions, (2) the share of emissions generated by entities from which INL purchased electrical power, and (3) indirect or shared emissions generated by outsourced activities that benefit INL (occur outside INL's organizational boundaries, but are a consequence of INL's activities). This inventory found that INL generated 103,590 and 102,413 MT of CO2-equivalent emissions during FY09 and FY10, respectively. The following conclusions were made from looking at the results of the individual contributors to INL's FY09 and FY10 GHG inventories: (1) Electricity (including the associated transmission and distribution losses) is the largest contributor to INL's GHG inventory, with over 50% of the CO2e

Energy Storage Annual Progress Report for FY15

Energy Technology Data Exchange (ETDEWEB)

Pesaran, Ahmad [National Renewable Energy Lab. (NREL), Golden, CO (United States); Ban, Chunmei [National Renewable Energy Lab. (NREL), Golden, CO (United States); Cao, Lei [National Renewable Energy Lab. (NREL), Golden, CO (United States); Graf, Peter [National Renewable Energy Lab. (NREL), Golden, CO (United States); Keyser, Matt [National Renewable Energy Lab. (NREL), Golden, CO (United States); Kim, Gi-Heon [National Renewable Energy Lab. (NREL), Golden, CO (United States); Santhanagopalan, Shriram [National Renewable Energy Lab. (NREL), Golden, CO (United States); Saxon, Aron [National Renewable Energy Lab. (NREL), Golden, CO (United States); Shi, Ying [National Renewable Energy Lab. (NREL), Golden, CO (United States); Smith, Kandler [National Renewable Energy Lab. (NREL), Golden, CO (United States); Tenent, Robert [National Renewable Energy Lab. (NREL), Golden, CO (United States); Yang, Chuanbo [National Renewable Energy Lab. (NREL), Golden, CO (United States); Zhang, Chao [National Renewable Energy Lab. (NREL), Golden, CO (United States)

2016-12-01

The Energy Storage research and development (R&D) subprogram within the DOE Vehicle Technologies Office (VTO) provides support and guidance for projects focusing on batteries for plug-in electric vehicles (PEVs) in support of the EV Everywhere Grand Challenge. PEVs could have a significant impact on the nation's goal of reducing dependence on imported oil and gaseous pollutant emissions. The Energy Storage program targets overcoming technical barriers to enable market success, including: (1) significantly reducing battery cost; (2) increasing battery performance (power, energy, durability); (3) reducing battery weight and volume; and (4) increasing battery tolerance to abusive conditions such as short circuit, overcharge, and crush. The National Renewable Energy Laboratory (NREL) supports the VTO's Energy Storage program by evaluating the thermal performance of cells and packs, developing electrochemical-thermal models to accelerate the design cycle for developing batteries, investigating the behavior of lithium-ion batteries under abuse conditions such as crush, enhancing the durability of electrodes by coatings such as atomic layer deposition, synthesis of materials for higher energy density batteries, and conducting techno-economic analysis of batteries in various electric-drive vehicles. This report describes the progress made by NREL on the research and development projects funded by the DOE VTO Energy Storage subprogram in FY15.

Los Alamos Waste Management FY96 and FY97 Tactical Plan, March 1, 1996

International Nuclear Information System (INIS)

1996-01-01

The Los Alamos National Laboratory (LANL) Waste Management Program (WMP) began a transition to become a open-quotes best of classclose quotes waste management program during fiscal year 1995 (FY95). A best of class waste management program means that LANL will provide cost-effective and compliant management of the minimum amount of waste. In FY94, the WMP could be characterized as a level of effort program requiring several new facilities and new LANL-developed technologies to carry out its waste management responsibilities. By the end of FY95, significant progress had been made in the transition to best of class. The FY96 WMP is realigned and reorganized. Its budget and scope of work are built upon discrete work packages. It is committed to achieving improved cost-effectiveness, providing significant tangible technical results, and to having its performance measured. During FY95, over $11,000,000 in facility and operational costs were avoided. The need for three new major facilities was reexamined and lower cost solutions, not requiring the development of new facilities, were agreed to. Technology development activities were terminated and replaced with the use of commercial facilities to achieve aggressive reductions in the Low-Level Mixed Waste legacy inventory. In addition, over $14,000,000 in improved cost-effectiveness has been included in the FY96 Baseline. An overall WMP vision, specific milestones, performance measures, and commitments are in place for FY96 to ensure that LANL continues the transition to a best of class waste management program. The following table identifies the overall vision and success indicators for FY96

FY-1979 progress report. Hydrotransport plugging study.

Energy Technology Data Exchange (ETDEWEB)

Eyler, L.L.; Lombardo, N.J.

1980-01-01

The objective of the Hydrotransport Plugging Study is to investigate phenomena associated with predicting the onset and occurrence of plugging in pipeline transport of coal. This study addresses large particle transport plugging phenomena that may be encountered in run-of-mine operations. The project is being conducted in four tasks: review and analysis of current capabilities and available data, analytical modeling, experimental investigations, and unplugging and static start-up. This report documents work completed in FY-1979 as well as work currently in progress. A review of currently available prediction methods was completed. Applicability of the methods to large particle hydrotransport and the prediction of plugging was evaluated. It was determined that available models were inadequate, either because they are empirical and tuned to a given solid or because they are simplified analytical models incapable of accounting for a wide range of parameters. Complicated regression curve fit models lacking a physical basis cannot be extrapolated with confidence. Several specific conclusions were reached: Recent developments in mechanistic modeling, describing flow conditions at the limit of stationary deposition, provide the best basis for prediction and extrapolation of large particle flow. Certain modeled phenomena require further analytical and experimental investigation to improve confidence levels. Experimental work needs to be performed to support modeling and to provide an adequate data base for comparison purposes. No available model permits treatment of solids mixtures such as coal and rock.

Present status of refining and conversion facility dismantling. Progress in latter half of 2010FY

International Nuclear Information System (INIS)

Kado, Kazumi; Sugitsue, Noritake; Morimoto, Yasuyuki; Ikegami, Sohei; Tanaka, Yoshio; Takahashi, Nobuo; Tokuyasu, Takashi

2011-09-01

The Refining and Conversion Facility located in the Ningyo-toge Environmental Engineering Center had the natural uranium conversion process and reprocessed uranium conversion process. The construction of this facility was started in 1979 and completed in October 1981. Dismantling of equipments in radiation controlled area of this facility was started from 2008. Equipments in radiation controlled area (excluding ventilating equipment and liquid waste treatment equipment) will be dismantled by the 2011 fiscal year, and ventilating equipment and liquid waste treatment equipment will be dismantled by the 2014 fiscal year. This report describes the master plan of this decommissioning and shows as the progress in latter half year of 2010FY, the actual time schedule, the method of decommissioning, the decommissioning progress appearance with photographs, work rates of each room / each worker class, and the quantity of dismantled materials and secondary wastes. (author)

NATURAL BARRIERS TARGETED THRUST FY 2004 PROJECTS

International Nuclear Information System (INIS)

NA

2005-01-01

This booklet contains project descriptions of work performed by the Department of Energy (DOE), Office of Civilian Radioactive Waste Management (OCRWM), Office of Science and Technology and International's (OSTandI) Natural Barriers Targeted Thrust during Fiscal Year (FY) 2004. The Natural Barriers Targeted Thrust is part of OSTandI's Science and Technology Program which supports the OCRWM mission to manage and dispose of high-level radioactive waste and spent nuclear fuel in a manner that protects health, safety, and the environment; enhances national and energy security; and merits public confidence. In general, the projects described will continue beyond FY 2004 assuming that the technical work remains relevant to the proposed Yucca Mountain Repository and sufficient funding is made available to the Science and Technology Program

Results of Tritium Tracking and Groundwater Monitoring at the Hanford Site 200 Area State-Approved Land Disposal Site-FY 1999

International Nuclear Information System (INIS)

Barnett, D.B.

1999-01-01

The Hanford Site 200 Area Effluent Treatment Facility (ETF) processes contaminated liquids derived from Hanford Site facilities. The clean water generated by these processes is occasionally enriched in tritium and is discharged to the 200 Area State Approved Land Disposal Site (SALDS). Groundwater monitoring for tritium and other constituents is required by the state-issued permit at 21 wells surrounding the facility. During FY 1999, average tritium activities in most wells declined from average activities in 1998. The exception was deep well 69948-77C, where tritium results were at an all-time high (77,000 pCi/L) as a result of the delayed penetration of effluent deeper into the aquifer. Of the 12 constituents with permit enforcement limits, which are monitored in SALDS proximal wells, all were within limits during FY 1999. Water level measurements in nearby wells indicate that a small hydraulic mound exists around the SALDS facility as a result of discharges. This feature is directing groundwater flow radially outward a short distance before the regional northeasterly flow predominates. Evaluation of this condition indicates that the network is currently adequate for tracking potential effects of the SALDS on the groundwater. Recommendations include the discontinuation of ammonia, benzene, tetrahydrofuran, and acetone from the regular groundwater constituent list; designating background well 299-W8-1 as a tritium-tracking well only, and the use of quadruplicate averages of field pH, instead of a single laboratory measurement, as a permit compliance parameter

Approaches to LLW disposal site selection and current progress of host states

International Nuclear Information System (INIS)

Walsh, J.J.; Kerr, T.A.

1990-11-01

In accordance with the Low-Level Radioactive Waste Policy Amendments Act of 1985 and under the guidance of 10 CFR 61, States have begun entering into compacts to establish and operate regional disposal facilities for low-level radioactive waste. The progress a state makes in implementing a process to identify a specific location for a disposal site is one indication of the level of a state's commitment to meeting its responsibilities under Federal law and interstate compact agreements. During the past few years, several States have been engaged in site selection processes. The purpose of this report is to summarize the site selection approaches of some of the Host States (California, Michigan, Nebraska, New York, North Carolina, Texas, and Illinois), and their progress to date. An additional purpose of the report is to discern whether the Host States's site selection processes were heavily influenced by any common factors. One factor each state held in common was that political and public processes exerted a powerful influence on the site selection process at virtually every stage. 1 ref

Biological and Environmental Research Program at Oak Ridge National Laboratory, FY 1992--1994

International Nuclear Information System (INIS)

1992-01-01

This report is the 1992--1994 Program Director's Overview Report for Oak Ridge National Laboratory's (ORNL's) Biological and Environmental Research (BER) Program, and as such it addresses KP-funded work at ORNL conducted during FY 1991 and in progress during FY 1992; it also serves as a planning document for the remainder of FY 1992 through FY 1994. Non-BER funded work at ORNL relevant to the mission of OHER is also discussed. The second section of the report describes ORNL facilities and resources used by the BER program. The third section addresses research management practices at ORNL. The fourth, fifth, and sixth sections address BER-funded research in progress, program accomplishments and research highlights, and program orientation for the remainder of FY 1992 through FY 1994, respectively. Work for non-BER sponsors is described in the seventh section, followed by a discussion of significant near and long-term issues facing BER work at ORNL in the eighth section. The last section provides a statistical summary of BER research at ORNL. Appendices supplement the above topics with additional detail

Summary of the Hanford Site decontamination, decommissioning, and cleanup, FY 1974--FY 1990

International Nuclear Information System (INIS)

Wahlen, R.K.

1991-08-01

At the end of World War II, the demand for more production along with process and military surveillance changes at the Hanford Site caused a continuing cycle of building and obsolescence. This trend continued until 1964, when the cutback in plutonium production began. The cutback caused the shutdown of excess production facilities. The last of eight reactors was shut down in 1971. Since that time, N Reactor has been the only production reactor that has operated. In addition, changes in the method of separating plutonium caused a number of excess facilities in the 200 Areas. Before 1973, no structured program existed for the disposal of unusable facilities or for general cleanup. Following a plant-wide safety and housekeeping inspection in 1973, a program was developed for the disposal of all surplus facilities. Since the start of FY 1974, a total of 46 radioactively contaminated sites have been demolished and disposed of. In addition, 28 buildings have been decontaminated for in situ disposal or for reuse, 21 contaminated sites have been stabilized, 131 clean structures have been removed, and 93 clean sites have received special remedial action to eliminate potential safety and/or environmental hazards. This report summarizes these activities. 3 refs, 1 fig., 18 tabs

Solid waste integrated forecast technical (SWIFT) report: FY1997 to FY 2070, Revision 1

International Nuclear Information System (INIS)

Valero, O.J.

1997-01-01

This web site provides an up-to-date report on the radioactive solid waste expected to be managed by Hanford's Waste Management (WM) Project from onsite and offsite generators. It includes: an overview of Hanford-wide solid waste to be managed by the WM Project; program-level and waste class-specific estimates; background information on waste sources; and comparisons with previous forecasts and with other national data sources. This web site does not include: liquid waste (current or future generation); waste to be managed by the Environmental Restoration (EM-40) contractor (i.e., waste that will be disposed of at the Environmental Restoration Disposal Facility (ERDF)); or waste that has been received by the WM Project to date (i.e., inventory waste). The focus of this web site is on low-level mixed waste (LLMW), and transuranic waste (both non-mixed and mixed) (TRU(M)). Some details on low-level waste and hazardous waste are also provided. Currently, this web site is reporting data that was requested on 10/14/96 and submitted on 10/25/96. The data represent a life cycle forecast covering all reported activities from FY97 through the end of each program's life cycle. Therefore, these data represent revisions from the previous FY97.0 Data Version, due primarily to revised estimates from PNNL. There is some useful information about the structure of this report in the SWIFT Report Web Site Overview

NATURAL BARRIERS TARGETED THRUST FY 2004 PROJECTS

Energy Technology Data Exchange (ETDEWEB)

NA

2005-07-27

This booklet contains project descriptions of work performed by the Department of Energy (DOE), Office of Civilian Radioactive Waste Management (OCRWM), Office of Science and Technology and International's (OST&I) Natural Barriers Targeted Thrust during Fiscal Year (FY) 2004. The Natural Barriers Targeted Thrust is part of OST&I's Science and Technology Program which supports the OCRWM mission to manage and dispose of high-level radioactive waste and spent nuclear fuel in a manner that protects health, safety, and the environment; enhances national and energy security; and merits public confidence. In general, the projects described will continue beyond FY 2004 assuming that the technical work remains relevant to the proposed Yucca Mountain Repository and sufficient funding is made available to the Science and Technology Program.

Progress in welding studies for Canadian nuclear fuel waste disposal containers

International Nuclear Information System (INIS)

Maak, P.Y.Y.

1985-11-01

This report describes the progress in the development of closure-welding technology for Canadian nuclear fuel waste disposal containers. Titanium, copper and Inconel 625 are being investigated as candidate materials for fabrication of these containers. Gas-tungsten-arc welding, gas metal-arc-welding, resistance-heated diffusion bonding and electron beam welding have been evaluated as candidate closure welding processes. Characteristic weldment properties, relative merits of welding techniques, suitable weld joint configurations and fit-up tolerances, and welding parameter control ranges have been identified for various container designs. Furthermore, the automation requirements for candidate welding processes have been assessed. Progress in the development of a computer-controlled remote gas-shielded arc welding system is described

Biological and Environmental Research Program at Oak Ridge National Laboratory, FY 1992--1994

Energy Technology Data Exchange (ETDEWEB)

1992-01-01

This report is the 1992--1994 Program Director's Overview Report for Oak Ridge National Laboratory's (ORNL's) Biological and Environmental Research (BER) Program, and as such it addresses KP-funded work at ORNL conducted during FY 1991 and in progress during FY 1992; it also serves as a planning document for the remainder of FY 1992 through FY 1994. Non-BER funded work at ORNL relevant to the mission of OHER is also discussed. The second section of the report describes ORNL facilities and resources used by the BER program. The third section addresses research management practices at ORNL. The fourth, fifth, and sixth sections address BER-funded research in progress, program accomplishments and research highlights, and program orientation for the remainder of FY 1992 through FY 1994, respectively. Work for non-BER sponsors is described in the seventh section, followed by a discussion of significant near and long-term issues facing BER work at ORNL in the eighth section. The last section provides a statistical summary of BER research at ORNL. Appendices supplement the above topics with additional detail.

Used fuel disposition research and development roadmap - FY10 status.

Energy Technology Data Exchange (ETDEWEB)

Nutt, W. M. (Nuclear Engineering Division)

2010-10-01

Since 1987 the U.S. has focused research and development activities relevant to the disposal of commercial used nuclear fuel and U.S. Department of Energy (DOE) owned spent nuclear fuel and high level waste on the proposed repository at Yucca Mountain, Nevada. At the same time, the U.S. successfully deployed a deep geologic disposal facility for defense-related transuranic waste in bedded salt at the Waste Isolation Pilot Plant. In 2009 the DOE established the Used Fuel Disposition Campaign (UFDC) within the Office of Nuclear Energy. The Mission of the UFDC is to identify alternatives and conduct scientific research and technology development to enable storage, transportation and disposal of used nuclear fuel and wastes generated by existing and future nuclear fuel cycles. The U.S. national laboratories have participated on these programs and has conducted research and development related to these issues to a limited extent. However, a comprehensive research and development (R&D) program investigating a variety of geologic media has not been a part of the U.S. waste management program since the mid 1980s. Such a comprehensive R&D program is being developed in the UFDC with a goal of meeting the UFDC Grand Challenge to provide a sound technical basis for absolute confidence in the safety and security of long-term storage, transportation, and disposal of used nuclear fuel and wastes from the nuclear energy enterprise. The DOE has decided to no longer pursue the development of a repository at Yucca Mountain, Nevada. Since a repository site will ultimately have to be selected, sited, characterized, designed, and licensed, other disposal options must now be considered. In addition to the unsaturated volcanic tuff evaluated at Yucca Mountain, several different geologic media are under investigation internationally and preliminary assessments indicate that disposal of used nuclear fuel and high level waste in these media is feasible. Considerable progress has been made in

Used fuel disposition research and development roadmap - FY10 status

International Nuclear Information System (INIS)

Nutt, W.M.

2010-01-01

Since 1987 the U.S. has focused research and development activities relevant to the disposal of commercial used nuclear fuel and U.S. Department of Energy (DOE) owned spent nuclear fuel and high level waste on the proposed repository at Yucca Mountain, Nevada. At the same time, the U.S. successfully deployed a deep geologic disposal facility for defense-related transuranic waste in bedded salt at the Waste Isolation Pilot Plant. In 2009 the DOE established the Used Fuel Disposition Campaign (UFDC) within the Office of Nuclear Energy. The Mission of the UFDC is to identify alternatives and conduct scientific research and technology development to enable storage, transportation and disposal of used nuclear fuel and wastes generated by existing and future nuclear fuel cycles. The U.S. national laboratories have participated on these programs and has conducted research and development related to these issues to a limited extent. However, a comprehensive research and development (R and D) program investigating a variety of geologic media has not been a part of the U.S. waste management program since the mid 1980s. Such a comprehensive R and D program is being developed in the UFDC with a goal of meeting the UFDC Grand Challenge to provide a sound technical basis for absolute confidence in the safety and security of long-term storage, transportation, and disposal of used nuclear fuel and wastes from the nuclear energy enterprise. The DOE has decided to no longer pursue the development of a repository at Yucca Mountain, Nevada. Since a repository site will ultimately have to be selected, sited, characterized, designed, and licensed, other disposal options must now be considered. In addition to the unsaturated volcanic tuff evaluated at Yucca Mountain, several different geologic media are under investigation internationally and preliminary assessments indicate that disposal of used nuclear fuel and high level waste in these media is feasible. Considerable progress has been

FY2016 Update on ILAW Glass Testing for Disposal at IDF

Energy Technology Data Exchange (ETDEWEB)

Brown, E. E. [Hanford Site (HNF), Richland, WA (United States); Swanberg, D. J. [Hanford Site (HNF), Richland, WA (United States); Muller, Isabelle S. [The Catholic Univ. of America, Washington, DC (United States); Pegg, Ian L. [The Catholic Univ. of America, Washington, DC (United States)

2017-04-12

This status report provides a FY2016 update on work performed to collect information on the corrosion behavior of LAW glasses to support the IDF PA. In addition to the development of the baseline operating envelope for the WTP, since 2003, VSL has developed a wide range of LAW formulations that achieve considerably higher waste loadings than the WTP baseline formulations.

Technology Development, Evaluation, and Application (TDEA) FY 2001 Progress Report Environment, Safety, and Health (ESH) Division

Energy Technology Data Exchange (ETDEWEB)

L.G. Hoffman; K. Alvar; T. Buhl; E. Foltyn; W. Hansen; B. Erdal; P. Fresquez; D. Lee; B. Reinert

2002-05-01

This progress report presents the results of 11 projects funded ($500K) in FY01 by the Technology Development, Evaluation, and Application (TDEA) Committee of the Environment, Safety, and Health Division (ESH). Five projects fit into the Health Physics discipline, 5 projects are environmental science and one is industrial hygiene/safety. As a result of their TDEA-funded projects, investigators have published sixteen papers in professional journals, proceedings, or Los Alamos reports and presented their work at professional meetings. Supplement funds and in-kind contributions, such as staff time, instrument use, and workspace, were also provided to TDEA-funded projects by organizations external to ESH Divisions.

Technology Development, Evaluation, and Application (TDEA) FY 1999 Progress Report, Environment, Safety, and Health (ESH) Division

International Nuclear Information System (INIS)

Hoffman, Larry G.

2000-01-01

This progress report presents the results of 10 projects funded ($500K) in FY99 by the Technology Development, Evaluation, and Application (TDEA) Committee of the Environment, Safety, and Health Division. Five are new projects for this year; seven projects have been completed in their third and final TDEA-funded year. As a result of their TDEA-funded projects, investigators have published thirty-four papers in professional journals, proceedings, or Los Alamos reports and presented their work at professional meetings. Supplemental funds and in-kind contributions, such as staff time, instrument use, and work space, were also provided to TDEA-funded projects by organizations external to ESH Division

Technology Development, Evaluation, and Application (TDEA) FY 1999 Progress Report, Environment, Safety, and Health (ESH) Division

Energy Technology Data Exchange (ETDEWEB)

Larry G. Hoffman

2000-12-01

This progress report presents the results of 10 projects funded ($500K) in FY99 by the Technology Development, Evaluation, and Application (TDEA) Committee of the Environment, Safety, and Health Division. Five are new projects for this year; seven projects have been completed in their third and final TDEA-funded year. As a result of their TDEA-funded projects, investigators have published thirty-four papers in professional journals, proceedings, or Los Alamos reports and presented their work at professional meetings. Supplemental funds and in-kind contributions, such as staff time, instrument use, and work space, were also provided to TDEA-funded projects by organizations external to ESH Division.

Using Automation to Monitor and Report Hazardous Waste Disposal Costs: A Mission-Critical Obligation

National Research Council Canada - National Science Library

Hassrick, H

1996-01-01

Controlling, monitoring, and reporting hazardous waste disposal costs has become increasingly important as environmental problems arise, costs escalate, and budgets contract. In FY94, the U.S. Army, Europe (USAREUR), spent...

Geological disposal of high level radioactive waste in China: progress during 1985-2004

International Nuclear Information System (INIS)

Wang Ju; Xu Guoqing; Zheng Hualing; Fan Xianhua; Wang Chengzu; Fan Zhiwen

2005-01-01

Safe disposal of high level radioactive waste (HLW) is a challenging issue for the sustainable development of nuclear energy. The studies for the disposal of HLW in China started in 1985, the proposed goal was to build China's high level waste repository by mid-21st Century, while the waste to be disposed of will be vitrified waste, transuranic waste and small amount of spent fuel. The proposed repository was a shaft-tunnel-silo model hosted by granite in saturated zone. In the period of 1985 to 2004, progress was made in China's HLW disposal program. It was decided that 'deep geological disposal' will be used to dispose of China's HLW, while the technical strategy for the development of repository will a 3-step strategy, that includes steps of site selection and site evaluation, construction of underground research laboratory, and construction of repository. Based on nation wide screening, the Beishan area, Gansu Province, northwestern China, located in Gobi desert area with few inhabitants, integral crust structure and favorable geological and hydrogeological conditions, was selected as the most potential area for China's repository. In early 1990's, site selection for underground research laboratory was conducted, 2 sites in the suburb of Beijing were preliminarily selected as the potential sites for a 'generic underground research laboratory'. It was determined to use bentonite as backfill material for the repository, while the bentonite from Gaomiaozi deposit in Inner Mongolia was selected as potential buffer and backfill material for China's repository. The studies on the mineralogical, geotechnical, physico-mechanical and thermal properties of the Gaomiaozi bentonite have been conducting. Some parameters such as sorption radio, diffusion coefficient and dispersion coefficient of radionuclides (Np, Pu and Tc) in Beishan granite and bentonite have been obtained. A low-oxygen glove box and a device simulating the temperature, pressure and redox potential of

Spent fuel sabotage aerosol test program :FY 2005-06 testing and aerosol data summary

International Nuclear Information System (INIS)

Gregson, Michael Warren; Brockmann, John E.; Nolte, O.; Loiseau, O.; Koch, W.; Molecke, Martin Alan; Autrusson, Bruno; Pretzsch, Gunter Guido; Billone, M. C.; Lucero, Daniel A.; Burtseva, T.; Brucher, W; Steyskal, Michele D.

2006-01-01

This multinational, multi-phase spent fuel sabotage test program is quantifying the aerosol particles produced when the products of a high energy density device (HEDD) interact with and explosively particulate test rodlets that contain pellets of either surrogate materials or actual spent fuel. This program has been underway for several years. This program provides source-term data that are relevant to some sabotage scenarios in relation to spent fuel transport and storage casks, and associated risk assessments. This document focuses on an updated description of the test program and test components for all work and plans made, or revised, primarily during FY 2005 and about the first two-thirds of FY 2006. It also serves as a program status report as of the end of May 2006. We provide details on the significant findings on aerosol results and observations from the recently completed Phase 2 surrogate material tests using cerium oxide ceramic pellets in test rodlets plus non-radioactive fission product dopants. Results include: respirable fractions produced; amounts, nuclide content, and produced particle size distributions and morphology; status on determination of the spent fuel ratio, SFR (the ratio of respirable particles from real spent fuel/respirables from surrogate spent fuel, measured under closely matched test conditions, in a contained test chamber); and, measurements of enhanced volatile fission product species sorption onto respirable particles. We discuss progress and results for the first three, recently performed Phase 3 tests using depleted uranium oxide, DUO 2 , test rodlets. We will also review the status of preparations and the final Phase 4 tests in this program, using short rodlets containing actual spent fuel from U.S. PWR reactors, with both high- and lower-burnup fuel. These data plus testing results and design are tailored to support and guide, follow-on computer modeling of aerosol dispersal hazards and radiological consequence assessments

Progress and future direction for the interim safe storage and disposal of Hanford high level waste (HLW)

International Nuclear Information System (INIS)

Wodrich, D.D.

1996-01-01

This paper describes the progress made at the largest environmental cleanup program in the United States. Substantial advances in methods to start interim safe storage of Hanford Site high-level wastes, waste characterization to support both safety- and disposal-related information needs, and proceeding with cost-effective disposal by the US DOE and its Hanford Site contractors, have been realized. Challenges facing the Tank Waste Remediation System Program, which is charged with the dual and parallel missions of interim safe storage and disposal of the high-level tank waste stored at the Hanford Site, are described

Study of applicable methods on safety verification of disposal facilities and waste packages

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

Three subjects about safety verification on the disposal of low level radioactive waste were investigated in FY. 2012. For radioactive waste disposal facilities, specs and construction techniques of covering with soil to prevent possible destruction caused by natural events (e.g. earthquake) were studied to consider verification methods for those specs. For waste packages subject to near surface pit disposal, settings of scaling factor and average radioactivity concentration (hereafter referred to as ''SF'') on container-filled and solidified waste packages generated from Kashiwazaki Kariwa Nuclear Power Station Unit 1-5, setting of cesium residual ratio of molten solidified waste generated from Tokai and Tokai No.2 Power Stations, etc. were studied. Those results were finalized in consideration of the opinion from advisory panel, and publicly opened as JNES-EV reports. In FY 2012, five JNES reports were published and these have been used as standards of safety verification on waste packages. The verification method of radioactive wastes subject to near-surface trench disposal and intermediate depth disposal were also studied. For radioactive wastes which will be returned from overseas, determination methods of radioactive concentration, heat rate and hydrogen generation rate of CSD-C were established. Determination methods of radioactive concentration and heat rate of CSD-B were also established. These results will be referred to verification manuals. (author)

Technical reliability of geological disposal for high-level radioactive wastes in Japan. The second progress report. Part 1. Geological environment of Japan

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-11-01

Based on the Advisory Committee Report on Nuclear Fuel Cycle Backend Policy submitted to the Japanese Government in 1997, JNC documents the progress of research and development program in the form of the second progress report (the first one published in 1992). It summarizes an evaluation of the technical reliability and safety of the geological disposal concept for high-level radioactive wastes (HLW) in Japan. The present document, the part 1 of the progress report, describes first in detail the role of geological environment in high-level radioactive wastes disposal, the features of Japanese geological environment, and programs to proceed the investigation in geological environment. The following chapter summarizes scientific basis for possible existence of stable geological environment, stable for a long period needed for the HLW disposal in Japan including such natural phenomena as volcano and faults. The results of the investigation of the characteristics of bed-rocks and groundwater are presented. These are important for multiple barrier system construction of deep geological disposal. The report furthermore describes the present status of technical and methodological progress in investigating geological environment and finally on the results of natural analog study in Tono uranium deposits area. (Ohno, S.)

MELCOR/CONTAIN LMR Implementation Report - FY16 Progress.

Energy Technology Data Exchange (ETDEWEB)

Louie, David [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Humphries, Larry L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2016-11-01

This report describes the progress of the CONTAIN - LMR sodium physics and chemistry models to be implemented in MELCOR 2.1. In the past three years , the implementation included the addition of sodium equations of state and sodium properties from two different sources. The first source is based on the previous work done by Idaho National Laboratory by modifying MELCOR to include liquid lithium equation of state as a working fluid to model the nuclear fusion safety research. The second source uses properties generated for the SIMMER code. The implemented modeling has been tested and results are reported in this document. In addition, the CONTAIN - LMR code was derived from an early version of the CONTAIN code, and many physical models that were developed since this early version of CONTAIN are not available in this early code version. Therefore, CONTAIN 2 has been updated with the sodium models in CONTAIN - LMR as CONTAIN2 - LMR, which may be used to provide code-to-code comparison with CONTAIN - LMR and MELCOR when the sodium chemistry models from CONTAIN - LMR have been completed. Both the spray fire and pool fire chemistry routines from CONTAIN - LMR have been integrated into MELCOR 2.1, and debugging and testing are in progress. Because MELCOR only models the equation of state for liquid and gas phases of the coolant, a modeling gap still exists when dealing with experiments or accident conditions that take place when the ambient temperature is below the freezing point of sodium. An alternative method is under investigation to overcome this gap . We are no longer working on the separate branch from the main branch of MELCOR 2.1 since the major modeling of MELCOR 2.1 has been completed. At the current stage, the newly implemented sodium chemistry models will be a part of the main MELCOR release version (MELCOR 2.2). This report will discuss the accomplishments and issues relating to the implementation. Also, we will report on the planned completion of all

Optimal imaging for treaty verification FY2014 annual report

International Nuclear Information System (INIS)

Hilton, Nathan R.; Johnson, William C.; Brubaker, Erik M.; Kupinski, Matthew Alan; MacGahan, Christopher Jonathan

2014-01-01

FY2014 technical report of our project funded by DNN R&D that leverages advanced inference methods developed for medical and adaptive imaging to address arms control applications. We seek a method to acquire and analyze imaging data of declared treaty-accountable items without creating an image of those objects or otherwise storing or revealing any classified information. Such a method would avoid the use of classified-information barriers. We present our progress on FY2014 tasks defined in our life-cycle plan. We also describe some future work that is part of the continuation of this project in FY2015 and beyond as part of a venture that joins ours with a related PNNL project.

Optimal imaging for treaty verification FY2014 annual report

Energy Technology Data Exchange (ETDEWEB)

Hilton, Nathan R. [Sandia National Lab. (SNL-CA), Livermore, CA (United States); Johnson, William C. [Sandia National Lab. (SNL-CA), Livermore, CA (United States); Brubaker, Erik M. [Sandia National Lab. (SNL-CA), Livermore, CA (United States); Kupinski, Matthew Alan [Univ. of Arizona, Tucson, AZ (United States); MacGahan, Christopher Jonathan [Univ. of Arizona, Tucson, AZ (United States)

2014-10-01

FY2014 technical report of our project funded by DNN R&D that leverages advanced inference methods developed for medical and adaptive imaging to address arms control applications. We seek a method to acquire and analyze imaging data of declared treaty-accountable items without creating an image of those objects or otherwise storing or revealing any classified information. Such a method would avoid the use of classified-information barriers. We present our progress on FY2014 tasks defined in our life-cycle plan. We also describe some future work that is part of the continuation of this project in FY2015 and beyond as part of a venture that joins ours with a related PNNL project.

Current status of the Demonstration Test of Underground Cavern-Type Disposal Facilities

International Nuclear Information System (INIS)

Akiyama, Yoshihiro; Terada, Kenji; Oda, Nobuaki; Yada, Tsutomu; Nakajima, Takahiro

2011-01-01

In Japan, the underground cavern-type disposal facilities for low-level waste (LLW) with relatively high radioactivity, mainly generated from power reactor decommissioning, and for certain transuranic (TRU) waste, mainly from spent fuel reprocessing, are designed to be constructed in a cavern 50-100 m underground and to employ an engineered barrier system (EBS) made of bentonite and cement materials. To advance a disposal feasibility study, the Japanese government commissioned the Demonstration Test of Underground Cavern-Type Disposal Facilities in fiscal year (FY) 2005. Construction of a full-scale mock-up test facility in an actual subsurface environment started in FY 2007. The main test objective is to establish the construction methodology and procedures that ensure the required quality of the EBS on-site. A portion of the facility was constructed by 2010, and the test has demonstrated both the practicability of the construction and the achievement of quality standards: low permeability of less than 5x10 -13 m/s and low-diffusion of less than 1x10 -12 m 2 /s at the completion of construction. This paper covers the test results from the construction of certain parts using bentonite and cement materials. (author)

Waste isolation safety assessment program. Summary of FY-77 progress

International Nuclear Information System (INIS)

Burkholder, H.C.; Greenborg, J.; Stottlemyre, J.A.; Bradley, D.J.; Raymond, J.R.; Serne, R.J.

1977-11-01

Objective is to provide long-term safety information for the National Waste Terminal Storage Program. Work in FY 77 supported the development of the generic assessment method (release scenario analysis, release consequence analysis) and of the generic data base (waste form release rate data, radionuclide geochemical interaction data)

Technical reliability of geological disposal for high-level radioactive wastes in Japan. The second progress report. Introductory part and summaries

International Nuclear Information System (INIS)

1999-11-01

Based on the Advisory Committee Report on Nuclear Fuel Cycle Backend Policy submitted to the Japanese Government in 1997, JNC documents the progress of research and development program in the form of the second progress report (the first one published in 1992). It summarizes an evaluation of the technical reliability and safety of the geological disposal concept for high-level radioactive wastes (HLW) in Japan and comprises seven chapters. Chapter I briefly describes the importance of HLW management in promoting nuclear energy utilization. According to the long-term program, the HLW separated from spent fuels at reprocessing plants is to be vitrified and stored for a period of 30 to 50 years to allow cooling, then be disposed of in a deep geological formation. Chapter II mainly explains the concepts of geological disposal in Japan. Chapters III to V are devoted to discussions on three important technical elements (the geological environment of Japan, engineering technology and safety assessment of the geological disposal system) which are necessary for reliable realization of the geological disposal concept. Chapter VI demonstrates the technical ground for site selection and for setup of safety standards of the disposal. Chapter VII summarizes together with plans for future research and development. (Ohno, S.)

Waste Generation Forecast for DOE-ORO's Environmental Restoration OR-1 Project: FY 1994--FY 2001

International Nuclear Information System (INIS)

1993-12-01

This Waste Generation Forecast for DOE-ORO's Environmental Restoration OR-1 Project. FY 1994--FY 2001 is the third in a series of documents that report current estimates of the waste volumes expected to be generated as a result of Environmental Restoration activities at Department of Energy, Oak Ridge Operations Office (DOE-ORO), sites. Considered in the scope of this document are volumes of waste expected to be generated as a result of remedial action and decontamination and decommissioning activities taking place at these sites. Sites contributing to the total estimates make up the DOE-ORO Environmental Restoration OR-1 Project: the Oak Ridge K-25 Site, the Oak Ridge National Laboratory, the Y-12 Plant, the Paducah Gaseous Diffusion Plant, the Portsmouth Gaseous Diffusion Plant, and the off-site contaminated areas adjacent to the Oak Ridge facilities (collectively referred to as the Oak Ridge Reservation Off-Site area). Estimates are available for the entire fife of all waste generating activities. This document summarizes waste estimates forecasted for the 8-year period of FY 1994-FY 2001. Updates with varying degrees of change are expected throughout the refinement of restoration strategies currently in progress at each of the sites. Waste forecast data are relatively fluid, and this document represents remediation plans only as reported through September 1993

Final Report: 06-LW-013, Nuclear Physics the Monte Carlo Way

International Nuclear Information System (INIS)

Ormand, W.E.

2009-01-01

This is document reports the progress and accomplishments achieved in 2006-2007 with LDRD funding under the proposal 06-LW-013, 'Nuclear Physics the Monte Carlo Way'. The project was a theoretical study to explore a novel approach to dealing with a persistent problem in Monte Carlo approaches to quantum many-body systems. The goal was to implement a solution to the notorious 'sign-problem', which if successful, would permit, for the first time, exact solutions to quantum many-body systems that cannot be addressed with other methods. In this document, we outline the progress and accomplishments achieved during FY2006-2007 with LDRD funding in the proposal 06-LW-013, 'Nuclear Physics the Monte Carlo Way'. This project was funded under the Lab Wide LDRD competition at Lawrence Livermore National Laboratory. The primary objective of this project was to test the feasibility of implementing a novel approach to solving the generic quantum many-body problem, which is one of the most important problems being addressed in theoretical physics today. Instead of traditional methods based matrix diagonalization, this proposal focused a Monte Carlo method. The principal difficulty with Monte Carlo methods, is the so-called 'sign problem'. The sign problem, which will discussed in some detail later, is endemic to Monte Carlo approaches to the quantum many-body problem, and is the principal reason that they have not been completely successful in the past. Here, we outline our research in the 'shifted-contour method' applied the Auxiliary Field Monte Carlo (AFMC) method

SERI Biomass Program. FY 1983 annual report

Energy Technology Data Exchange (ETDEWEB)

Corder, R.E.; Hill, A.M.; Lindsey, H.; Lowenstein, M.Z.; McIntosh, R.P.

1984-02-01

This report summarizes the progress and research accomplishments of the SERI Biomass Program during FY 1983. The SERI Biomass Program consists of three elements: Aquatic Species, Anaerobic Digestion, and Photo/Biological Hydrogen. Each element has been indexed separately. 2 references, 44 figures, 22 tables.

FY 2012 Lightweight Materials Annual Report

Energy Technology Data Exchange (ETDEWEB)

None

2013-04-15

The FY 2012 Annual Progress Report for Lightweight Materials provides a detailed description of the activities and technical accomplishments which focuses on the development and validation of advanced materials and manufacturing technologies to significantly reduce light and heavy duty vehicle weight without compromising other attributes such as safety, performance, recyclability, and cost.

Progress toward disposal of LLRW in Canada

Energy Technology Data Exchange (ETDEWEB)

Charlesworth, D. H.

1989-08-15

Low-level radioactive wastes are managed in Canada currently by interim storage methods operated by the major generators of the wastes. The potential benefits of permanent disposal have led Atomic Energy of Canada Limited to undertake a development and demonstration program to make the transition from storage to disposal at its Chalk River Nuclear Laboratories. The first stages of the demonstration are based on an enhanced version of shallow land burial for the least hazardous wastes, and a unique design of a belowground concrete vault. The program includes the development and testing of the auxiliary equipment, processes and procedures necessary to support the disposal system, as well as the performance assessment methods and information needed to assure its safety.

Progress toward disposal of LLRW in Canada

International Nuclear Information System (INIS)

Charlesworth, D.H.

1989-08-01

Low-level radioactive wastes are managed in Canada currently by interim storage methods operated by the major generators of the wastes. The potential benefits of permanent disposal have led Atomic Energy of Canada Limited to undertake a development and demonstration program to make the transition from storage to disposal at its Chalk River Nuclear Laboratories. The first stages of the demonstration are based on an enhanced version of shallow land burial for the least hazardous wastes, and a unique design of a belowground concrete vault. The program includes the development and testing of the auxiliary equipment, processes and procedures necessary to support the disposal system, as well as the performance assessment methods and information needed to assure its safety

Cementitious Barriers Partnership FY2013 End-Year Report

Energy Technology Data Exchange (ETDEWEB)

Flach, G. P. [Savannah River Site (SRS), Aiken, SC (United States); Langton, C. A. [Savannah River Site (SRS), Aiken, SC (United States); Burns, H. H. [Savannah River Site (SRS), Aiken, SC (United States); Smith, F. G. [Savannah River Site (SRS), Aiken, SC (United States); Kosson, D. S. [Vanderbilt University, School of Engineering, Nashville, TN (United States); Brown, K. G. [Vanderbilt University, School of Engineering, Nashville, TN (United States); Samson, E. [SIMCO Technologies, Inc., Quebec (Canada); Meeussen, J. C.L. [Nuclear Research and Consultancy Group (NRG), Petten (The Netherlands); van der Sloot, H. A. [Hans van der Sloot Consultancy, Langedijk (The Netherlands); Garboczi, E. J. [Materials & Construction Research Division, National Institute of Standards and Technology, Gaithersburg, MD (United States)

2013-11-01

In FY2013, the Cementitious Barriers Partnership (CBP) demonstrated continued tangible progress toward fulfilling the objective of developing a set of software tools to improve understanding and prediction of the long-term structural, hydraulic and chemical performance of cementitious barriers used in nuclear applications. In November 2012, the CBP released “Version 1.0” of the CBP Software Toolbox, a suite of software for simulating reactive transport in cementitious materials and important degradation phenomena. In addition, the CBP completed development of new software for the “Version 2.0” Toolbox to be released in early FY2014 and demonstrated use of the Version 1.0 Toolbox on DOE applications. The current primary software components in both Versions 1.0 and 2.0 are LeachXS/ORCHESTRA, STADIUM, and a GoldSim interface for probabilistic analysis of selected degradation scenarios. The CBP Software Toolbox Version 1.0 supports analysis of external sulfate attack (including damage mechanics), carbonation, and primary constituent leaching. Version 2.0 includes the additional analysis of chloride attack and dual regime flow and contaminant migration in fractured and non-fractured cementitious material. The LeachXS component embodies an extensive material property measurements database along with chemical speciation and reactive mass transport simulation cases with emphasis on leaching of major, trace and radionuclide constituents from cementitious materials used in DOE facilities, such as Saltstone (Savannah River) and Cast Stone (Hanford), tank closure grouts, and barrier concretes. STADIUM focuses on the physical and structural service life of materials and components based on chemical speciation and reactive mass transport of major cement constituents and aggressive species (e.g., chloride, sulfate, etc.). THAMES is a planned future CBP Toolbox component focused on simulation of the microstructure of cementitious materials and calculation of resultant

Development activities on shallow land disposal of solid radioactive waste. Progress report, January--December 1976

International Nuclear Information System (INIS)

1977-06-01

Progress on projects focused on problems of shallow land burial of radioactively contaminated solid waste is summarized. Developments on a system to evaluate the containment adequacy of existing burial sites are described. Efforts to describe the environmental factors in monitoring the LASL disposal sites are discussed. The aim of a new program on radioactive waste burial technology is outlined

FY 1999 Annual Self-Evaluation Report of the Pacific Northwest National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Randy R. LaBarge

1999-11-05

This is a report of the Pacific Northwest National Laboratory's (Pacific Northwest's) FY1999 Annual Self-Evaluation Report. This report summarizes our progress toward accomplishment of the critical outcomes, objectives, and performance indicators as delineated in the FY1999 Performance Evaluation & Fee Agreement. It also summarizes our analysis of the results of Pacific Northwest's Division and Directorate annual self-assessments, and the implementation of our key operational improvement initiatives. Together, these provide an indication of how well we have used our Integrated Assessment processes to identify and plan improvements for FY2000. As you review the report you will find areas of significantly positive progress; you will also note areas where I believe the Laboratory could make improvements. Overall, however, I believe you will be quite pleased to note that we have maintained, or exceeded, the high standards of performance we have set for the Laboratory.

Radioactive waste disposal in UK: progress to date

International Nuclear Information System (INIS)

Folger, Michael

1995-01-01

In this paper, originally presented at a conference organised by the Financial Times, three main topics are covered. First, the current disposal strategies for different classes of waste, taking account of the Government's Consultative Document published recently. Second, an update on site characterisation at Sellafield and on the deep repository programme which will follow if Nirex's work confirms the site can support the demanding safety case disposal of intermediate level waste. Third, comments on costs of various options for waste disposal. (author)

Photovoltaic Subcontract Program, FY 1991

Energy Technology Data Exchange (ETDEWEB)

1992-03-01

This report summarizes the fiscal year (FY) 1991 (October 1, 1990, through September 30, 1991) progress of the subcontracted photovoltaic (PV) research and development (R D) performed under the Photovoltaic Advanced Research and Development Project at the National Renewable Energy Laboratory (NREL) -- formerly the Solar Energy Research Institute (SERI). The mission of the national PV program is to develop PV technology for large-scale generation of economically competitive electric power in the United States. The technical sections of the report cover the main areas of the subcontract program: the Amorphous Silicon Research Project, Polycrystalline Thin Films, Crystalline Silicon Materials Research, High-Efficiency Concepts, the New Ideas Program, the University Participation Program, and the Photovoltaic Manufacturing Technology (PVMaT) project. Technical summaries of each of the subcontracted programs provide a discussion of approaches, major accomplishments in FY 1991, and future research directions.

Tank waste remediation system retrieval and disposal mission phase 1 financial analysis

International Nuclear Information System (INIS)

Wells, M.W.

1998-01-01

The purpose of the Tank Waste Remediation System (TWRS) Retrieval and Disposal Mission Phase 1 Financial Analysis is to provide a quantitative and qualitative cost and schedule risk analysis of HNF-1946, Tank Waste Remediation System Retrieval and Disposal Mission Initial Updated Baseline (Swita et al. 1998). The Updated Baseline (Section 3.0) is compared to the current TWRS Project Multi-Year Work Plan (MYWP) for fiscal year (FY) 1998 and target budgets for FY 1999 through FY 2011 (Section 4.1). The analysis then evaluates the executability of HNF-1946 (Sections 4.2 through 4.5) and recommends a path forward for risk mitigation (Sections 4.6, 4.7, and 5.0). A sound systems engineering approach was applied to understand and analyze the Phase 1B Retrieval and Disposal mission. Program and Level 1 Logics were decomposed to Level 8 of the Work Breakdown Structure (WBS) where logic was detailed, scope was defined, detail durations and estimates prepared, and resource loaded schedules developed. Technical Basis Review (TBR) packages were prepared which include this information and, in addition, defined the enabling assumptions for each task, and the risks associated with performance. This process is discussed in Section 2.1. Detailed reviews at the subactivity within the Level 1 Logic TBR levels were conducted to provide the recommended solution to the Phase 1B Retrieval and Disposal Mission. Independent cost analysis and risk assessments were performed by members of the Lockheed Martin Hanford Corporation (LMHC) Business Management and Chief Financial Officer organization along with specialists in risk analysis from TRW, Inc. and Lockheed Martin Energy Systems. The process evaluated technical, schedule, and cost risk by category (program specific fixed and variable, integrated program, and programmatic) based on risk certainly from high probability well defined to very low probability that is not bounded or priceable as discussed in Section 2.2. The results have been

Benchmark Imagery FY11 Technical Report

Energy Technology Data Exchange (ETDEWEB)

Roberts, R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Pope, P. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2011-06-14

This report details the work performed in FY11 under project LL11-GS-PD06, “Benchmark Imagery for Assessing Geospatial Semantic Extraction Algorithms.” The original LCP for the Benchmark Imagery project called for creating a set of benchmark imagery for verifying and validating algorithms that extract semantic content from imagery. More specifically, the first year was slated to deliver real imagery that had been annotated, the second year to deliver real imagery that had composited features, and the final year was to deliver synthetic imagery modeled after the real imagery.

Application of Generic Disposal System Models

Energy Technology Data Exchange (ETDEWEB)

Mariner, Paul [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hammond, Glenn Edward [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sevougian, S. David [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Stein, Emily [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2015-11-01

This report describes specific GDSA activities in fiscal year 2015 (FY2015) toward the development of the enhanced disposal system modeling and analysis capability for geologic disposal of nuclear waste. The GDSA framework employs the PFLOTRAN thermal-hydrologic-chemical multi-physics code (Hammond et al., 2011) and the Dakota uncertainty sampling and propagation code (Adams et al., 2013). Each code is designed for massively-parallel processing in a high-performance computing (HPC) environment. Multi-physics representations in PFLOTRAN are used to simulate various coupled processes including heat flow, fluid flow, waste dissolution, radionuclide release, radionuclide decay and ingrowth, precipitation and dissolution of secondary phases, and radionuclide transport through the engineered barriers and natural geologic barriers to a well location in an overlying or underlying aquifer. Dakota is used to generate sets of representative realizations and to analyze parameter sensitivity.

Disposal R&D in the Used Fuel Disposition Campaign: A Discussion of Opportunities for Active International Collaboration

Energy Technology Data Exchange (ETDEWEB)

Birkholzer, J.T.

2011-06-01

For DOE's Used Fuel Disposition Campaign (UFDC), international collaboration is a beneficial and cost-effective strategy for advancing disposal science with regards to multiple disposal options and different geologic environments. While the United States disposal program focused solely on Yucca Mountain tuff as host rock over the past decades, several international programs have made significant progress in the characterization and performance evaluation of other geologic repository options, most of which are very different from the Yucca Mountain site in design and host rock characteristics. Because Yucca Mountain was so unique (e.g., no backfill, unsaturated densely fractured tuff), areas of direct collaboration with international disposal programs were quite limited during that time. The decision by the U.S. Department of Energy to no longer pursue the disposal of high-level radioactive waste and spent fuel at Yucca Mountain has shifted UFDC's interest to disposal options and geologic environments similar to those being investigated by disposal programs in other nations. Much can be gained by close collaboration with these programs, including access to valuable experience and data collected over recent decades. Such collaboration can help to efficiently achieve UFDC's long-term goals of conducting 'experiments to fill data needs and confirm advanced modeling approaches' (by 2015) and of having a 'robust modeling and experimental basis for evaluation of multiple disposal system options' (by 2020). This report discusses selected opportunities of active international collaboration, with focus on both Natural Barrier System (NBS) and Engineered Barrier System (EBS) aspects and those opportunities that provide access to field data (and respective interpretation/modeling) or allow participation in ongoing field experiments. This discussion serves as a basis for the DOE/NE-53 and UFDC planning process for FY12 and beyond.

Treatment/Disposal Plan for Drummed Waste from the 300-FF-1 Operable Unit, 618-4 Burial Ground

International Nuclear Information System (INIS)

Lerch, J.A.

1999-01-01

The objective of this plan is to support selection of a safe, environmentally responsible, and cost-effective treatment and disposal method for drums containing depleted uranium metal chips submerged in oil that have been and will be excavated from the 618-4 Burial Ground. Remediation of the 300-FF-1 Operable Unit, 618-4 Burial Ground was initiated in fiscal year (FY) 1998 as an excavation and removal operation. Routine processes were established to excavate and ship contaminated soil and debris to the Environmental Restoration Disposal Facility (ERDF) for disposal

Hearth monitoring project annual report for FY-1981

International Nuclear Information System (INIS)

Nieschmidt, E.B.; Lawrence, R.S.

1981-08-01

Progress during FY 1981 in the Hearth Monitoring project for the Idaho National Engineering Laboratory Transuranic Waste Treatment Facility is reported. Results of calculational, experimental and instrumental phases of the program are presented. Recommendations and plans for continuation of the program are displayed. Schedules for future efforts are included

Developing a low-level radioactive waste disposal facility in Connecticut: Update on progress and new directions

Energy Technology Data Exchange (ETDEWEB)

Gingerich, R.E. [Connecticut Hazardous Waste Management Service, Hartford, CT (United States)

1993-03-01

Connecticut is a member of the Northeast Interstate Low-Level Radioactive Waste Management Compact (Northeast LLRW Compact). The other member of the Northeast LLRW Compact is New Jersey. The Northeast Interstate Low-Level Radioactive Waste Commission (Northeast Compact Commission), the Northeast LLRW Compact`s governing body, has designated both Connecticut and New Jersey as host states for disposal facilities. The Northeast Compact Commission has recommended that, for purposes of planning for each state`s facility, the siting agency for the state should use projected volumes and characteristics of the LLW generated in its own state. In 1987 Connecticut enacted legislation that assigns major responsibilities for developing a LLW disposal facility in Connecticut to the Connecticut Hazardous Waste Management Service (CHWMS). The CHWMS is required to: prepare and revise, as necessary, a LLW Management Plan for the state; select a site for a LLW disposal facility; select a disposal technology to be used at the site; select a firm to obtain the necessary approvals for the facility and to develop and operate it; and serve as the custodial agency for the facility. This paper discusses progress in developing a facility.

NRC perspective on alternative disposal methods

International Nuclear Information System (INIS)

Pittiglio, C.L.; Tokar, M.

1987-01-01

In this paper is discussed an NRC staff strategy for the development of technical criteria and procedures for the licensing of various alternatives for disposal of low-level radioactive waste. Steps taken by the staff to identify viable alternative disposal methods and to comply with the requirements of the Low-Level Radioactive Waste Policy Amendments Act (LLRWPAA) of 1985 are also discussed. The strategy proposed by the NRC staff is to focus efforts in FY 87 on alternative concepts that incorporate concrete materials with soil or rock cover (e.g., below ground vaults and earth-mounded concrete bunkers), which several State and State Compacts have identified as preferred disposal options. While the NRC staff believes that other options, such as above ground vaults and mined cavities, are workable and licensable, the staff also believes, for reasons addressed in the paper, that it is in the best interest of the industry and the public to encourage standardization and to focus limited resources on a manageable number of alternative options. Therefore, guidance on above ground vaults, which are susceptible to long-term materials degradation due to climatological effects, and mined cavities, which represent a significant departure from the current experience base for low-level radioactive waste disposal, will receive minimal attention. 6 references

FY2013 Vehicle and Systems Simulation and Testing R&D Annual Progress Report

Energy Technology Data Exchange (ETDEWEB)

none,

2014-02-01

FY 2013 annual report focuses on the following areas: vehicle modeling and simulation, component and systems evaluations, laboratory and field evaluations, codes and standards, industry projects, and vehicle systems optimization.

Progress report for 1988/89 from the Waste Treatment and Disposal Working Party covering joint funded work

International Nuclear Information System (INIS)

Claxton, D.G.S.A.

1989-05-01

The report covers progress in the area of ILW Product Evaluation. This work is a continuation of a generic study programme directed by the Waste Treatment and Disposal Working Party. The objective of the programme was to evaluate potential waste products arising from the treatment of ILW. (author)

Progress towards CSR RL06 GRACE gravity solutions

Science.gov (United States)

Save, Himanshu

2017-04-01

The GRACE project plans to re-processes the GRACE mission data in order to be consistent with the first gravity products released by the GRACE-FO project. The next generation Release-06 (RL06) gravity products from GRACE will include the improvements in GRACE Level-1 data products, background gravity models and the processing methodology. This paper will outline the planned improvements for CSR - RL06 and discuss the preliminary results. This paper will discuss the evolution of the quality of the GRACE solutions, especially over the past few years. We will also discuss the possible challenges we may face in connecting/extending the measurements of mass fluxes from the GRACE era to the GRACE-FO era due quality of the GRACE solutions from recent years.

Disposal R and D in the Used Fuel Disposition Campaign: A Discussion of Opportunities for Active International Collaboration

International Nuclear Information System (INIS)

Birkholzer, J.T.

2011-01-01

For DOE's Used Fuel Disposition Campaign (UFDC), international collaboration is a beneficial and cost-effective strategy for advancing disposal science with regards to multiple disposal options and different geologic environments. While the United States disposal program focused solely on Yucca Mountain tuff as host rock over the past decades, several international programs have made significant progress in the characterization and performance evaluation of other geologic repository options, most of which are very different from the Yucca Mountain site in design and host rock characteristics. Because Yucca Mountain was so unique (e.g., no backfill, unsaturated densely fractured tuff), areas of direct collaboration with international disposal programs were quite limited during that time. The decision by the U.S. Department of Energy to no longer pursue the disposal of high-level radioactive waste and spent fuel at Yucca Mountain has shifted UFDC's interest to disposal options and geologic environments similar to those being investigated by disposal programs in other nations. Much can be gained by close collaboration with these programs, including access to valuable experience and data collected over recent decades. Such collaboration can help to efficiently achieve UFDC's long-term goals of conducting 'experiments to fill data needs and confirm advanced modeling approaches' (by 2015) and of having a 'robust modeling and experimental basis for evaluation of multiple disposal system options' (by 2020). This report discusses selected opportunities of active international collaboration, with focus on both Natural Barrier System (NBS) and Engineered Barrier System (EBS) aspects and those opportunities that provide access to field data (and respective interpretation/modeling) or allow participation in ongoing field experiments. This discussion serves as a basis for the DOE/NE-53 and UFDC planning process for FY12 and beyond.

Deficiencies in FY 1998 DOD Financial Statements and Progress Toward Improved Financial Reporting

National Research Council Canada - National Science Library

Lane, F

1999-01-01

The audit objectives were to identify and summarize the major deficiencies that prevented favorable audit opinions on the FY 1998 DoD financial statements and to identify the actions taken or planned...

Tanks focus area multiyear program plan - FY96-FY98

International Nuclear Information System (INIS)

1995-07-01

The Tanks Focus Area (TFA) Multiyear Program Plan (MYPP) presents the recommended TFA technical program. The recommendation covers a 3-year funding outlook (FY96-FY98), with an emphasis on FY96 and FY97. In addition to defining the recommended program, this document also describes the processes used to develop the program, the implementation strategy for the program, the references used to write this report, data on the U.S. Department of Energy (DOE) tank site baselines, details on baseline assumptions and the technical elements, and a glossary

Thermally conductive cementitious grouts for geothermal heat pumps. Progress report FY 1998

Energy Technology Data Exchange (ETDEWEB)

Allan, M.L.; Philippacopoulos, A.J.

1998-11-01

Research commenced in FY 97 to determine the suitability of superplasticized cement-sand grouts for backfilling vertical boreholes used with geothermal heat pump (GHP) systems. The overall objectives were to develop, evaluate and demonstrate cementitious grouts that could reduce the required bore length and improve the performance of GHPs. This report summarizes the accomplishments in FY 98. The developed thermally conductive grout consists of cement, water, a particular grade of silica sand, superplasticizer and a small amount of bentonite. While the primary function of the grout is to facilitate heat transfer between the U-loop and surrounding formation, it is also essential that the grout act as an effective borehole sealant. Two types of permeability (hydraulic conductivity) tests was conducted to evaluate the sealing performance of the cement-sand grout. Additional properties of the proposed grout that were investigated include bleeding, shrinkage, bond strength, freeze-thaw durability, compressive, flexural and tensile strengths, elastic modulus, Poisson`s ratio and ultrasonic pulse velocity.

Ethanol annual report FY 1990

Energy Technology Data Exchange (ETDEWEB)

Texeira, R.H.; Goodman, B.J. (eds.)

1991-01-01

This report summarizes the research progress and accomplishments of the US Department of Energy (DOE) Ethanol from Biomass Program, field managed by the Solar Energy Research Institute, during FY 1990. The report includes an overview of the entire program and summaries of individual research projects. These projects are grouped into the following subject areas: technoeconomic analysis; pretreatment; cellulose conversion; xylose fermentation; and lignin conversion. Individual papers have been indexed separately for inclusion on the data base.

Significant progress towards development of the low-level radioactive waste disposal facility in Illinois

International Nuclear Information System (INIS)

Klebe, M.; Henry, T.L.; Corpstein, P.

1996-01-01

Development of disposal sites for low-level radioactive waste is a complicated legal, regulatory and public sector process. Development of the low-level radioactive waste disposal facility to support generators in Illinois and Kentucky is well under way. Significant progress has been made to re-engineer the siting development process capitalizing on prior lessons learned and a recommitment from Illinois state leadership assuring the future success of the program. Comparisons of why this new process will succeed are the major focus of this paper. Specific changes in approach from the previous process including changes in the Illinois Management Act (Management Act), creation of the Illinois Low-Level Radioactive Waste Siting Task Group (Task Group), new roles for the Illinois State Geologic Survey and Illinois State Water Survey (Scientific Surveys) and the Illinois Department of Nuclear Safety (IDNS), a new contractor reliance approach and increased confidence on the open-quote science close-quote are the major contrasts between the previous process and the new process currently underway

FY 2017-Progress Report on the Design and Construction of the Sodium Loop SMT-3

Energy Technology Data Exchange (ETDEWEB)

Natesan, K. [Argonne National Lab. (ANL), Argonne, IL (United States); Momozaki, Y. [Argonne National Lab. (ANL), Argonne, IL (United States)

2017-09-01

information is being transmitted to the tank fabricator. The SMT-3 loop will be located in Building 206 adjacent to the currently operating SMT-2 loop. In addition, we have demolished the aged power supply system in Building 206 and installed a new transformer, wiring, and power panels for the new loop. Procurement of some of the long lead items such as valves, EM pumps, EM flowmeters, etc. is in progress and will continue in FY 2018. The construction of components such as cold trap, economizers, piping arrangement etc. will be performed in the central shops at ANL. About 150 liters of sodium for the loop will be procured in early FY2018. The loop system is designed to circulate sodium through the sample tanks and the associated loop without an operator for an extended period of time. With the three sodium loops (with single-tank, dual-tank and four–tanks), materials can be tested at different sodium temperatures, and large tensile, creep, fatigue, creep-fatigue, and fracture toughness specimens can be exposed to sodium for extended periods of time and generate data on mechanical properties in support of ASME Code Qualification and USNRC Licensing of advanced Alloy 709 for use as a structural material in SFRs.

Nevada nuclear waste storage investigations: FY 1980 Project Plan and FY 1981 forecast

International Nuclear Information System (INIS)

1980-02-01

The DOE is responsible for developing or improving the technology for safely and permanently isolating radioactive wastes from the biosphere. The National Waste Terminal Storage Program, which is a part of the US Nuclear Waste Management Program, is concerned with disposing of the high-level wastes associated with DOE and commercial nuclear reactor fuel cycles. The DOE/NV has been delegated the responsibility to evaluate the geohydrologic setting and underground rock masses of the Nevada Test Site (NTS) area to determine whether a suitable site exists for constructing a repository for isolating highly radioactive solid wastes. Accordingly, the Nevada Nuclear Waste Storage Investigations (NNWSI) were established by NV to conduct these evaluations. The NNWSI are managed by the DOE/NV, but the field and laboratory investigations are being performed by scientific investigators from several organizations. The four primary organizations involved are: Los Alamos Scientific Laboratory (LASL), Lawrence Livermore Laboratory (LLL), Sandia Laboratories (SL), and the US Geological Survey (USGS). DOE/NV is responsible for coordinating these investigations. This document presents the Project Plan for the NNWSI for FY 1980 and forecasts activities for FY 1981. Each task is divided into subtasks and described. This Plan is subject ot periodic review and revision by the DOE/NV. Changes will be addressed as they occur in NNWSI Quarterly Reports. This document also presents information on the Project's technical approach as well as its history, organization, and management

PBX 9502 Gas Generation Progress Report FY17

Energy Technology Data Exchange (ETDEWEB)

Holmes, Matthew David [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Erickson, Michael Andrew Englert [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-10-03

The self-ignition (“cookoff”) behavior of PBX 9502 depends on the dynamic evolution of gas permeability and physical damage in the material. The time-resolved measurement of product gas generation yields insight regarding the crucial properties that dominate cookoff behavior. We report on small-scale laboratory testing performed in FY17, in which small unconfined samples of PBX 9502 were heated in a small custom-built sealed pressure vessel to self-ignition. We recorded time-lapse video of the evolving physical changes in the sample, quasi-static long-duration pressure rise, then high-speed video and dynamic pressure rise of the cookoff event. We report the full pressure attained during the cookoff of a 1.02g sample in a free volume of 62.5 cm³.

Nuclear Energy Advanced Modeling and Simulation (NEAMS) Waste Integrated Performance and Safety Codes (IPSC) : FY10 development and integration.

Energy Technology Data Exchange (ETDEWEB)

Criscenti, Louise Jacqueline; Sassani, David Carl; Arguello, Jose Guadalupe, Jr.; Dewers, Thomas A.; Bouchard, Julie F.; Edwards, Harold Carter; Freeze, Geoffrey A.; Wang, Yifeng; Schultz, Peter Andrew

2011-02-01

This report describes the progress in fiscal year 2010 in developing the Waste Integrated Performance and Safety Codes (IPSC) in support of the U.S. Department of Energy (DOE) Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) Campaign. The goal of the Waste IPSC is to develop an integrated suite of computational modeling and simulation capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive waste storage or disposal system. The Waste IPSC will provide this simulation capability (1) for a range of disposal concepts, waste form types, engineered repository designs, and geologic settings, (2) for a range of time scales and distances, (3) with appropriate consideration of the inherent uncertainties, and (4) in accordance with robust verification, validation, and software quality requirements. Waste IPSC activities in fiscal year 2010 focused on specifying a challenge problem to demonstrate proof of concept, developing a verification and validation plan, and performing an initial gap analyses to identify candidate codes and tools to support the development and integration of the Waste IPSC. The current Waste IPSC strategy is to acquire and integrate the necessary Waste IPSC capabilities wherever feasible, and develop only those capabilities that cannot be acquired or suitably integrated, verified, or validated. This year-end progress report documents the FY10 status of acquisition, development, and integration of thermal-hydrologic-chemical-mechanical (THCM) code capabilities, frameworks, and enabling tools and infrastructure.

FY2007 NREL Energy Storage R&D Progress Report

Energy Technology Data Exchange (ETDEWEB)

Pesaran, A.

2007-11-01

The National Renewable Energy Laboratory is engaged in research and development activities to support achieving targets and objectives set by the Energy Storage Program at the Office of FreedomCAR and Vehicle Technology in the U.S. Department of Energy. These activities include: 1. supporting the Battery Technology Development Program with battery thermal characterization and modeling and with energy storage system simulations and analysis; 2. supporting the Applied Research Program by developing thermal models to address abuse of Li-Ion batteries; and 3. supporting the Focused Long-Term Research Program by investigating improved Li-Ion battery electrode materials. This report summarizes the results of NREL energy storage activities in FY07.

Laboratory-directed research and development: FY 1996 progress report

Energy Technology Data Exchange (ETDEWEB)

Vigil, J.; Prono, J. [comps.

1997-05-01

This report summarizes the FY 1996 goals and accomplishments of Laboratory-Directed Research and Development (LDRD) projects. It gives an overview of the LDRD program, summarizes work done on individual research projects, and provides an index to the projects` principal investigators. Projects are grouped by their LDRD component: Individual Projects, Competency Development, and Program Development. Within each component, they are further divided into nine technical disciplines: (1) materials science, (2) engineering and base technologies, (3) plasmas, fluids, and particle beams, (4) chemistry, (5) mathematics and computational sciences, (6) atomic and molecular physics, (7) geoscience, space science, and astrophysics, (8) nuclear and particle physics, and (9) biosciences.

Laboratory-directed research and development: FY 1996 progress report

International Nuclear Information System (INIS)

Vigil, J.; Prono, J.

1997-05-01

This report summarizes the FY 1996 goals and accomplishments of Laboratory-Directed Research and Development (LDRD) projects. It gives an overview of the LDRD program, summarizes work done on individual research projects, and provides an index to the projects' principal investigators. Projects are grouped by their LDRD component: Individual Projects, Competency Development, and Program Development. Within each component, they are further divided into nine technical disciplines: (1) materials science, (2) engineering and base technologies, (3) plasmas, fluids, and particle beams, (4) chemistry, (5) mathematics and computational sciences, (6) atomic and molecular physics, (7) geoscience, space science, and astrophysics, (8) nuclear and particle physics, and (9) biosciences

Site characterization progress report: Yucca Mountain, Nevada. October 1, 1996--March 31, 1997

International Nuclear Information System (INIS)

1997-10-01

The report is the sixteenth in a series issued approximately every six months to report progress and results of site characterization activities being conducted to evaluate Yucca Mountain as a possible geologic repository for the disposal of spent nuclear fuel and high-level radioactive waste. This report highlights work started, in progress, and completed during the reporting period. In addition, this report documents and discusses changes to the Office of Civilian Radioactive Waste Management (OCRWM) Site Characterization Program (Program) resulting from the ongoing collection and evaluation of site information, systems analyses, development of repository and waste package designs, and results of performance assessment activities. Details on the activities summarized can be found in the numerous technical reports cited throughout the progress report. Yucca Mountain Site Characterization Project (Project) activities this period focused on implementing the near-term objectives of the revised Program Plan issued last period. Near-term objectives of the revised Program Plan include updating the US Department of Energy's (DOE) repository siting guidelines to be consistent with a more focused performance-driven program; supporting an assessment in 1998 of the viability of continuing with actions leading to the licensing of a repository; and if the site is suitable, submittal of a Secretarial site recommendation to the President in 2001 and license application the US Nuclear Regulatory Commission (NRC) in 2002. During this reporting period, the Project developed and baselined its long-range plan in December 1996. That revision reflected the detailed fiscal year (FY) 1997 work scope and funding plan previously baselined at the end of FY 1996. Site characterization activities have been focused to answer the major open technical issues and to support the viability assessment

CAES Annual Report FY 2011

Energy Technology Data Exchange (ETDEWEB)

Kortny Rolston

2011-10-01

The Center for Advanced Energy Studies was created to lead research programs important to the nation, attract students and faculty to the Idaho universities and act as a catalyst for technology-based economic development. CAES is striving to meet those goals by continuing to develop its infrastructure and equipment capabilities, expand its research portfolio and bolster Idaho's energy workforce. This Annual Report details the progress CAES made in FY 2011 toward fulfilling its research, education and economic development missions.

Advanced Industrial Materials (AIM) Program: Annual progress report FY 1995

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-04-01

In many ways, the Advanced Industrial Materials (AIM) Program underwent a major transformation in Fiscal Year 1995 and these changes have continued to the present. When the Program was established in 1990 as the Advanced Industrial Concepts (AIC) Materials Program, the mission was to conduct applied research and development to bring materials and processing technologies from the knowledge derived from basic research to the maturity required for the end use sectors for commercialization. In 1995, the Office of Industrial Technologies (OIT) made radical changes in structure and procedures. All technology development was directed toward the seven ``Vision Industries`` that use about 80% of industrial energy and generated about 90% of industrial wastes. The mission of AIM has, therefore, changed to ``Support development and commercialization of new or improved materials to improve productivity, product quality, and energy efficiency in the major process industries.`` Though AIM remains essentially a National Laboratory Program, it is essential that each project have industrial partners, including suppliers to, and customers of, the seven industries. Now, well into FY 1996, the transition is nearly complete and the AIM Program remains reasonably healthy and productive, thanks to the superb investigators and Laboratory Program Managers. This Annual Report for FY 1995 contains the technical details of some very remarkable work by the best materials scientists and engineers in the world. Areas covered here are: advanced metals and composites; advanced ceramics and composites; polymers and biobased materials; and new materials and processes.

Tank waste remediation system retrieval and disposal mission - Phase 1: Financial analysis

International Nuclear Information System (INIS)

Bickford, J.C.

1998-01-01

In Section 1.0, an overview of the Financial Analysis was provided and summarized in Table 1 for both the Retrieval and Disposal program and the TWRS project life cycle. A table recaps the pre-Phase 1B analysis budget requirements as discussed in previous sections. Another table in this section shows a similar build-up of costs and the impact of proposed offsets and increases to the pre-Phase 1B analysis. The issues concerning the increased requirements in FY 1998/1999 and the recommended adjustments were discussed. The Phase 1B Program as recommended is achievable. Specific recommendations are as follows: (a) Adopt the revised project baseline as presented in the cited tables; (b) Incorporate the $248.5 million in allowances for risk into the baseline; (c) Develop detailed action plans to realize the costs reduction opportunities; (d) Incorporate site indirect and benefits reduction rates into baseline; (e) Delay non-critical path scope which can be moved beyond FY 1999, as indicated: and (f) Renegotiate the Tri-Party Agreement milestones associated with the current compliance unfunded list for FY 1998

Disability Compensation and Patient Expenditures: FY2000 to FY2013

Data.gov (United States)

Department of Veterans Affairs — This report contains FY2000 through FY2013 data on disability compensation expenditures and recipients and on VA healthcare system patients and patient expenditures.

Photovoltaic Subcontract Program. Annual report, FY 1992

Energy Technology Data Exchange (ETDEWEB)

1993-03-01

This report summarizes the fiscal year (FY) 1992 progress of the subcontracted photovoltaic (PV) research and development (R&D) performed under the Photovoltaic Advanced Research and Development Project at the National Renewable Energy Laboratory (NREL)-formerly the Solar Energy Research Institute (SERI). The mission of the national PV program is to develop PV technology for large-scale generation of economically competitive electric power in the United States. The technical sections of the report cover the main areas of the subcontract program: the Crystalline Materials and Advanced Concepts project, the Polycrystalline Thin Films project, Amorphous Silicon Research project, the Photovoltaic Manufacturing Technology (PVMaT) project, PV Module and System Performance and Engineering project, and the PV Analysis and Applications Development project. Technical summaries of each of the subcontracted programs provide a discussion of approaches, major accomplishments in FY 1992, and future research directions.

Annual Report: Photovoltaic Subcontract Program FY 1991

Energy Technology Data Exchange (ETDEWEB)

Summers, K. A. [National Renewable Energy Lab. (NREL), Golden, CO (United States)

1992-03-01

This report summarizes the fiscal year (FY) 1991 (October 1, 1990, through September 30, 1991) progress of the subcontracted photovoltaic (PV) research and development (R&D) performed under the Photovoltaic Advanced Research and Development Project at the National Renewable Energy Laboratory (NREL)-formerly the Solar Energy Research Institute (SERI). The mission of the national PV program is to develop PV technology for large-scale generation of economically competitive electric power in the United States. The technical sections of the report cover the main areas of the subcontract program: the Amorphous Silicon Research Project, Polycrystalline Thin Films, Crystalline Silicon Materials Research, High Efficiency Concepts, the New Ideas Program, the University Participation Program, and the Photovoltaic Manufacturing Technology (PVMaT) project. Technical summaries of each of the subcontracted programs provide a discussion of approaches, major accomplishments in FY 1991, and future research directions.

Photovoltaic Program Branch annual report, FY 1989

Energy Technology Data Exchange (ETDEWEB)

Summers, K A [ed.

1990-03-01

This report summarizes the progress of the Photovoltaic (PV) Program Branch of the Solar Energy Research Institute (SERI) from October 1, 1988, through September 30, 1989. The branch is responsible for managing the subcontracted portion of SERI's PV Advanced Research and Development Project. In fiscal year (FY) 1989, this included nearly 50 subcontracts, with a total annualized funding of approximately $13.1 million. Approximately two-thirds of the subcontracts were with universities, at a total funding of nearly $4 million. The six technical sections of the report cover the main areas of the subcontracted program: Amorphous Silicon Research, Polycrystalline Thin Films, Crystalline Silicon Materials Research, High-Efficiency Concepts, New Ideas, and University Participation. Technical summaries of each of the subcontracted programs provide a discussion of approaches, major accomplishments in FY 1989, and future research directions. Each report will be cataloged individually.

3rd Quarter Transportation Report FY 2014: Radioactive Waste Shipments to and from the Nevada National Security Site (NNSS)

International Nuclear Information System (INIS)

Gregory, Louis

2014-01-01

This report satisfies the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO) commitment to prepare a quarterly summary report of radioactive waste shipments to the Nevada National Security Site (NNSS) Radioactive Waste Management Complex (RWMC) at Area 5. There were no shipments sent for offsite treatment and returned to the NNSS this quarter. This report summarizes the 3rd quarter of Fiscal Year (FY) 2014 low-level radioactive waste (LLW) and mixed low-level radioactive waste (MLLW) shipments. This report also includes annual summaries for FY 2014 in Tables 4 and 5. Tabular summaries are provided which include the following: Sources of and carriers for LLW and MLLW shipments to and from the NNSS; Number and external volume of LLW and MLLW shipments; Highway routes used by carriers; and Incident/accident data applicable to LLW and MLLW shipments. In this report shipments are accounted for upon arrival at the NNSS, while disposal volumes are accounted for upon waste burial. The disposal volumes presented in this report do not include minor volumes of non-radioactive materials that were approved for disposal. Volume reports showing cubic feet generated using the Low-Level Waste Information System may vary slightly due to differing rounding conventions.

Progress report for 1984/85 from the Waste Treatment and Disposal Working Party covering joint BNFL/DOE funded work

International Nuclear Information System (INIS)

Claxton, D.G.S.A.

1985-01-01

The progress report from the waste treatment and disposal working party is concerned with the management of intermediate-level radioactive waste arising from dismantled fuel assemblies, cladding removed from fuel cans, sludges from fuel cladding corrosion, flocs from liquid waste, ion exchange resins and solid wastes generated during reprocessing. It is proposed that these wastes be incorporated in a matrix for safe transport, storage and disposal and the objectives of the study are to evaluate waste products arising from the treatment of ILWS and to develop techniques to check the quality of the finished waste product. (UK)

4th Quarter Transportation Report FY 2014: Radioactive Waste Shipments to and from the Nevada National Security Site (NNSS)

International Nuclear Information System (INIS)

Gregory, Louis

2014-01-01

This report satisfies the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO) commitment to prepare a quarterly summary report of radioactive waste shipments to and from the Nevada National Security Site (NNSS) Radioactive Waste Management Complex (RWMC) at Area 5. There were no shipments sent for offsite treatment and returned to the NNSS this quarter. There was one shipment of two drums sent for offsite treatment and disposal. This report summarizes the 4th quarter of Fiscal Year (FY) 2014 low-level radioactive waste (LLW) and mixed low-level radioactive waste (MLLW) shipments. This report also includes annual summaries for FY 2014.

Fusion reactor safety studies, FY 1977

International Nuclear Information System (INIS)

Darby, J.B. Jr.

1978-04-01

This report reviews the technical progress in the fusion reactor safety studies performed during FY 1977 in the Fusion Power Program at the Argonne National Laboratory. The subjects reported on include safety considerations of the vacuum vessel and first-wall design for the ANL/EPR, the thermal responses of a tokamak reactor first wall, the vacuum wall electrical resistive requirements in relationship to magnet safety, and a major effort is reported on considerations and experiments on air detritiation

Guidance for closure of existing DOE LLW disposal sites

International Nuclear Information System (INIS)

Blanchfield, L.

1987-01-01

During FY 1986, a closure guidance document was developed. The purpose of this document is to provide guidance in support of DOE Order 5820.2 to site operating contractors for the stabilization and closure of existing low-level waste (LLW) shallow land disposal sites at US Department of Energy (DOE) facilities. Guidance is provided to aid operators in placing existing LLW sites in a closed conditions, i.e., a condition in which a nonoperational site meets postclosure performance requirements and can be shown, within a high degree of confidence, to perform as anticipated in the future, under the most cost-effective maintenance approach. Guidance is based on the philosophy that closure should be planned and performed using a systems approach. Plans for FY 1987 call for revision of the document to incorporate more information on closure of LLW sites also containing radioactive mixed waste and/or transuranic waste. 4 references, 3 figures, 2 tables

Tethys and Annex IV Progress Report for FY 2012

Energy Technology Data Exchange (ETDEWEB)

Hanna, Luke A.; Butner, R. Scott; Whiting, Jonathan M.; Copping, Andrea E.

2013-09-01

The marine and hydrokinetic (MHK) environmental Impacts Knowledge Management System, dubbed “Tethys” after the mythical Greek titaness of the seas, is being developed by the Pacific Northwest National Laboratory (PNNL) to support the U.S. Department of Energy’s Wind and Water Power Program (WWPP). Functioning as a smart database, Tethys enables its users to identify key words or terms to help gather, organize and make available information and data pertaining to the environmental effects of MHK and offshore wind (OSW) energy development. By providing and categorizing relevant publications within a simple and searchable database, Tethys acts as a dissemination channel for information and data which can be utilized by regulators, project developers and researchers to minimize the environmental risks associated with offshore renewable energy developments and attempt to streamline the permitting process. Tethys also houses a separate content-related Annex IV data base with identical functionality to the Tethys knowledge base. Annex IV is a collaborative project among member nations of the International Energy Agency (IEA) Ocean Energy Systems – Implementing Agreement (OES-IA) that examines the environmental effects of ocean energy devices and projects. The U.S. Department of Energy leads the Annex IV working with federal partners such as the Federal Energy Regulatory Commission (FERC), the Bureau of Ocean Energy Management (BOEM), and the National Oceanic Atmospheric Administration (NOAA). While the Annex IV database contains technical reports and journal articles, it is primarily focused on the collection of project site and research study metadata forms (completed by MHK researchers and developers around the world, and collected by PNNL) which provide information on environmental studies and the current progress of the various international MHK developments in the Annex IV member nations. The purpose of this report is to provide a summary of the content

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

Energy Technology Data Exchange (ETDEWEB)

Templeton, K.J.

1996-05-23

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

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

International Nuclear Information System (INIS)

Templeton, K.J.

1996-01-01

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

Advances in Geologic Disposal System Modeling and Application to Crystalline Rock

Energy Technology Data Exchange (ETDEWEB)

Mariner, Paul E. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Stein, Emily R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Frederick, Jennifer M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sevougian, S. David [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hammond, Glenn Edward [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Fascitelli, D. G. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2016-09-22

The Used Fuel Disposition Campaign (UFDC) of the U.S. Department of Energy (DOE) Office of Nuclear Energy (NE), Office of Fuel Cycle Technology (OFCT) is conducting research and development (R&D) on geologic disposal of used nuclear fuel (UNF) and high-level nuclear waste (HLW). Two of the high priorities for UFDC disposal R&D are design concept development and disposal system modeling (DOE 2011). These priorities are directly addressed in the UFDC Generic Disposal Systems Analysis (GDSA) work package, which is charged with developing a disposal system modeling and analysis capability for evaluating disposal system performance for nuclear waste in geologic media (e.g., salt, granite, clay, and deep borehole disposal). This report describes specific GDSA activities in fiscal year 2016 (FY 2016) toward the development of the enhanced disposal system modeling and analysis capability for geologic disposal of nuclear waste. The GDSA framework employs the PFLOTRAN thermal-hydrologic-chemical multi-physics code and the Dakota uncertainty sampling and propagation code. Each code is designed for massively-parallel processing in a high-performance computing (HPC) environment. Multi-physics representations in PFLOTRAN are used to simulate various coupled processes including heat flow, fluid flow, waste dissolution, radionuclide release, radionuclide decay and ingrowth, precipitation and dissolution of secondary phases, and radionuclide transport through engineered barriers and natural geologic barriers to the biosphere. Dakota is used to generate sets of representative realizations and to analyze parameter sensitivity.

Laboratory directed research and development program FY 2003

Energy Technology Data Exchange (ETDEWEB)

Hansen, Todd

2004-03-27

The Ernest Orlando Lawrence Berkeley National Laboratory (Berkeley Lab or LBNL) is a multi-program national research facility operated by the University of California for the Department of Energy (DOE). As an integral element of DOE's National Laboratory System, Berkeley Lab supports DOE's missions in fundamental science, energy resources, and environmental quality. Berkeley Lab programs advance four distinct goals for DOE and the nation: (1) To perform leading multidisciplinary research in the computing sciences, physical sciences, energy sciences, biosciences, and general sciences in a manner that ensures employee and public safety and protection of the environment. (2) To develop and operate unique national experimental facilities for qualified investigators. (3) To educate and train future generations of scientists and engineers to promote national science and education goals. (4) To transfer knowledge and technological innovations and to foster productive relationships among Berkeley Lab's research programs, universities, and industry in order to promote national economic competitiveness. In FY03, Berkeley Lab was authorized by DOE to establish a funding ceiling for the LDRD program of $15.0 M, which equates to about 3.2% of Berkeley Lab's FY03 projected operating and capital equipment budgets. This funding level was provided to develop new scientific ideas and opportunities and allow the Berkeley Lab Director an opportunity to initiate new directions. Budget constraints limited available resources, however, so only $10.1 M was expended for operating and $0.6 M for capital equipment (2.4% of actual Berkeley Lab FY03 costs). In FY03, scientists submitted 168 proposals, requesting over $24.2 M in operating funding. Eighty-two projects were funded, with awards ranging from $45 K to $500 K. These projects are summarized in Table 1.

In-situ containment and stabilization of buried waste: Annual report FY 1994

International Nuclear Information System (INIS)

Allan, M.L.; Kukacka, L.E.

1994-10-01

The two landfills of specific interest are the Chemical Waste Landfill (CWL) and the Mixed Waste Landfill (MWL), both located at Sandia National Laboratory. The work is comprised of two subtasks: (1) In-Situ Barriers and (2) In-Situ Stabilization of Contaminated Soils. The main environmental concern at the CWL is a chromium plume resulting from disposal of chromic acid and chromic sulfuric acid into unlined pits. This program has investigated means of in-situ stabilization of chromium contaminated soils and placement of containment barriers around the CWL. The MWL contains a plume of tritiated water. In-situ immobilization of tritiated water with cementitious grouts was not considered to be a method with a high probability of success and was not pursued. This is discussed further in Section 5.0. Containment barriers for the tritium plume were investigated. FY 94 work focused on stabilization of chromium contaminated soil with blast furnace slag modified grouts to bypass the stage of pre-reduction of Cr(6), barriers for tritiated water containment at the MWL, continued study of barriers for the CWL, and jet grouting field trials for CWL barriers at an uncontaminated site at SNL. Cores from the FY 93 permeation grouting field trails were also tested in FY 94

Alternative Electrochemical Salt Waste Forms, Summary of FY11-FY12 Results

Energy Technology Data Exchange (ETDEWEB)

Riley, Brian J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Mccloy, John S. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Crum, Jarrod V. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Lepry, William C. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Rodriguez, Carmen P. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Windisch, Charles F. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Matyas, Josef [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Westman, Matthew P. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Rieck, Bennett T. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Lang, Jesse B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Olszta, Matthew J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Pierce, David A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2014-01-17

The Fuel Cycle Research and Development Program, sponsored by the U.S. Department of Energy Office of Nuclear Energy, is currently investigating alternative waste forms for wastes generated from nuclear fuel processing. One such waste results from an electrochemical separations process, called the “Echem” process. The Echem process utilizes a molten KCl-LiCl salt to dissolve the fuel. This process results in a spent salt containing alkali, alkaline earth, lanthanide halides and small quantities of actinide halides, where the primary halide is chloride with a minor iodide fraction. Pacific Northwest National Laboratory (PNNL) is concurrently investigating two candidate waste forms for the Echem spent-salt: high-halide minerals (i.e., sodalite and cancrinite) and tellurite (TeO2)-based glasses. Both of these candidates showed promise in fiscal year (FY) 2009 and FY2010 with a simplified nonradioactive simulant of the Echem waste. Further testing was performed on these waste forms in FY2011 and FY2012 to assess the possibility of their use in a sustainable fuel cycle. This report summarizes the combined results from FY2011 and FY2012 efforts.

Annual Report for Los Alamos National Laboratory Technical Area 54, Area G Disposal Facility - Fiscal Year 2016

Energy Technology Data Exchange (ETDEWEB)

Birdsell, Kay Hanson [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Stauffer, Philip H. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Atchley, Adam Lee [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Miller, Elizabeth D. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Chu, Shaoping [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); French, Sean B. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-03-24

As a condition to the disposal authorization statement issued to Los Alamos National Laboratory (LANL or the Laboratory) on March 17, 2010, a comprehensive performance assessment and composite analysis (PA/CA) maintenance program must be implemented for the Technical Area 54, Area G disposal facility. Annual determinations of the adequacy of the PA/CA are to be conducted under the maintenance program to ensure that the conclusions reached by those analyses continue to be valid. This report summarizes the results of the fiscal year (FY) 2016 annual review for Area G.

Site characterization progress report: Yucca Mountain, Nevada. October 1, 1996--March 31, 1997

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-10-01

The report is the sixteenth in a series issued approximately every six months to report progress and results of site characterization activities being conducted to evaluate Yucca Mountain as a possible geologic repository for the disposal of spent nuclear fuel and high-level radioactive waste. This report highlights work started, in progress, and completed during the reporting period. In addition, this report documents and discusses changes to the Office of Civilian Radioactive Waste Management (OCRWM) Site Characterization Program (Program) resulting from the ongoing collection and evaluation of site information, systems analyses, development of repository and waste package designs, and results of performance assessment activities. Details on the activities summarized can be found in the numerous technical reports cited throughout the progress report. Yucca Mountain Site Characterization Project (Project) activities this period focused on implementing the near-term objectives of the revised Program Plan issued last period. Near-term objectives of the revised Program Plan include updating the US Department of Energy`s (DOE) repository siting guidelines to be consistent with a more focused performance-driven program; supporting an assessment in 1998 of the viability of continuing with actions leading to the licensing of a repository; and if the site is suitable, submittal of a Secretarial site recommendation to the President in 2001 and license application the US Nuclear Regulatory Commission (NRC) in 2002. During this reporting period, the Project developed and baselined its long-range plan in December 1996. That revision reflected the detailed fiscal year (FY) 1997 work scope and funding plan previously baselined at the end of FY 1996. Site characterization activities have been focused to answer the major open technical issues and to support the viability assessment.

Closure Report for Corrective Action Unit 139: Waste Disposal Sites, Nevada Test Site, Nevada

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Restoration

2009-07-31

Corrective Action Unit (CAU) 139 is identified in the Federal Facility Agreement and Consent Order (FFACO) as 'Waste Disposal Sites' and consists of the following seven Corrective Action Sites (CASs), located in Areas 3, 4, 6, and 9 of the Nevada Test Site: CAS 03-35-01, Burn Pit; CAS 04-08-02, Waste Disposal Site; CAS 04-99-01, Contaminated Surface Debris; CAS 06-19-02, Waste Disposal Site/Burn Pit; CAS 06-19-03, Waste Disposal Trenches; CAS 09-23-01, Area 9 Gravel Gertie; and CAS 09-34-01, Underground Detection Station. Closure activities were conducted from December 2008 to April 2009 according to the FFACO (1996, as amended February 2008) and the Corrective Action Plan for CAU 139 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2007b). The corrective action alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls. Closure activities are summarized. CAU 139, 'Waste Disposal Sites,' consists of seven CASs in Areas 3, 4, 6, and 9 of the NTS. The closure alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls. This CR provides a summary of completed closure activities, documentation of waste disposal, and confirmation that remediation goals were met. The following site closure activities were performed at CAU 139 as documented in this CR: (1) At CAS 03-35-01, Burn Pit, soil and debris were removed and disposed as LLW, and debris was removed and disposed as sanitary waste. (2) At CAS 04-08-02, Waste Disposal Site, an administrative UR was implemented. No postings or post-closure monitoring are required. (3) At CAS 04-99-01, Contaminated Surface Debris, soil and debris were removed and disposed as LLW, and debris was removed and disposed as sanitary waste. (4) At CAS 06-19-02, Waste Disposal Site/Burn Pit, no work was performed. (5) At CAS 06-19-03, Waste Disposal Trenches, a native soil cover was installed

Closure Report for Corrective Action Unit 139: Waste Disposal Sites, Nevada Test Site, Nevada

International Nuclear Information System (INIS)

2009-01-01

Corrective Action Unit (CAU) 139 is identified in the Federal Facility Agreement and Consent Order (FFACO) as 'Waste Disposal Sites' and consists of the following seven Corrective Action Sites (CASs), located in Areas 3, 4, 6, and 9 of the Nevada Test Site: CAS 03-35-01, Burn Pit; CAS 04-08-02, Waste Disposal Site; CAS 04-99-01, Contaminated Surface Debris; CAS 06-19-02, Waste Disposal Site/Burn Pit; CAS 06-19-03, Waste Disposal Trenches; CAS 09-23-01, Area 9 Gravel Gertie; and CAS 09-34-01, Underground Detection Station. Closure activities were conducted from December 2008 to April 2009 according to the FFACO (1996, as amended February 2008) and the Corrective Action Plan for CAU 139 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2007b). The corrective action alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls. Closure activities are summarized. CAU 139, 'Waste Disposal Sites,' consists of seven CASs in Areas 3, 4, 6, and 9 of the NTS. The closure alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls. This CR provides a summary of completed closure activities, documentation of waste disposal, and confirmation that remediation goals were met. The following site closure activities were performed at CAU 139 as documented in this CR: (1) At CAS 03-35-01, Burn Pit, soil and debris were removed and disposed as LLW, and debris was removed and disposed as sanitary waste. (2) At CAS 04-08-02, Waste Disposal Site, an administrative UR was implemented. No postings or post-closure monitoring are required. (3) At CAS 04-99-01, Contaminated Surface Debris, soil and debris were removed and disposed as LLW, and debris was removed and disposed as sanitary waste. (4) At CAS 06-19-02, Waste Disposal Site/Burn Pit, no work was performed. (5) At CAS 06-19-03, Waste Disposal Trenches, a native soil cover was installed, and a UR was

Gyrocon radio-frequency generator for FY-80 and FY-81

International Nuclear Information System (INIS)

Tallerico, P.J.

1982-09-01

The gyrocon is a high-power, high-efficiency amplifier that operates by deflection modulation of an electron beam. The spatial bunching can be better than the temporal bunching in a klystron, especially for high output powers and uhf frequencies. Soviet gyrocons have produced over 40 MW of pulsed power at 430 MHz and 250-kW cw at 181 MHz. The progress on the construction and testing of a 450-MHz prototype gyrocon is discussed. The maximum pulsed output power that has been achieved in the reporting period is 1 kW. Although these powers are significantly below the design goal of 650 kW, there is a good chance that the experimental program in FY-82 will result in increased output power

Annual Report for Los Alamos National Laboratory Technical Area 54, Area G Disposal Facility – Fiscal Year 2015

Energy Technology Data Exchange (ETDEWEB)

French, Sean B. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Stauffer, Philip H. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Birdsell, Kay H. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-02-29

As a condition to the disposal authorization statement issued to Los Alamos National Laboratory (LANL or the Laboratory) on March 17, 2010, a comprehensive performance assessment and composite analysis maintenance program must be implemented for the Technical Area 54, Area G disposal facility. Annual determinations of the adequacy of the performance assessment and composite analysis (PA/CA) are to be conducted under the maintenance program to ensure that the conclusions reached by those analyses continue to be valid. This report summarizes the results of the fiscal year (FY) 2015 annual review for Area G.

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

International Nuclear Information System (INIS)

Hinga, K.R.

1981-07-01

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

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

Energy Technology Data Exchange (ETDEWEB)

Hinga, K.R. (ed.)

1981-07-01

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

Recent progress of the waste processing and disposal projects within the Underground Storage Tank-Integrated Demonstration

International Nuclear Information System (INIS)

Hunt, R.D.; McGinnis, C.P.; Cruse, J.M.

1994-01-01

The US Department of Energy (DOE) Office of Environmental Restoration and Waste Remediation has created the Office of Technology Development (OTD) to provide new and improved remediation technologies for the 1 x 10 8 gal of radioactive waste in the underground storage tanks (USTs) at five DOE sites. The OTD established and the Underground Storage Tank-Integrated Demonstration (UST-ID) to perform demonstrations, tests, and evaluations on these new technologies before these processes are transferred to the tank sites for use in full-scale remediation of the USTs. The UST-ID projects are performed by the Characterization and Waste Retrieval Program or the Waste Processing and Disposal Program (WPDP). During FY 1994, the WPDP is funding 12 projects in the areas of supernate processing, sludge processing, nitrate destruction, and final waste forms. The supernate projects are primarily concerned with cesium removal. A mobile evaporator and concentrator for cesium-free supernate is also being demonstrated. The sludge projects are emphasizing sludge dissolution and the evaluation of the TRUEX and diamide solvent extraction processes for transuranic waste streams. One WPDP project is examining both supernate and sludge processes in an effort to develop a system-level plan for handling all UST waste. The other WPDP studies are concerned with nitrate and organic destruction as well as subsequent waste forms. The current status of these WPDP projects is presented

FY 1994 Annual Work Plan

Energy Technology Data Exchange (ETDEWEB)

1993-10-01

This is the third Office of Inspector General (OIG)Annual Work Plan. Its purpose is to summarize work completed in Fiscal Year (FY) 1993, identify ongoing projects from previous fiscal years which the OIG intends to continue into FY 1994, and announce planned projects which the OIG intends to begin in FY 19994.

In situ vitrification program treatability investigation progress report

International Nuclear Information System (INIS)

Arrenholz, D.A.

1990-12-01

This document presents a summary of the efforts conducted under the in situ vitrification treatability study during the period from its initiation in FY-88 until FY-90. In situ vitrification is a thermal treatment process that uses electrical power to convert contaminated soils into a chemically inert and stable glass and crystalline product. Contaminants present in the soil are either incorporated into the product or are pyrolyzed during treatment. The treatability study being conducted at the Idaho National Engineering Laboratory by EG ampersand G Idaho is directed at examining the specific applicability of the in situ vitrification process to buried wastes contaminated with transuranic radionuclides and other contaminants found at the Subsurface Disposal Area of the Radioactive Waste Management Complex. This treatability study consists of a variety of tasks, including engineering tests, field tests, vitrified product evaluation, and analytical models of the ISV process. The data collected in the course of these efforts will address the nine criteria set forth in the Comprehensive Environmental Response, Compensation, and Liability Act, which will be used to identify and select specific technologies to be used in the remediation of the buried wastes at the Subsurface Disposal Area. 6 refs., 4 figs., 3 tabs

Biodiesel from aquatic species. Project report: FY 1993

Energy Technology Data Exchange (ETDEWEB)

Brown, L.M.; Sprague, S.; Jarvis, E.E.; Dunahay, T.G.; Roessler, P.G.; Zeiler, K.G.

1994-01-01

Researchers in the Biodiesel/Aquatic Species Project focus on the use of microalgae as a feedstock for producing renewable, high-energy liquid fuels. The program`s basic premise is that microalgae, which have been called the most productive biochemical factories in the world, can produce up to 30 times more oil per unit of growth area than land plants. It is estimated that 150 to 400 barrels of oil per acre per year (0.06 to 0.16 million liters/hectar) could be produced with microalgal oil technology. Initial commercialization of this technology is envisioned for the desert Southwest because this area provides high solar radiation and offers flat land that has few competing uses (hence low land costs). Similarly, there are large saline aquifers with few competing uses in the region. This water source could provide a suitable, low-cost medium for the growth of many microalgae. The primary area of research during FY 1993 was the effort to genetically improve microalgae in order to control the timing and magnitude of lipid accumulation. Increased lipid content will have a direct effect on fuel price, and the control of lipid content is a major project goal. The paper describes progress on the following: culture collection; molecular biology of lipid biosynthesis; microalgal transformation; and environmental, safety, and health and quality assurance.

Nevada Nuclear Waste Storage Investigations. FY 1979 project plan

International Nuclear Information System (INIS)

1979-03-01

This document presents the management and cost for the Nevada Nuclear Waste Storage Investigations (disposal of high-level wastes at Nevada Test Site) and provides a complete description of the overall project, management structure, technical approach, and work breakdown structure. The document is organized into five major sections. Section I summarizes the history of the project and indicates a potential future course of action. FY 1979 project work is briefly described in Section II. Section III outlines the delegated responsibilities of all project management functions. A list of critical questions that guide the technical approach of the project are presented in Section IV. Section V contains subtask work plans which outline the work in detail for this fiscal year

Progress of the decommissioning process of Musashi Institute of Technology reactor (4)

International Nuclear Information System (INIS)

Uchiyama, Takafumi; Tanzawa, Tomio; Mitsuhashi, Ishi; Morishima, Kayoko; Matsumoto, Tetsuo

2012-01-01

The research reactor of Tokyo City University Atomic Energy Research Laboratory (Musashi Institute of Technology reactor) is zirconium-moderated water-cooled solid homogeneous type (TRIGA-II type), and its maximum heat output is 100 kW. It got into the first critical state in January 1963, and since then, it has mainly contributed to education and training for upgrading nuclear engineers, radioactivation analysis and reactor physics, and medical researches, as the joint usage research facilities across Japan. Then, after a long-term suspension, the university submitted the file in 2004 to the Ministry of Education, Culture, Sports, Science and Technology on the dismantling for the purpose of facility abolishment. Through the procedure of submitting a decommissioning plan, it was approved. Furthermore, in order to perform the function stop of the disposal facilities of liquid waste, application for change authorization for the decommissioning plan was submitted and approved. Regarding the progress of the decommissioning plan, the dismantling and removal of waste facilities for liquid waste and solid waste was carried out in FY2011 without any trouble. This paper explains this progress and future work plans. (A.O.)

Progress report on disposal concept for TRU waste in Japan

International Nuclear Information System (INIS)

2000-03-01

The object of this report is to contribute towards establishing a national TRU waste disposal program by integrating the results of research and development work carried out by JNC and the electricity utilities and summarizing the findings concerning safe methods for TRU waste disposal. The report consists of 5 chapters: the first describes the boundary conditions for the review of the TRU waste disposal concept (including geological conditions) and the basic concept adopted; the second describes the generation and characteristics of TRU waste and the third outlines the disposal technology; the fourth gives the key of the safety assessment and the fifth presents the conclusions of the report and lists issues for future consideration. The geological environment of Japan is simply classified into crystalline and sedimentary rock types (in terms of groundwater flow properties and rock strength) and a set of target conditions/properties for each rock type is then established. Based on this, a case which represents the basis for performance assessment (the reference case) will be defined. Alternatives to the reference case are studied to investigate the flexibility of the disposal concept. Under the conditions assumed in this study, the perturbing events considered showed no significant effects on the dose at the 100 meter evaluation point, owing to the relatively high efficiency of the natural barrier. However, the significant effect of these events on nuclide from the EBS shows that, in the case of a less efficient natural barrier, their effects could influence resulting dose. (S.Y.)

FY2007 Laboratory Directed Research and Development Annual Report

Energy Technology Data Exchange (ETDEWEB)

Craig, W W; Sketchley, J A; Kotta, P R

2008-03-20

The Laboratory Directed Research and Development (LDRD) annual report for fiscal year 2007 (FY07) provides a summary of LDRD-funded projects for the fiscal year and consists of two parts: An introduction to the LDRD Program, the LDRD portfolio-management process, program statistics for the year, and highlights of accomplishments for the year. A summary of each project, submitted by the principal investigator. Project summaries include the scope, motivation, goals, relevance to Department of Energy (DOE)/National Nuclear Security Administration (NNSA) and Lawrence Livermore National Laboratory (LLNL) mission areas, the technical progress achieved in FY07, and a list of publications that resulted from the research in FY07. Summaries are organized in sections by research category (in alphabetical order). Within each research category, the projects are listed in order of their LDRD project category: Strategic Initiative (SI), Exploratory Research (ER), Laboratory-Wide Competition (LW), and Feasibility Study (FS). Within each project category, the individual project summaries appear in order of their project tracking code, a unique identifier that consists of three elements. The first is the fiscal year the project began, the second represents the project category, and the third identifies the serial number of the proposal for that fiscal year.

Research on geological disposal

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

The aims of this research are to develop criteria for reviewing reliability and suitability of the result from Preliminary Investigations to be submitted by the implementer, and to establish a basic policy for safety review. For development of reliability and suitability criteria for reviewing the result of Preliminary Investigations, we evaluated the uncertainties and their influence from limited amount of investigations, as well as we identified important procedures during investigations and constructions of models, as follows: (1) uncertainties after limited amount of geological exploration and drilling, (2) influence of uncertainties in regional groundwater flow model, (3) uncertainties of DFN (Discrete Fracture Network) models in the fractured rock, (4) analyzed investigation methods described in implementer's report, and (5) identified important aspects in investigation which need to be reviewed and follow QA (Quality Assurance). For development of reliability and suitability criteria for reviewing the result of Detailed Investigations, we analyzed important aspects in investigation which supplies data to design and safety assessment, as well as studied the applicability of pressure interference data during excavation to verify hydrogeological model. Regarding the research for safety review, uncertainties of geologic process in long time-scale was studied. In FY2012, we started to evaluate the structural stabilities of concrete and bentonite in disposal environment. Finally, we continued to accumulate the knowledge on geological disposal into the database system. (author)

WASTE PACKAGE OPERATIONS FY99 CLOSURE METHODS REPORT

Energy Technology Data Exchange (ETDEWEB)

M. C. Knapp

1999-09-23

The waste package (WP) closure weld development task is part of a larger engineering development program to develop waste package designs. The purpose of the larger waste package engineering development program is to develop nuclear waste package fabrication and closure methods that the Nuclear Regulatory Commission will find acceptable and will license for disposal of spent nuclear fuel (SNF), non-fuel components, and vitrified high-level waste within a Monitored Geologic Repository (MGR). Within the WP closure development program are several major development tasks, which, in turn, are divided into subtasks. The major tasks include: WP fabrication development, WP closure weld development, nondestructive examination (NDE) development, and remote in-service inspection development. The purpose of this report is to present the objectives, technical information, and work scope relating to the WP closure weld development.and NDE tasks and subtasks and to report results of the closure weld and NDE development programs for fiscal year 1999 (FY-99). The objective of the FY-99 WP closure weld development task was to develop requirements for closure weld surface and volumetric NDE performance demonstrations, investigate alternative NDE inspection techniques, and develop specifications for welding, NDE, and handling system integration. In addition, objectives included fabricating several flat plate mock-ups that could be used for NDE development, stress relief peening, corrosion testing, and residual stress testing.

WASTE PACKAGE OPERATIONS FY-99 CLOSURE METHODS REPORT

International Nuclear Information System (INIS)

M. C. Knapp

1999-01-01

The waste package (WP) closure weld development task is part of a larger engineering development program to develop waste package designs. The purpose of the larger waste package engineering development program is to develop nuclear waste package fabrication and closure methods that the Nuclear Regulatory Commission will find acceptable and will license for disposal of spent nuclear fuel (SNF), non-fuel components, and vitrified high-level waste within a Monitored Geologic Repository (MGR). Within the WP closure development program are several major development tasks, which, in turn, are divided into subtasks. The major tasks include: WP fabrication development, WP closure weld development, nondestructive examination (NDE) development, and remote in-service inspection development. The purpose of this report is to present the objectives, technical information, and work scope relating to the WP closure weld development.and NDE tasks and subtasks and to report results of the closure weld and NDE development programs for fiscal year 1999 (FY-99). The objective of the FY-99 WP closure weld development task was to develop requirements for closure weld surface and volumetric NDE performance demonstrations, investigate alternative NDE inspection techniques, and develop specifications for welding, NDE, and handling system integration. In addition, objectives included fabricating several flat plate mock-ups that could be used for NDE development, stress relief peening, corrosion testing, and residual stress testing

Organic analysis progress report FY 1997

Energy Technology Data Exchange (ETDEWEB)

Clauss, S.A.; Grant, K.E.; Hoopes, V.; Mong, G.M.; Steele, R.; Bellofatto, D.; Sharma, A.

1998-04-01

The Organic Analysis and Methods Development Task is being conducted by Pacific Northwest National Laboratory (PNNL) as part of the Organic Tank Waste Safety Project. The objective of the task is to apply developed analytical methods to identify and/or quantify the amount of particular organic species in tank wastes. In addition, this task provides analytical support for the Gas Generation Studies Task, Waste Aging, and Solubility Studies. This report presents the results from analyses of tank waste samples archived at Pacific Northwest National Laboratory (PNNL) and received from the Project Hanford Management Contractor (PHMC), which included samples associated with both the Flammable Gas and Organic Tank Waste Safety Programs. The data are discussed in Section 2.0. In addition, the results of analytical support for analyzing (1) simulated wastes for Waste Aging, (2) tank waste samples for Gas Generation, and (3) simulated wastes associated with solubility studies discussed in Sections 3.0, 4.0, and 5.0, respectively. The latter part of FY 1997 was devoted to documenting the analytical procedures, including derivation gas chromatography/mass spectrometry (GC/MS) and GC/FID for quantitation, ion-pair chromatography (IPC), IC, and the cation exchange procedure for reducing the radioactivity of samples. The documentation of analytical procedures is included here and discussed in Section 6.0 and Section 7.0 discusses other analytical procedures. The references are listed in Section 8.0 and future plans are discussed in Section 9.0. Appendix A is a preprint of a manuscript accepted for publication. Appendix B contains the cc mail messages and chain-of-custody forms for the samples received for analyses. Appendix C contains the test plan for analysis of tank waste samples.

Organic analysis progress report FY 1997

International Nuclear Information System (INIS)

Clauss, S.A.; Grant, K.E.; Hoopes, V.; Mong, G.M.; Steele, R.; Bellofatto, D.; Sharma, A.

1998-04-01

The Organic Analysis and Methods Development Task is being conducted by Pacific Northwest National Laboratory (PNNL) as part of the Organic Tank Waste Safety Project. The objective of the task is to apply developed analytical methods to identify and/or quantify the amount of particular organic species in tank wastes. In addition, this task provides analytical support for the Gas Generation Studies Task, Waste Aging, and Solubility Studies. This report presents the results from analyses of tank waste samples archived at Pacific Northwest National Laboratory (PNNL) and received from the Project Hanford Management Contractor (PHMC), which included samples associated with both the Flammable Gas and Organic Tank Waste Safety Programs. The data are discussed in Section 2.0. In addition, the results of analytical support for analyzing (1) simulated wastes for Waste Aging, (2) tank waste samples for Gas Generation, and (3) simulated wastes associated with solubility studies discussed in Sections 3.0, 4.0, and 5.0, respectively. The latter part of FY 1997 was devoted to documenting the analytical procedures, including derivation gas chromatography/mass spectrometry (GC/MS) and GC/FID for quantitation, ion-pair chromatography (IPC), IC, and the cation exchange procedure for reducing the radioactivity of samples. The documentation of analytical procedures is included here and discussed in Section 6.0 and Section 7.0 discusses other analytical procedures. The references are listed in Section 8.0 and future plans are discussed in Section 9.0. Appendix A is a preprint of a manuscript accepted for publication. Appendix B contains the cc mail messages and chain-of-custody forms for the samples received for analyses. Appendix C contains the test plan for analysis of tank waste samples

Investigation of Coupled Processes and Impact of High Temperature Limits in Argillite Rock: FY17 Progress. Predecisional Draft

Energy Technology Data Exchange (ETDEWEB)

Zheng, Liange; Rutqvist, Jonny; Xu, Hao; Kim, Kunwhi; Voltolini, Marco; Cao, Xiaoyuan

2017-07-03

-Scale Engineered Barrier Experiment Dismantling Project (FEBEX-DP). The data collected in the test after almost two decades of heating and two dismantling events provide a unique opportunity of validating coupled THMC models and enhancing our understanding of coupled THMC process in EBS bentonite. Section 5 presents a planned large in-situ test, “HotBENT,” at Grimsel Test Site, Switzerland. In this test, bentonite backfilled EBS in granite will be heated up to 200 °C, where the most relevant features of future emplacement conditions can be adequately reproduced. Lawrence Berkeley National Laboratory (LBNL) has very actively participated in the project since the very beginning and have conducted scoping calculations in FY17 to facilitate the final design of the experiment. Section 6 presents present LBNL’s activities for modeling gas migration in clay related to Task A of the international DECOVALEX-2019 project. This is an international collaborative activity in which DOE and LBNL gain access to unique laboratory and field data of gas migration that are studied with numerical modeling to better understand the processes, to improve numerical models that could eventually be applied in the performance assessment for nuclear waste disposal in clay host rocks and bentonite backfill. Section 7 summarizes the main research accomplishments for FY17 and proposes future work activities.

Annual progress report FY 1977

International Nuclear Information System (INIS)

Hansen, K.F.; Henry, A.F.

1977-07-01

Progress is summarized in a project directed toward development of numerical methods suitable for the computer solution of problems in reactor dynamics and safety. Specific areas of research include methods of integration of the time-dependent diffusion equations by finite difference and finite element methods; representation of reactor properties by various homogenization procedures; application of synthesis methods; and development of response matrix techniques

Progress on developing expert systems in waste management and disposal

International Nuclear Information System (INIS)

Rivera, A.L.; Ferrada, J.J.

1990-01-01

The concept of artificial intelligence (AI) represents a challenging opportunity in expanding the potential benefits from computer technology in waste management and disposal. The potential of this concept lies in facilitating the development of intelligent computer systems to help analysts, decision makers, and operators in waste and technology problem solving similar to the way that machines support the laborer. Because the knowledge of multiple human experts is an essential input in the many aspects of waste management and disposal, there are numerous opportunities for the development of expert systems using software products from AI. This paper presents systems analysis as an attractive framework for the development of intelligent computer systems of significance to waste management and disposal, and it provides an overview of limited prototype systems and the commercially available software used during prototype development activities

Nuclear Waste Treatment Program: Annual report for FY 1986

International Nuclear Information System (INIS)

Burkholder, H.C.; Brouns, R.A.; Powell, J.A.

1987-09-01

To support DOE's attainment of its goals, Nuclear Waste Treatment Program (NWTP) is to provide technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management system and problem-specific treatment approaches, waste form and treatment process adaptations, equipment designs, and trouble-shooting. This annual report describes progress during FY 1986 toward meeting these two objectives. 29 refs., 59 figs., 25 tabs

Nuclear Waste Treatment Program: Annual report for FY 1986

Energy Technology Data Exchange (ETDEWEB)

Burkholder, H.C.; Brouns, R.A. (comps.); Powell, J.A. (ed.)

1987-09-01

To support DOE's attainment of its goals, Nuclear Waste Treatment Program (NWTP) is to provide technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management system and problem-specific treatment approaches, waste form and treatment process adaptations, equipment designs, and trouble-shooting. This annual report describes progress during FY 1986 toward meeting these two objectives. 29 refs., 59 figs., 25 tabs.

FY 1990/FY 1991 Biennial Budget Descriptive Summaries for the Strategic Defense Initiative Organization

Science.gov (United States)

1989-01-01

reduction in cryccooler size. o (U) Develop the first diamond ME_2 with monocrystalline , semiconductor quality thin-film diamcnd. o (U) Develop Atomic Layer...stiffness and dynamic response. A lightweight thermal radiator panel will also be fabricated and tested. Fabrication of tubes and sheets in gauges...FY 91 o Precision Gimbal Test IQ FY 91 C Cx:mlete Deveic..ent of Integrated Structures Model 2Q FY 91 c Light’weight Ccmpcsitas Radiator Panel Demo 2Q

DOE Hydropower Program Annual Report for FY 2003

Energy Technology Data Exchange (ETDEWEB)

Cada, Glenn F. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Carlson, Thomas J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Dauble, Dennis D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Hunt, Richard T. [Idaho National Lab. (INL), Idaho Falls, ID (United States). Idaho National Engineering and Environmental Lab. (INEEL); Sale, Michael J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Sommers, Garold L. [Idaho National Lab. (INL), Idaho Falls, ID (United States). Idaho National Engineering and Environmental Lab. (INEEL)

2004-02-01

This report describes the progress of the R&D conducted in FY 2003 the under four program areas at the time: (1) Advanced Hydropower Technology (Large Turbine Field Testing, Testing of the Alden/NREC pilot scale runner, and Improved Mitigation Practices); (2) Supporting Research and Testing (Biological Design Criteria, Computer and Physical Modeling, Instrumentation and Controls, and Environmental Analysis); (3) Systems Integration and Technology Acceptance (Wind/Hydro Integration Studies and Technical Support and Outreach); and (4) Engineering and Analysis (Innovative Technology Characterization).

Development of an integrated software system (Digital Geological Disposal System) for design and evaluation of HLW disposal system

International Nuclear Information System (INIS)

Fusaeda, Shigeki; Yanagisawa, Ichiro; Imamura, Naoko

2000-02-01

In this study, a design study on 'Digital Geological Disposal System' has been carried out in order to define the developmental goal for the first phase (- FY2002) system and to demonstrate the feasibility of the system development. The key conclusions are summarized as follows: (1) As the result of the basic design of the Integrated Analysis Platform (IAP), the representation method for PLAN (Process Linkage Analysis Network), the PLAN objects configuration and definition and the execution control mechanism of PLAN are newly proposed in order to enhance the flexibility of IAP. (2) A prototyping study concerning an optimization problem that includes cavity stability analysis and thermal analysis, showed that the design of IAP is practical one and also has enough flexibility to solve complex problems expected in the repository design processes. (3) The development plan for the Digital Geological Disposal System' has been investigated based on the discussions about the system usage by the potential users such as the regulators, the implementation body and the research institutes, as well as the technical discussions. As a result, short-term (for the first phase) and long-term development plans have been proposed. (author)

Annual Performance Report - FY 2011

Science.gov (United States)

This report summarizes OIG activity, performance, results, and challenges, and provides a financial accounting of resources for fiscal year (FY) 2011 compared to our FY 2011 annual performance targets.

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

International Nuclear Information System (INIS)

Talbert, D.M.

1981-04-01

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

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

International Nuclear Information System (INIS)

Talbert, D.M.

1981-04-01

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

Unmanned Aircraft Systems (UAS) Integration in the National Airspace System (NAS) Project FY16 Annual Review

Science.gov (United States)

Grindle, Laurie; Hackenberg, Davis

2016-01-01

This presentation gives insight into the research activities and efforts being executed in order to integrate unmanned aircraft systems into the national airspace system. This briefing is to inform others of the UAS-NAS FY16 progress and future directions.

Active Sites Environmental Monitoring Program: FY 1990 annual report

International Nuclear Information System (INIS)

Wickliff, D.S.; Morrissey, C.M.; Ashwood, T.L.

1991-10-01

Chapter 3 of US Department of Energy (DOE) Order 5820.2A (DOE 1988) sets forth requirements for environmental monitoring of active low-level waste (LLW) disposal sites. Active sites are defined as those LLW facilities that were in use on or after the date of the order (September 1988). The transuranic (TRU) waste storage areas in Solid Waste Storage Area (SWSA) 5 North are covered by Chap. 2 of the order. In both chapters, monitoring is required to provide for early warning of leaks before those leaks pose a threat to human health or the environment. Chapter 3 also requires that monitoring be conducted to evaluate the short- and long-term performance of LLW disposal facilities. In accordance with this order, the Solid Waste Operations Department at Oak Ridge National Laboratory (ORNL) has established an Active Sites Environmental Monitoring Program (ASEMP) that is implemented by staff of the Environmental Sciences Division (ESD) at ORNL. This report summarizes data from ASEMP monitoring activities for the final 6 months of FY 1990. A brief summary of the monitoring methodology for each site is presented also

Analytical Chemistry Laboratory. Progress report for FY 1996

Energy Technology Data Exchange (ETDEWEB)

Green, D.W.; Boparai, A.S.; Bowers, D.L.

1996-12-01

The purpose of this report is to summarize the activities of the Analytical Chemistry Laboratory (ACL) at Argonne National Laboratory (ANL) for Fiscal Year (FY) 1996. This annual report is the thirteenth for the ACL. It describes effort on continuing and new projects and contributions of the ACL staff to various programs at ANL. The ACL operates in the ANL system as a full-cost-recovery service center, but has a mission that includes a complementary research and development component: The Analytical Chemistry Laboratory will provide high-quality, cost-effective chemical analysis and related technical support to solve research problems of our clients -- Argonne National Laboratory, the Department of Energy, and others -- and will conduct world-class research and development in analytical chemistry and its applications. Because of the diversity of research and development work at ANL, the ACL handles a wide range of analytical chemistry problems. Some routine or standard analyses are done, but the ACL usually works with commercial laboratories if our clients require high-volume, production-type analyses. It is common for ANL programs to generate unique problems that require significant development of methods and adaption of techniques to obtain useful analytical data. Thus, much of the support work done by the ACL is very similar to our applied analytical chemistry research.

Disposable bioprocessing: the future has arrived.

Science.gov (United States)

Rao, Govind; Moreira, Antonio; Brorson, Kurt

2009-02-01

Increasing cost pressures are driving the rapid adoption of disposables in bioprocessing. While well ensconced in lab-scale operations, the lower operating/ validation costs at larger scale and relative ease of use are leading to these systems entering all stages and operations of a typical biopharmaceutical manufacturing process. Here, we focus on progress made in the incorporation of disposable equipment with sensor technology in bioprocessing throughout the development cycle. We note that sensor patch technology is mostly being adapted to disposable cell culture devices, but future adaptation to downstream steps is conceivable. Lastly, regulatory requirements are also briefly assessed in the context of disposables and the Process Analytical Technologies (PAT) and Quality by Design (QbD) initiatives.

Report of interim evaluation of Horonobe Underground Research Project Plan in FY2004

International Nuclear Information System (INIS)

2005-09-01

The research results on the ground in the first step, until 2004 FY, and the research program of drift work in the second step are evaluated. On the first step, development of the geological environment research technologies, the monitoring technologies and the basic engineering technologies in the deep underground, long period stability of geological environment, and improvement of the geological disposal technologies, and the stability evaluation methods are investigated and these research results were high in estimation. The research program in the second step contains to obtain the geological environment data at sinking shaft, the effects of sinking on the geological environment, validity of the geological environment model in the first step and around the shaft are estimated. Validity of monitoring technologies of geological environment on the ground, engineering technologies of work, maintenance and management of shaft are evaluated. The fault, upheaval, submergence, change of sea level and climate are determined by earthquakes measurements, GPS and time-stratigraphic classification. The geological disposal technologies are improved by storage of data, better model and verification of engineering element techniques. Test program of materials transition in the geological disposal system is work out. (S.Y.)

DOE Hydropower Program Annual Report for FY 2004

Energy Technology Data Exchange (ETDEWEB)

Sommers, Garold L. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Hunt, Richard T. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Cada, Glenn F. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Sale, Michael J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Dauble, Dennis D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Carlson, Thomas [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ahlgrimm, James [U.S. Dept. of Energy, Washington, D.C. (United States); Acker, Tomas L. [National Renewable Energy Lab. (NREL), Golden, CO (United States)

2005-02-01

This report describes the progress of the R&D conducted in FY 2004 the under four program areas at the time: (1) Advanced Hydropower Technology (Large Turbine Field Testing, Water Use Optimization, and Improved Mitigation Practices); (2) Supporting Research and Testing (Environmental Performance Testing Methods, Computational and Physical Modeling, Instrumentation and Controls, and Environmental Analysis); (3) Systems Integration and Technology Acceptance (Hydro/Wind Integration, National Hydropower Collaborative, and Integration and Communications); and (4) Supporting Engineering and Analysis (Valuation Methods and Assessments and Characterization of Innovative Technology).

RELAP-7 Progress Report. FY-2015 Optimization Activities Summary

Energy Technology Data Exchange (ETDEWEB)

Berry, Ray Alden [Idaho National Lab. (INL), Idaho Falls, ID (United States); Zou, Ling [Idaho National Lab. (INL), Idaho Falls, ID (United States); Andrs, David [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2015-09-01

This report summarily documents the optimization activities on RELAP-7 for FY-2015. It includes the migration from the analytical stiffened gas equation of state for both the vapor and liquid phases to accurate and efficient property evaluations for both equilibrium and metastable (nonequilibrium) states using the Spline-Based Table Look-up (SBTL) method with the IAPWS-95 properties for steam and water. It also includes the initiation of realistic closure models based, where appropriate, on the U.S. Nuclear Regulatory Commission’s TRACE code. It also describes an improved entropy viscosity numerical stabilization method for the nonequilibrium two-phase flow model of RELAP-7. For ease of presentation to the reader, the nonequilibrium two-phase flow model used in RELAP-7 is briefly presented, though for detailed explanation the reader is referred to RELAP-7 Theory Manual [R.A. Berry, J.W. Peterson, H. Zhang, R.C. Martineau, H. Zhao, L. Zou, D. Andrs, “RELAP-7 Theory Manual,” Idaho National Laboratory INL/EXT-14-31366(rev. 1), February 2014].

radioactive waste disposal standards abroad

International Nuclear Information System (INIS)

Lu Yan; Xin Pingping; Wu Jian; Zhang Xue

2012-01-01

With the world focus on human health and environmental protection, the problem of radioactive waste disposal has gradually become a global issue, and the focus of attention of public. The safety of radioactive waste disposal, is not only related to human health and environmental safety, but also an important factor of affecting the sustainable development of nuclear energy. In recent years the formulation of the radioactive waste disposal standards has been generally paid attention to at home and abroad, and it has made great progress. In China, radioactive waste management standards are being improved, and there are many new standards need to be developed. The revised task of implement standards is very arduous, and there are many areas for improvement about methods and procedures of the preparation of standards. This paper studies the current situation of radioactive waste disposal standards of the International Atomic Energy Agency, USA, France, Britain, Russia, Japan, and give some corresponding recommendations of our radioactive waste disposal standards. (authors)

Reversible deep disposal

International Nuclear Information System (INIS)

2009-10-01

This presentation, given by the national agency of radioactive waste management (ANDRA) at the meeting of October 8, 2009 of the high committee for the nuclear safety transparency and information (HCTISN), describes the concept of deep reversible disposal for high level/long living radioactive wastes, as considered by the ANDRA in the framework of the program law of June 28, 2006 about the sustainable management of radioactive materials and wastes. The document presents the social and political reasons of reversibility, the technical means considered (containers, disposal cavities, monitoring system, test facilities and industrial prototypes), the decisional process (progressive development and blocked off of the facility, public information and debate). (J.S.)

Key scientific challenges in geological disposal of high level radioactive waste

International Nuclear Information System (INIS)

Wang Ju

2007-01-01

The geological disposal of high radioactive waste is a challenging task facing the scientific and technical world. This paper introduces the latest progress of high level radioactive disposal programs in the latest progress of high level radioactive disposal programs in the world, and discusses the following key scientific challenges: (1) precise prediction of the evolution of a repository site; (2) characteristics of deep geological environment; (3) behaviour of deep rock mass, groundwater and engineering material under coupled con-ditions (intermediate to high temperature, geostress, hydraulic, chemical, biological and radiation process, etc); (4) geo-chemical behaviour of transuranic radionuclides with low concentration and its migration with groundwater; and (5) safety assessment of disposal system. Several large-scale research projects and several hot topics related with high-level waste disposal are also introduced. (authors)

LSTA Allotments (FY 2003-2016)

Data.gov (United States)

Institute of Museum and Library Services — Review Library Services and Technology Act (LSTA) allotments by state from FY 2003 to FY 2016. The Grants to States program is the largest source of federal funding...

Status of Progress Made Toward Safety Analysis and Technical Site Evaluations for DOE Managed HLW and SNF.

Energy Technology Data Exchange (ETDEWEB)

Sevougian, S. David [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Stein, Emily [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Gross, Michael B [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hammond, Glenn Edward [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Frederick, Jennifer M [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Mariner, Paul [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2016-11-01

The Spent Fuel and Waste Science and Technology (SFWST) Campaign of the U.S. Department of Energy (DOE) Office of Nuclear Energy (NE) is conducting research and development (R&D) on generic deep geologic disposal systems (i.e., repositories). This report describes specific activities in FY 2016 associated with the development of a Defense Waste Repository (DWR)a for the permanent disposal of a portion of the HLW and SNF derived from national defense and research and development (R&D) activities of the DOE.

FY2000 Annual Self-Evaluation Report for the Pacific Northwest National Laboratory

Energy Technology Data Exchange (ETDEWEB)

RR Labarge

2000-11-15

This self-evaluation report offers a summary of results from FY2000 actions to achieve Pacific Northwest National Laboratory's strategy and provides an analysis of the state of their self-assessment process. The result of their integrated planning and assessment process identifies Laboratory strengths and opportunities for improvement. Critical elements of that process are included in this report; namely, a high-level summary of external oversight activities, progress against Operations Improvement Initiatives, and a summary of Laboratory strengths and areas for improvement developed by management from across the laboratory. Some key areas targeted for improvement in FY2001 are: systems approach to resource management; information protection; integrated safety management flow-down to the benchtop; cost management; integrated assessment; Price Anderson Amendments Act (PAAA) Program; and travel risk mitigation.

FY 10 Multifamily Initial Endorsements

Data.gov (United States)

Department of Housing and Urban Development — In FY 2010, HUD's Multifamily's 18 Hubs initially endorsed 1011 loans totaling $11.3 billion and providing 170,672 units/ beds. FY 10's $11.3 billion is the highest...

Seabed Disposal Program. Annual report, January--December 1975

International Nuclear Information System (INIS)

Talbert, D.M.

1976-05-01

This document is the report of the activities in the Seabed Disposal Program for CY 1975. A summary is given of the progress made to determine the feasibility of disposal of high-level solidified and encapsulated radioactive wastes into the deep seafloor. While a considerable amount of work remains to be done to assure safety and feasibility, no technological reasons have been presented that would preclude the possibility of successful disposal into submarine geologic media

Study on the background information for the geological disposal concept

International Nuclear Information System (INIS)

Matsui, Kazuaki; Murano, Tohru; Hirusawa, Shigenobu; Komoto, Harumi

1999-11-01

Japan Nuclear Cycle Development Institute (JNC) has published the first R and D progress report in 1992. In which the fruits of the R and D works were compiled. Since then the next step of R and D has been developing progressively in Japan. Now JNC has a plan to make the second R and D progress report until before 2000, in which information on the geological disposal of high level radioactive waste(HLW) will be presented to show the technical reliability and technical basis to contribute for the site selection or the safety-standard developments. Recognizing the importance of the social consensus to the geological disposal of international discussions in 1990's, understanding and consensus by the society are essential to the development and realization of the geological disposal of HLW. For getting social understanding and consensus, it is quite important to present the broad basis background information on the geological disposal of HLW, together with the technical basis and also the international discussion of the issues. In this report, the following studies have been done to help to prepare the background information for the 2nd R and D progress report, based on the recent informations and research and assessment works of last 2 years. These are, (1) As the part of general discussion, characteristics of HLW disposal and several issues to be considered for establishing the measures of the disposal of HLW were identified and analyzed from both practical and logical points of view. Those issues were the concept and image of the long term safety measures, the concept and criteria of geological disposal, and, safety assessment and performance assessment. (2) As the part of specific discussion, questions and concerns frequently raised by the non-specialists were taken up and 10 topics in relation to the geological disposal have been identified based on the discussion. Scientific and technical facts, consensus by the specialists on the issues, and international

Evaluations for draft reports on geological disposal

International Nuclear Information System (INIS)

Maekawa, Keisuke; Igarashi, Hiroshi

2002-10-01

This report summarizes the results of the technical evaluations on two reports which are named as 'Overview of the Geological Disposal Facility' and Considerable Factors on Selection of Potential Sites for Geological Disposal' drafted by NUMO (Nuclear Waste Management Organization of Japan). The review of each draft report has been referred to committee (held on 9th September, 2002) and working group (held on 1st October, 2002) which were organized in order to confirm a progress of implementation of geological disposal by government. (author)

FY 2009 National Renewable Energy Laboratory (NREL) Annual Report: A Year of Energy Transformation

Energy Technology Data Exchange (ETDEWEB)

2010-01-01

This FY2009 Annual Report surveys the National Renewable Energy Laboratory's (NREL) accomplishments in renewable energy and energy efficiency research and development, commercialization and deployment of technologies, and strategic energy analysis. It offers NREL's vision and progress in building a clean, sustainable research campus and reports on community involvement.

Geothermal Progress Monitor report No. 5. Progress report, June 1981

Energy Technology Data Exchange (ETDEWEB)

1981-01-01

Updated information is presented on activities and progress in the areas of electric power plants, direct heat applications, deep well drilling, leasing of federal lands, legislative and regulatory actions, research and development, and others. Special attention is given in this report to 1980 highlights, particularly in the areas of electric and direct heat uses, drilling, and the Federal lands leasing program. This report also includes a summary of the DOE FY 1982 geothermal budget request to Congress.

In situ vitrification program treatability investigation progress report

International Nuclear Information System (INIS)

Arrenholz, D.A.

1991-02-01

This document presents a summary of the efforts conducted under the in situ vitrification treatability study during the period from its initiation in FY-88 until FY-90. In situ vitrification is a thermal treatment process that uses electrical power to convert contaminated soils into a chemically inert and stable glass and crystalline product. Contaminants present in the soil are either incorporated into the product or are pyrolyzed during treatment. The treatability study being conducted at the Idaho National Engineering Laboratory by EG ampersand G Idaho is directed at examining the specific applicability of the in situ vitrification process to buried wastes contaminated with transuranic radionuclides and other contaminants found at the Subsurface Disposal Area of the Radioactive Waste Management Complex. This treatability study consists of a variety of tasks, including engineering tests, field tests, vitrified product evaluation, and analytical models of the in situ vitrification process. 6 refs., 4 figs., 3 tabs

A plan for administrative computing at ANL FY1991 through FY1993

Energy Technology Data Exchange (ETDEWEB)

Caruthers, L.E. (ed.); O' Brien, D.E.; Bretscher, M.E.; Hischier, R.C.; Moore, N.J.; Slade, R.G.

1990-10-01

In July of 1988, Argonne National Laboratory management approved the restructuring of Computing Services into the Computing and Telecommunications Division, part of the Physical Research area of the Laboratory. One major area of the Computing and Telecommunications Division is Management Information Systems (MIS). A significant aspect of Management Information Systems' work is the development of proposals for new and enhanced administrative computing systems based on an analysis of informational needs. This document represent the outcome of the planning process for FY1991 through FY1993. The introduction of the FY1991 through FY1993 Long-Range Plan assesses the state of administrative computing at ANL and the implications of FY1991 funding recommendations. It includes a history of MIS planning for administrative data processing. This document discusses the strategy and goals which are an important part of administrative data processing plans for the Laboratory. It also describes the management guidelines established by the Administrative Data Processing Oversight Committee for the proposal and implementation of administrative computing systems. Summaries of the proposals for new or enhanced administrative computing systems presented by individual divisions or departments with assistance of Management Information Systems, to the Administrative Data Processing Oversight Committee are given. The detailed tables in this paper give information on how much the resources to develop and implement a given systems will cost its users. The tables include development costs, computing/operations costs, software and hardware costs, and efforts costs. They include both systems funded by Laboratory General Expense and systems funded by the users themselves.

A Portable Burn Pan for the Disposal of Excess Propellants

Science.gov (United States)

2016-06-01

2013 - 06/01/2016 A Portable Burn Pan for the Disposal of Excess Propellants Michael Walsh USA CRREL USA CRREL 72 Lyme Road Hanover, NH 03755...Army Alaska XRF X-Ray Florescence vii ACKNOWLEDGEMENTS Project ER-201323, A Portable Burn Pan for the Disposal of Gun Propellants, was a very...contamination problem while allowing troops to train as they fight, we have developed a portable training device for burning excess gun propellants. 1.1

Area G perimeter surface-soil and single-stage water sampling: Environmental surveillance for fiscal year 94, Group ESH-19. Progress report

International Nuclear Information System (INIS)

Conrad, R.; Childs, M.; Lyons, C.R.; Coriz, F.

1996-08-01

ESH-19 personnel collected soil and single-stage water samples around the perimeter of Area G at Los Alamos National Laboratory during FY94 to characterize possible contaminant movement out of Area G through surface-water and sediment runoff. These samples were analyzed for tritium, total uranium, isotopic plutonium, americium-241, and cesium-137. Ten metals were also analyzed on selected soils using analytical laboratory techniques. All radiochemical data are compared with analogous samples collected during FY 93 and reported in LA-12986. Baseline concentrations for future disposal operations were established for metals and radionuclides by a sampling program in the proposed Area G Expansion Area. Considering the amount of radioactive waste that has been disposed at Area G, there is evidence of only low concentrations of radionuclides on perimeter surface soils. Consequently, little radioactivity is leaving the confines of Area G via the surface water runoff pathway

Analytical Chemistry Laboratory, progress report for FY 1993

Energy Technology Data Exchange (ETDEWEB)

1993-12-01

The purpose of this report is to summarize the activities of the Analytical Chemistry Laboratory (ACL) at Argonne National Laboratory (ANL) for Fiscal Year (FY) 1993 (October 1992 through September 1993). This annual report is the tenth for the ACL and describes continuing effort on projects, work on new projects, and contributions of the ACL staff to various programs at ANL. The Analytical Chemistry Laboratory is a full-cost-recovery service center, with the primary mission of providing a broad range of analytical chemistry support services to the scientific and engineering programs at ANL. The ACL also has research programs in analytical chemistry, conducts instrumental and methods development, and provides analytical services for governmental, educational, and industrial organizations. The ACL handles a wide range of analytical problems. Some routine or standard analyses are done, but it is common for the Argonne programs to generate unique problems that require development or modification of methods and adaption of techniques to obtain useful analytical data. The ACL is administratively within the Chemical Technology Division (CMT), its principal ANL client, but provides technical support for many of the technical divisions and programs at ANL. The ACL has four technical groups--Chemical Analysis, Instrumental Analysis, Organic Analysis, and Environmental Analysis--which together include about 45 technical staff members. Talents and interests of staff members cross the group lines, as do many projects within the ACL.

Explanation of ICRP publication 81 in consideration of geologic disposal

International Nuclear Information System (INIS)

Kosako, Toshiso; Sugiura, Nobuyuki; Yamamoto, Hideaki

2003-01-01

The International Commission on Radiological Protection which has published various recommendations on the radiation protection describes the system of radiation protection on the disposal of radioactive waste in Publication 46, 77 and 81. Especially, Publication 81, Radiation Protection Recommendations as Applied to the Disposal of Long-lived Solid Radioactive Waste, was published in order to supplement, update and clarify the material in Publication 46 published in 1985 in consideration of the recent international progress in the disposal of radioactive waste. At present, the study is in progress to materialize the concept and the safety regulation of geologic disposal in Japan, and it is important to reflect appropriately these international publications. This paper explains each paragraph in Publication 81 in order to understand the system of radiation protection on the geologic disposal fully and concretely, paying attention to the mutual relationship among each paragraph, the development of ICRP recommendations and the relationship to other publications. (author)

Physics division. Progress report, January 1, 1995--December 31, 1996

International Nuclear Information System (INIS)

Stewart, M.; Bacon, D.S.; Aine, C.J.; Bartsch, R.R.

1997-10-01

This issue of the Physics Division Progress Report describes progress and achievements in Physics Division research during the period January 1, 1995-December 31, 1996. The report covers the five main areas of experimental research and development in which Physics Division serves the needs of Los Alamos National Laboratory and the nation in applied and basic sciences: (1) biophysics, (2) hydrodynamic physics, (3) neutron science and technology, (4) plasma physics, and (5) subatomic physics. Included in this report are a message from the Division Director, the Physics Division mission statement, an organizational chart, descriptions of the research areas of the five groups in the Division, selected research highlights, project descriptions, the Division staffing and funding levels for FY95-FY97, and a list of publications and presentations

Physics division. Progress report, January 1, 1995--December 31, 1996

Energy Technology Data Exchange (ETDEWEB)

Stewart, M.; Bacon, D.S.; Aine, C.J.; Bartsch, R.R. [eds.] [comps.] [and others

1997-10-01

This issue of the Physics Division Progress Report describes progress and achievements in Physics Division research during the period January 1, 1995-December 31, 1996. The report covers the five main areas of experimental research and development in which Physics Division serves the needs of Los Alamos National Laboratory and the nation in applied and basic sciences: (1) biophysics, (2) hydrodynamic physics, (3) neutron science and technology, (4) plasma physics, and (5) subatomic physics. Included in this report are a message from the Division Director, the Physics Division mission statement, an organizational chart, descriptions of the research areas of the five groups in the Division, selected research highlights, project descriptions, the Division staffing and funding levels for FY95-FY97, and a list of publications and presentations.

Development of the Internet Library for the Second Progress Report on R and D for the geological disposal of HLW in Japan

International Nuclear Information System (INIS)

Shiotsuki, Masao; Ishikawa, Hirohisa

2000-01-01

This paper describes an Internet Library, the goal of which is to improve the quality assurance of the technical content of the Second Progress Report on R and D into the geological disposal of HLW in Japan. The Internet Library is used to centralize information management for the Second Progress Report. It uses a database system which stores a large quantity of technical memoranda and numeric data which provide the technical basis for the report. Members of the public and specialists are allowed access the data held on the system and may communicate their opinions and expert reviews, through the Internet. (author)

Advanced Neutron Source (ANS) Project progress report, FY 1994

Energy Technology Data Exchange (ETDEWEB)

Campbell, J.H.; King-Jones, K.H. [eds.; Selby, D.L.; Harrington, R.M. [Oak Ridge National Lab., TN (United States); Thompson, P.B. [Martin Marietta Energy Systems, Inc., Oak Ridge, TN (United States). Central Engineering Services

1995-01-01

The President`s budget request for FY 1994 included a construction project for the Advanced Neutron Source (ANS). However, the budget that emerged from the Congress did not, and so activities during this reporting period were limited to continued research and development and to advanced conceptual design. A significant effort was devoted to a study, requested by the US Department of Energy (DOE) and led by Brookhaven National Laboratory, of the performance and cost impacts of reducing the uranium fuel enrichment below the baseline design value of 93%. The study also considered alternative core designs that might mitigate those impacts. The ANS Project proposed a modified core design, with three fuel elements instead of two, that would allow operation with only 50% enriched uranium and use existing fuel technology. The performance penalty would be 15--20% loss of thermal neutron flux; the flux would still just meet the minimum design requirement set by the user community. At the time of this writing, DOE has not established an enrichment level for ANS, but two advisory committees have recommended adopting the new core design, provided the minimum flux requirements are still met.

Advanced Neutron Source (ANS) Project progress report, FY 1994

International Nuclear Information System (INIS)

Campbell, J.H.; King-Jones, K.H.; Thompson, P.B.

1995-01-01

The President's budget request for FY 1994 included a construction project for the Advanced Neutron Source (ANS). However, the budget that emerged from the Congress did not, and so activities during this reporting period were limited to continued research and development and to advanced conceptual design. A significant effort was devoted to a study, requested by the US Department of Energy (DOE) and led by Brookhaven National Laboratory, of the performance and cost impacts of reducing the uranium fuel enrichment below the baseline design value of 93%. The study also considered alternative core designs that might mitigate those impacts. The ANS Project proposed a modified core design, with three fuel elements instead of two, that would allow operation with only 50% enriched uranium and use existing fuel technology. The performance penalty would be 15--20% loss of thermal neutron flux; the flux would still just meet the minimum design requirement set by the user community. At the time of this writing, DOE has not established an enrichment level for ANS, but two advisory committees have recommended adopting the new core design, provided the minimum flux requirements are still met

Research and development for treatment and disposal technologies of TRU waste

International Nuclear Information System (INIS)

Kamei, Gento; Honda, Akira; Mihara, Morihiro; Oda, Chie; Murakami, Hiroshi; Masuda, Kenta; Yamaguchi, Kohei; Nakanishi, Hiroshi; Sasaki, Ryoichi; Ichige, Satoru; Takahashi, Kuniaki; Meguro, Yoshihiro; Yamaguchi, Hiromi; Aoyama, Yoshio

2007-09-01

After the publication of the 2nd progress report of geological disposal of TRU waste in Japan, policy and general scheme of future study for the waste disposal in Japan was published by ANRE and JAEA. This annual report summarized aim and progress of individual problem, which was assigned into JAEA in the published policy and general scheme. The problems are as follows; characteristics of TRU waste and its geologic disposal, treatment and waste production, quality control and inspection methodology for waste, mechanical analysis of near-field, data acquisition and preparation on radionuclides migration, cementitious material transition, bentonite and rock alteration in alkaline solution, nitrate effect, performance assessment of the disposal system and decomposition of nitrate as an alternative technology. (author)

Active Time-Domain Reflectometry for Unattended Safeguards Systems FY15 Report

Energy Technology Data Exchange (ETDEWEB)

Tedeschi, Jonathan R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Smith, Leon E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Moore, David E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Sheen, David M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Conrad, Ryan C. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Gavric, Gordan [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2015-09-01

The International Atomic Energy Agency (IAEA) continues to expand its use of unattended measurement systems. An increasing number of systems and an expanding family of instruments create challenges in terms of deployment efficiency and the implementation of data authentication measures. In collaboration with the IAEA, tamper-indicating measures to address data-transmission authentication challenges with unattended safeguards systems are under investigation. Pacific Northwest National Laboratory (PNNL) is studying the viability of active time-domain reflectometry (TDR) along two parallel but interconnected paths: (1) swept-frequency TDR as the highly flexible, laboratory gold standard to which field-deployable options can be compared, and (2) a low-cost commercially available spread-spectrum TDR technology as one option for field implementation. This report describes PNNL’s FY15 progress in the viability study including: an overview of the TDR methods under investigation; description of the testing configurations and mock tampering scenarios; results from a preliminary sensitivity comparison of the two TDR methods; demonstration of a quantitative metric for estimating field performance that acknowledges the need for high detection probability while minimizing false alarms. FY15 progress reported here sets the stage for a rigorous comparison of the candidate TDR methods, over a range of deployment scenarios and perturbing effects typical of IAEA unattended monitoring systems.

Development of an integrated software system (Digital Geological Disposal System) for design and evaluation of HLW disposal system

International Nuclear Information System (INIS)

Fusaeda, Shigeki; Yanagisawa, Ichiro; Imamura, Naoko

2000-02-01

In this study, a design study on 'Digital Geological Disposal System' has been carried out in order to define the developmental goal for the first phase (-FY2002) system and to demonstrate the feasibility of the system development. The key conclusions are summarized as follows: (1) As the result of the basic design of the Integrated Analysis Platform (IAP), the representation method for the procedure of analysis that is called analysis network, the configuration of the object that makes up the analysis network, and the execution control mechanism of the analysis network are newly proposed in order to enhance the flexibility of IAP. (2) A prototyping study concerning an optimization problem that includes cavity stability analysis and thermal analysis, showed that the design of IAP is practical one and also has enough flexibility to solve complex problems expected in the repository design processes. (3) The development plan for the 'Digital Geological Disposal System' has been investigated based on the discussions about the system usage by the potential users such as the regulators, the implementation body and the research institutes, as well as the technical discussions. As a result, short-term (for the first phase) and long-term development plans have been proposed. (author)

Environmental Systems Research and Analysis FY 2000 Annual Report

Energy Technology Data Exchange (ETDEWEB)

David L. Miller; Castle, Peter Myer; Steven J. Piet

2001-01-01

The Environmental Systems Research (ESR) Program, a part of the Environmental Systems Research and Analysis (ESRA) Program, was implemented to enhance and augment the technical capabilities of the INEEL. Strengthening the Technical capabilities of the INEEL will provide the technical base to serve effectively as the Environmental Management Laboratory for the Office of Environmental Management (EM). This is a progress report for the third year of the ESR Program (FY 2000). A report of activities is presented for the five ESR research investment areas: (1) Transport Aspects of Selective Mass Transport Agents, (2) Chemistry of Environmental Surfaces, (3) Materials Dynamics, (4) Characterization Science, and (5) Computational Simulation of Mechanical and Chemical Systems. In addition to the five technical areas, the report describes activities in the Science and Technology Foundations element of the program, e.g., interfaces between ESR and the EM Science Program (EMSP) and the EM Focus Areas. The five research areas are subdivided into 18 research projects. FY 2000 research in these 18 projects has resulted in more than 50 technical papers that are in print, in press, in review, or in preparation. Additionally, more than 100 presentations were made at professional society meetings nationally and internationally. Work supported by this program was in part responsible for one of our researchers, Dr. Mason Harrup, receiving the Department of Energy’s “Bright Light” and “Energy at 23” awards. Significant accomplishments were achieved. Non-Destructive Assay hardware and software was deployed at the INEEL, enhancing the quality and efficiency of TRU waste characterization for shipment. The advanced tensiometer has been employed at numerous sites around the complex to determine hydrologic gradients in variably saturated vadose zones. An ion trap, secondary ion mass spectrometer (IT-SIMS) was designed and fabricated to deploy at the INEEL site to measure the

DOE Hydropower Program Biennial Report for FY 2005-2006

Energy Technology Data Exchange (ETDEWEB)

Sale, Michael J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Cada, Glenn F. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Acker, Thomas L. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Northern Arizona State Univ., Flagstaff, AZ (United States); Carlson, Thomas [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Dauble, Dennis D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Hall, Douglas G. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2006-07-01

This report describes the progress of the R&D conducted in FY 2005-2006 the under four program areas at the time: (1) Advanced Hydropower Technology (Large Turbine Field Testing, Water Use Optimization, and Improved Mitigation Practices); (2) Supporting Research and Testing (Environmental Performance Testing Methods, Computational and Physical Modeling, Instrumentation and Controls, and Environmental Analysis); (3) Systems Integration and Technology Acceptance (Hydro/Wind Integration, National Hydropower Collaborative, and Integration and Communications); and (4) Supporting Engineering and Analysis (Valuation Methods and Assessments and Characterization of Innovative Technology).

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

International Nuclear Information System (INIS)

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

1991-07-01

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

Waste acid detoxification and reclamation: Final Phase II report: Summary of distillation and material degradation tests for FY 1987 and FY 1988

International Nuclear Information System (INIS)

Brouns, T.M.; Stewart, T.L.

1988-11-01

The objective of the Waste Acid Detoxification and Reclamation project is to develop processes for reducing the volume, quantity, and toxicity of metal-bearing waste acids. The primary incentives for implementing these types of waste minimization processes are regulatory and economic (that is, to meet requirements in the Resource Conservation and Recovery Act and reduce the cost for treatment, storage, and disposal). Two precipitation processes and a distillation process are being developed to minimize waste from fuel fabrication operations or other metal-finishing operations conducted at US Department of Energy Defense Programs (DOE-DP) facilities. Waste process acids such as (1) HF-HNO 3 etch solutions containing Zr as a major metal impurity, and (2) HNO 3 strip solutions containing Cu as a major metal impurity are detoxified and reclaimed by concurrently precipitating heavy metals and regenerating acid for recycle. Acid from a third waste acid stream generated from chemical milling operations is reclaimed by the use of distillation. This stream comprises HNO 3 and H 2 SO 4 containing U as the major metal impurity. Distillation allows NO 3 /sup /minus// to be displaced by SO 4 /sup /minus/2/ in metal salts; free HNO 3 is then vaporized from the U-bearing sulfate stream. In a downstream precipitation step, uranium can be recovered from the sulfate stream. This report summarizes distillation tests and candidate material degradation tests conducted during FY 1987 and FY 1988

Progress of decommissioning of Rikkyo reactor in FY2014

International Nuclear Information System (INIS)

Suzuki, M.; Kato, M.; Tanzawa, T.; Kawaguchi, K.; Terasawa, T.; Yamada, Shigeru; Nakai, Masaru

2015-01-01

Institute for Atomic Energy, Rikkyo University, applied in 2012 for changes in the decommissioning plan toward the abolition of the reactor facilities, and received approval. It promoted the decommissioning work of the research reactors in a plan for two years from 2012, conducted the removal of the structure installed in the reactor tank and storage management measures, and implemented the function stop of the disposal facility of liquid waste and the removal of part of them. These procedures achieved the safe storage condition of core internal structure / equipment with relatively high radioactivity due to neutron irradiation. In addition, the maintenance management of partial facilities and equipment that had been maintained in operational conditions had come to be unnecessary. Based on these results, the implementation plan for decommissioning scheduled for 2015-2016 was prepared. The contents of main works are as follows: (1) dismantling and removal of disposal facilities for liquid waste and storage management of subsequently generated radioactive waste in the reactor building control area, (2) storage management of radioactive solid waste of solid waste storage facilities in the reactor building control area, (3) dismantling and removal of solid waste storage facilities that become unnecessary, and (4) release of part of the controlled area associated with the above actions. (A.O.)

A descriptive model of the molten salt reactor experiment after shutdown: Review of FY 1995 progress

International Nuclear Information System (INIS)

Williams, D.F.; Del Cul, G.D.; Toth, L.M.

1996-01-01

During FY 1995 considerable progress was made toward gaining a better understanding of the chemistry and transport processes that continue to govern the behavior of the Molten Salt Reactor Experiment (MSRE). As measurements in the MSRE proceed, laboratory studies continue, and better analyses are available, our understanding of the state of the MSRE and the best path toward remediation improves. Because of the immediate concern about the deposit in the auxiliary charcoal bed (ACB), laboratory studies in the past year focused on carbon-fluorine chemistry. Secondary efforts were directed toward investigation of gas generation from MSRE salts by both radiolytic and nonradiolytic pathways. In addition to the laboratory studies, field measurements at the MSRE provided the basis for estimating the inventory of uranium and fluorine in the ACB. Analysis of both temperature and radiation measurements provided independent and consistent estimates of about 2.6 kg of uranium deposited in the top of the ACB. Further analysis efforts included a refinement in the estimates of the fuel- salt source term, the deposited decay energy, and the projected rate of radiolytic gas generation. This report also provides the background material necessary to explain new developments and to review areas of particular interest. The detailed history of the MSRE is extensively documented and is cited where appropriate. This work is also intended to update and complement the more recent MSRE assessment reports

A descriptive model of the molten salt reactor experiment after shutdown: Review of FY 1995 progress

Energy Technology Data Exchange (ETDEWEB)

Williams, D.F.; Del Cul, G.D.; Toth, L.M.

1996-01-01

During FY 1995 considerable progress was made toward gaining a better understanding of the chemistry and transport processes that continue to govern the behavior of the Molten Salt Reactor Experiment (MSRE). As measurements in the MSRE proceed, laboratory studies continue, and better analyses are available, our understanding of the state of the MSRE and the best path toward remediation improves. Because of the immediate concern about the deposit in the auxiliary charcoal bed (ACB), laboratory studies in the past year focused on carbon-fluorine chemistry. Secondary efforts were directed toward investigation of gas generation from MSRE salts by both radiolytic and nonradiolytic pathways. In addition to the laboratory studies, field measurements at the MSRE provided the basis for estimating the inventory of uranium and fluorine in the ACB. Analysis of both temperature and radiation measurements provided independent and consistent estimates of about 2.6 kg of uranium deposited in the top of the ACB. Further analysis efforts included a refinement in the estimates of the fuel- salt source term, the deposited decay energy, and the projected rate of radiolytic gas generation. This report also provides the background material necessary to explain new developments and to review areas of particular interest. The detailed history of the MSRE is extensively documented and is cited where appropriate. This work is also intended to update and complement the more recent MSRE assessment reports.

Annual report of the Neutron Irradiation and Testing Reactor Center. FY 2008. April 1, 2008 - March 31, 2009

International Nuclear Information System (INIS)

2009-12-01

The JMTR, one of the most high flux test reactors in the world, has been used for the irradiation experiments of fuels and materials related to LWRs, fundamental research and radioisotope productions. The JMTR was stopped at the beginning of August 2006 to conduct refurbishment works, and the reoperation will be planned from FY 2011. After reoperation, the JMTR will contribute to many fields, such as the lifetime extension of LWRs, expansion of industrial use, progress of science and technology. This report summarizes the activities on refurbishment works, development of new irradiation techniques, enhancement of reactor availability, etc. in FY 2008. (author)

Environmental Sciences Division annual progress report for period ending September 30, 1990

International Nuclear Information System (INIS)

1991-04-01

The Environmental Sciences Division (ESD) of Oak Ridge National Laboratory (ORNL) conducts research on the environmental aspects of existing and emerging energy systems and applies this information to ensure that technology development and energy use are consistent with national environmental health and safety goals. Offering an interdisciplinary resource of staff and facilities to address complex environmental problems, the division is currently providing technical leadership for major environmental issues of national concern: (1) acidic deposition and related environmental effects, (2) effects of increasing concentrations of atmospheric CO 2 and the resulting climatic changes to ecosystems and natural and physical resources, (3) hazardous chemical and radioactive waste disposal and remediation research and development, and (4) development of commercial biomass energy production systems. This progress report outlines ESD's accomplishments in these and other areas in FY 1990. Individual reports are processed separately for the data bases in the following areas: ecosystem studies; environmental analyses; environmental toxicology; geosciences; technical and administrative support; biofuels feedstock development program; carbon dioxide information analysis and research program; and environmental waste program

Environmental Sciences Division annual progress report for period ending September 30, 1990

Energy Technology Data Exchange (ETDEWEB)

1991-04-01

The Environmental Sciences Division (ESD) of Oak Ridge National Laboratory (ORNL) conducts research on the environmental aspects of existing and emerging energy systems and applies this information to ensure that technology development and energy use are consistent with national environmental health and safety goals. Offering an interdisciplinary resource of staff and facilities to address complex environmental problems, the division is currently providing technical leadership for major environmental issues of national concern: (1) acidic deposition and related environmental effects, (2) effects of increasing concentrations of atmospheric CO{sub 2} and the resulting climatic changes to ecosystems and natural and physical resources, (3) hazardous chemical and radioactive waste disposal and remediation research and development, and (4) development of commercial biomass energy production systems. This progress report outlines ESD's accomplishments in these and other areas in FY 1990. Individual reports are processed separately for the data bases in the following areas: ecosystem studies; environmental analyses; environmental toxicology; geosciences; technical and administrative support; biofuels feedstock development program; carbon dioxide information analysis and research program; and environmental waste program.

Washing and caustic leaching of Hanford tank sludge: Results of FY 1997 studies

International Nuclear Information System (INIS)

Lumetta, G.J.; Burgeson, I.E.; Wagner, M.J.; Liu, J.; Chen, Y.L.

1997-08-01

The current plan for remediating the Hanford tank farms consists of waste retrieval, pretreatment, treatment (immobilization), and disposal. The tank wastes will be partitioned into high-level and low-level fractions. The HLW will be immobilized in a borosilicate glass matrix; the resulting glass canisters will then be disposed of in a geologic repository. Because of the expected high cost of HLW vitrification and geologic disposal, pretreatment processes will be implemented to reduce the volume of immobilized high-level waste (IHLW). Caustic leaching (sometimes referred to as enhanced sludge washing or ESW) represents the baseline method for pretreating Hanford tank sludges. Caustic leaching is expected to remove a large fraction of the Al, which is present in large quantities in Hanford tank sludges. A significant portion of the P is also expected to be removed from the sludge by metathesis of water-insoluble metal phosphates to insoluble hydroxides and soluble Na 3 PO 4 . Similar metathesis reactions can occur for insoluble sulfate salts, allowing the removal of sulfate from the HLW stream. This report describes the sludge washing and caustic leaching tests performed at the Pacific Northwest National Laboratory in FY 1996. The sludges used in this study were taken from Hanford tanks AN-104, BY-108, S-101, and S-111

The FY2011 Federal Budget

Science.gov (United States)

2010-08-04

long been the largest source of federal revenues, followed by social insurance (payroll) taxes. Federal individual and corporate income tax revenues...915 billion (6.4% of GDP). Corporate income tax revenues fell from $304 billion in FY2008 to $138 billion in FY2009. Federal revenues from other

Progress towards the use of disposable filters

International Nuclear Information System (INIS)

Macphail, I.

1979-08-01

Thermally degradable materials have been evaluated for service in HEPA filter units used to filter gases from active plants. The motivation was to reduce the bulk storage problems of contaminated filters by thermal decomposition to gaseous products and a solid residue substantially comprised of the filtered particulates. It is shown that while there are no commercially available alternatives to the glass fibre used in the filter medium, it would be feasible to manufacture the filter case and spacers from materials which could be incinerated. Operating temperatures, costs and the type of residues for disposal are discussed for filter case materials. (U.K.)

Final disposal of radioactive wastes

Energy Technology Data Exchange (ETDEWEB)

Kroebel, R [Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Wiederaufarbeitung und Abfallbehandlung; Krause, H [Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Abt. zur Behandlung Radioaktiver Abfaelle

1978-08-01

This paper discusses the final disposal possibilities for radioactive wastes in the Federal Republic of Germany and the related questions of waste conditioning, storage methods and safety. The programs in progress in neighbouring CEC countries and in the USA are also mentioned briefly. The autors conclude that the existing final disposal possibilities are sufficiently well known and safe, but that they could be improved still further by future development work. The residual hazard potential of radioactive wastes from fuel reprocessing after about 1000 years of storage is lower that of known inorganic core deposits.

Waste Tank Organic Safety Project organic concentration mechanisms task. FY 1994 progress report

International Nuclear Information System (INIS)

Gerber, M.A.

1994-09-01

The Pacific Northwest Laboratory (PNL), Waste Tank Organic Safety Project is conducting research to support Westinghouse Hanford Company's (WHC) Waste Tank Safety Program, sponsored by the U.S. Department of Energy's Tank Farm Project Office. The goal of PNL's program is to provide a scientific basis for analyzing organics in Hanford's underground storage tanks (USTs) and for determining whether they are at concentrations that pose a potentially unsafe condition. Part of this research is directed toward determining what organic concentrations are safe by conducting research on organic aging mechanisms and waste energetics to assess the conditions necessary to produce an uncontrolled energy release in tanks due to reactions between the organics and the nitrate and nitrate salts in the tank wastes. The objective of the Organic Concentration Mechanisms Task is to assess the degree of localized enrichment of organics to be expected in the USTs due to concentration mechanisms. This report describes the progress of research conducted in FY 1994 on two concentration mechanisms of interest to the tank safety project: (1) permeation of a separate organic liquid phase into the interstitial spaces of the tank solids during the draining of free liquid from the tanks; and (2) concentration of organics on the surfaces of the solids due to adsorption. Three experiments were conducted to investigate permeation of air and solvent into a sludge simulant that is representative of single-shell tank sludge. The permeation behavior of air and solvent into the sludge simulant can be explained by the properties of the fluid pairs (air/supernate and solvent supernate) and the sludge. One important fluid property is the interfacial tension between the supernate and either the solvent or air. In general, the greater the interfacial tension between two fluids, the more difficult it will be for the air or solvent to displace the supernate during dewatering of the sludge

FY 2005 Supplement to the President`s Budget

Data.gov (United States)

Networking and Information Technology Research and Development, Executive Office of the President — The Supplement to the President`s FY 2005 Budget reports on the FY 2004 research and development R and D activities and FY 2005 plans of the multiagency Networking...

75 FR 15686 - NOAA'S Office of Ocean Exploration and Research (OER) Strategic Plan FY 2011-FY 2015

Science.gov (United States)

2010-03-30

...-01] NOAA'S Office of Ocean Exploration and Research (OER) Strategic Plan FY 2011-FY 2015 AGENCY... and Atmospheric Administration (NOAA), Commerce. ACTION: Notice of availability and request for public comment. [[Page 15687

Ferrycyanide Safety Program cyanide speciation studies FY 1994 annual report

International Nuclear Information System (INIS)

Bryan, S.A.; Pool, K.H.; Bryan, S.L.; Sell, R.L.; Thomas, L.M.P.; Lerner, B.D.

1994-09-01

This report summarizes Pacific Northwest Laboratories FY 1994 progress toward developing and implementing methods to identify and quantify cyanide species in ferrocyanide tank waste. Currently, there are 24 high-level waste storage tanks at the the US DOE's Hanford Site that have been placed on a Ferrocyanide Tank Watch list because they contain an estimated 1000 g-moles or more of precipitated ferrocyanide. This amount of ferrocyanide is of concern because the consequences of a potential explosion may exceed those reported previously

Horonobe underground research program. Research report of 2002 FY investigation

International Nuclear Information System (INIS)

2003-06-01

Main results of investigation about Horonobe deep underground research center in 2002 FY were reported. It consists of six chapters: introduction, main results, selection of research center area, underground science research, R and D of geological disposal, and the environmental survey and research center on the ground. The research center area at about 3 km north of Horonobe (B1) was selected in the four areas: A, B1, B2 and C on the basis of data, researches in the sky, aboveground and underground and other conditions. The model of geological environment was constructed by physical, geological, surface water supply researches. Development of geological environment monitoring techniques, investigation of long stabilization of geological environment and design of underground facilities are reported. The basic design of preparation of research center was investigated. (S.Y.)

Isotope and Nuclear Chemistry Division annual report, FY 1983

International Nuclear Information System (INIS)

Heiken, J.H.; Lindberg, H.A.

1984-05-01

This report describes progress in the major research and development programs carried out in FY 1983 by the Isotope and Nuclear Chemistry Division. It covers radiochemical diagnostics of weapons tests; weapons radiochemical diagnostics research and development; other unclassified weapons research; stable and radioactive isotope production, separation, and applications (including biomedical applications); element and isotope transport and fixation; actinide and transition metal chemistry; structural chemistry, spectroscopy, and applications; nuclear structure and reactions; irradiation facilities; advanced analytical techniques; development and applications; atmospheric chemistry and transport; and earth and planetary processes

Isotope and Nuclear Chemistry Division annual report, FY 1983

Energy Technology Data Exchange (ETDEWEB)

Heiken, J.H.; Lindberg, H.A. (eds.)

1984-05-01

This report describes progress in the major research and development programs carried out in FY 1983 by the Isotope and Nuclear Chemistry Division. It covers radiochemical diagnostics of weapons tests; weapons radiochemical diagnostics research and development; other unclassified weapons research; stable and radioactive isotope production, separation, and applications (including biomedical applications); element and isotope transport and fixation; actinide and transition metal chemistry; structural chemistry, spectroscopy, and applications; nuclear structure and reactions; irradiation facilities; advanced analytical techniques; development and applications; atmospheric chemistry and transport; and earth and planetary processes.

Building America Systems Integration Research Annual Report: FY 2012

Energy Technology Data Exchange (ETDEWEB)

Gestwick, M.

2013-05-01

This document is the Building America FY2012 Annual Report, which includes an overview of the Building America Program activities and the work completed by the National Renewable Energy Laboratory and the Building America industry consortia (the Building America teams). The annual report summarizes major technical accomplishments and progress towards U.S. Department of Energy Building Technologies Program's multi-year goal of developing the systems innovations that enable risk-free, cost effective, reliable and durable efficiency solutions that reduce energy use by 30%-50% in both new and existing homes.

Building America Systems Integration Research Annual Report. FY 2012

Energy Technology Data Exchange (ETDEWEB)

Gestwick, Michael [National Renewable Energy Lab. (NREL), Golden, CO (United States)

2013-05-01

This Building America FY2012 Annual Report includes an overview of the Building America Program activities and the work completed by the National Renewable Energy Laboratory and the Building America industry consortia (the Building America teams). The annual report summarizes major technical accomplishments and progress towards U.S. Department of Energy Building Technologies Program's multi-year goal of developing the systems innovations that enable risk-free, cost effective, reliable and durable efficiency solutions that reduce energy use by 30%-50% in both new and existing homes.

Isotope and Nuclear Chemistry Division annual report, FY 1984

International Nuclear Information System (INIS)

Heiken, J.H.

1985-04-01

This report describes progress in the major research and development programs carried out in FY 1984 by the Isotope and Nuclear Chemistry Division. It covers radiochemical diagnostics of weapons tests; weapons radiochemical diagnostics research and development; other unclassified weapons research; stable and radioactive isotope production, separation, and applications (including biomedical applications); element and isotope transport and fixation; actinide and transition metal chemistry; structural chemistry, spectroscopy, and applications; nuclear structure and reactions; irradiation facilities; advanced analytical techniques: development and applications; atmospheric chemistry and transport; and earth and planetary processes. 287 refs

FY 1996 Congressional budget request: Budget highlights

Energy Technology Data Exchange (ETDEWEB)

1995-02-01

The FY 1996 budget presentation is organized by the Department`s major business lines. An accompanying chart displays the request for new budget authority. The report compares the budget request for FY 1996 with the appropriated FY 1995 funding levels displayed on a comparable basis. The FY 1996 budget represents the first year of a five year plan in which the Department will reduce its spending by $15.8 billion in budget authority and by $14.1 billion in outlays. FY 1996 is a transition year as the Department embarks on its multiyear effort to do more with less. The Budget Highlights are presented by business line; however, the fifth business line, Economic Productivity, which is described in the Policy Overview section, cuts across multiple organizational missions, funding levels and activities and is therefore included in the discussion of the other four business lines.

Annual Status Report (FY2013 Composite Analysis of Low Level Waste Disposal in the Central Plateau at the Hanford Site

Energy Technology Data Exchange (ETDEWEB)

Nichols, W. E. [CH2M HILL Plateau Remediation Company, Richland, WA (United States)

2014-03-25

In accordance with U.S. Department of Energy (DOE) requirements in DOE O 435.1, 3 Chg. 11, and as implemented by DOE/RL-2000-29, Rev. 22, the DOE Richland Operations 4 Office (DOE-RL) has prepared this annual summary of the Hanford Site Composite Analysis 5 for fiscal year (FY) 2013.

Study on the background information for the geological disposal concept

International Nuclear Information System (INIS)

Matsui, Kazuaki; Murano, Tohru; Hirusawa, Shigenobu; Komoto, Harumi

2000-03-01

Japan Nuclear Cycle Development Institute (JNC) has published first R and D report in 1992, in which the fruits of the R and D work were compiled. Since then, JNC, has been promoting the second R and D progress report until before 2000, in which the background information on the geological disposal of high level radioactive waste (HLW) was to be presented as well as the technical basis. Recognizing the importance of the social consensus to the geological disposal, understanding and consensus by the society are essential to the development and realization of the geological disposal of HLW. In this fiscal year, studies were divided into 2 phases, considering the time schedule of the second R and D progress report. 1. Phase 1: Analysis of the background information on the geological disposal concept. Based on the recent informations and the research works of last 2 years, final version of the study was made to contribute to the background informations for the second R and D progress report. (This was published in Nov. 1999 as the intermediate report: JNC TJ 1420 2000-006). 2. Phase 2: Following 2 specific items were selected for the candidate issues which need to be studied, considering the present circumstances around the R and D of geological disposal. (1) Educational materials and strategies related to nuclear energy and nuclear waste. Specific strategies and approaches in the area of nuclear energy and nuclear waste educational outreach and curriculum activities by the nuclear industry, government and other entities in 6 countries were surveyed and summarized. (2) Alternatives to geological disposal of HLW: Past national/international consideration and current status. The alternatives for the disposal of HLW have been discussed in the past and the major waste-producing countries have almost all chosen deep geological disposal as preferred method. Here past histories and recent discussions on the variations to geological disposal were studied. (author)

Idaho National Laboratory’s FY14 Greenhouse Gas Report

Energy Technology Data Exchange (ETDEWEB)

Frerichs, Kimberly Irene [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2015-03-01

A greenhouse gas (GHG) inventory is a systematic approach to account for the production and release of certain gases generated by an institution from various emission sources. The gases of interest are those that climate science has identified as related to anthropogenic global climate change. This document presents an inventory of GHGs generated during Fiscal Year (FY) 2014 by Idaho National Laboratory (INL), a Department of Energy (DOE) sponsored entity, located in southeastern Idaho. In recent years, concern has grown about the environmental impact of GHGs. This, together with a desire to decrease harmful environmental impacts, would be enough to encourage the calculation of an inventory of the total GHGs generated at INL. Additionally, INL has a desire to see how its emissions compare with similar institutions, including other DOE national laboratories. Executive Order 13514 requires that federal agencies and institutions document reductions in GHG emissions. INL’s GHG inventory was calculated according to methodologies identified in federal GHG guidance documents using operational control boundaries. It measures emissions generated in three scopes: (1) INL emissions produced directly by stationary or mobile combustion and by fugitive emissions, (2) the share of emissions generated by entities from which INL purchased electrical power, and (3) indirect or shared emissions generated by outsourced activities that benefit INL (occur outside INL’s organizational boundaries, but are a consequence of INL’s activities). This inventory found that INL generated 73,521 metric tons (MT) of CO2 equivalent (CO2e ) emissions during FY14. The following conclusions were made from looking at the results of the individual contributors to INL’s FY14 GHG inventory: • Electricity (including the associated transmission and distribution losses) is the largest contributor to INL’s GHG inventory, with over 50% of the CO2e emissions • Other sources with high emissions were

Idaho National Laboratory’s Greenhouse Gas FY08 Baseline

Energy Technology Data Exchange (ETDEWEB)

Jennifer D. Morton

2011-06-01

A greenhouse gas (GHG) inventory is a systematic attempt to account for the production and release of certain gasses generated by an institution from various emission sources. The gasses of interest are those which have become identified by climate science as related to anthropogenic global climate change. This document presents an inventory of GHGs generated during fiscal year (FY) 2008 by Idaho National Laboratory (INL), a Department of Energy (DOE)-sponsored entity, located in southeastern Idaho. Concern about the environmental impact of GHGs has grown in recent years. This, together with a desire to decrease harmful environmental impacts, would be enough to encourage the calculation of a baseline estimate of total GHGs generated at INL. Additionally, INL has a desire to see how its emissions compare with similar institutions, including other DOE national laboratories. Executive Order 13514 requires that federal agencies and institutions document reductions in GHG emissions in the future, and such documentation will require knowledge of a baseline against which reductions can be measured. INL's FY08 GHG inventory was calculated according to methodologies identified in federal GHG guidance documents using operational control boundaries. It measures emissions generated in three Scopes: (1) INL emissions produced directly by stationary or mobile combustion and by fugitive emissions, (2) the share of emissions generated by entities from which INL purchased electrical power, and (3) indirect or shared emissions generated by outsourced activities that benefit INL (occur outside INL's organizational boundaries but are a consequence of INL's activities). This inventory found that INL generated a total of 113,049 MT of CO2-equivalent emissions during FY08. The following conclusions were made from looking at the results of the individual contributors to INL's baseline GHG inventory: (1) Electricity (including the associated transmission and

FY 1997 cost savings report

International Nuclear Information System (INIS)

Sellards, J.B.

1998-01-01

With the end of the cold war, funding for the Environmental Management program increased rapidly as nuclear weapons production facilities were shut down, cleanup responsibilities increased, and facilities were transferred to the cleanup program. As funding for the Environmental Management (EM) program began to level off in response to Administration and Congressional efforts to balance the Federal budget, the program redoubled its efforts to increase efficiency and get more productivity out of every dollar. Cost savings and enhanced performance are an integral pair of Hanford Site operations. FY1997 was the third year of a cost savings program that was initially defined in FY 1995. The definitions and process remained virtually the same as those used in FY 1996

Photovoltaic Subcontract Program, FY 1991. Annual report, [October 1, 1990--September 30, 1991

Energy Technology Data Exchange (ETDEWEB)

1992-03-01

This report summarizes the fiscal year (FY) 1991 (October 1, 1990, through September 30, 1991) progress of the subcontracted photovoltaic (PV) research and development (R&D) performed under the Photovoltaic Advanced Research and Development Project at the National Renewable Energy Laboratory (NREL) -- formerly the Solar Energy Research Institute (SERI). The mission of the national PV program is to develop PV technology for large-scale generation of economically competitive electric power in the United States. The technical sections of the report cover the main areas of the subcontract program: the Amorphous Silicon Research Project, Polycrystalline Thin Films, Crystalline Silicon Materials Research, High-Efficiency Concepts, the New Ideas Program, the University Participation Program, and the Photovoltaic Manufacturing Technology (PVMaT) project. Technical summaries of each of the subcontracted programs provide a discussion of approaches, major accomplishments in FY 1991, and future research directions.

Annual Report: Photovoltaic Subcontract Program FY 1990

Energy Technology Data Exchange (ETDEWEB)

Summers, K. A. [Solar Energy Research Inst., Golden, CO (United States)

1991-03-01

This report summarizes the progress of the Photovoltaic (PV) Subcontract Program of the Solar Energy Research Institute (SERI) from October 1, 1989 through September 30, 1990. The PV Subcontract Program is responsible for managing the subcontracted portion of SERI's PV Advanced Research and Development Project. In fiscal year 1990, this included more than 54 subcontracts with a total annualized funding of approximately $11.9 million. Approximately two-thirds of the subcontracts were with universities at a total funding of nearly $3.3 million. The six technical sections of the report cover the main areas of the subcontract program: the Amorphous Silicon Research Project, Polycrystalline Thin Films, Crystalline Silicon Materials Research, High-Efficiency Concepts, the New Ideas Program, and the University Participation Program. Technical summaries of each of the subcontracted programs provide a discussion of approaches, major accomplishments in FY 1990, and future research directions. Another section introduces the PVMaT project and reports on its progress.

FY 2017 Stockpile Stewardship and Management Plan - Biennial Plan Summary

Energy Technology Data Exchange (ETDEWEB)

None, None

2016-03-01

This year’s summary report updates the Fiscal Year 2016 Stockpile Stewardship and Management Plan (FY 2016 SSMP), the 25-year strategic program of record that captures the plans developed across numerous NNSA programs and organizations to maintain and modernize the scientific tools, capabilities, and infrastructure necessary to ensure the success of NNSA’s nuclear weapons mission. The SSMP is a companion to the Prevent, Counter, and Respond: A Strategic Plan to Reduce Global Nuclear Threats (FY 2017-2021) report, the planning document for NNSA’s nuclear threat reduction mission. New versions of both reports are published each year in response to new requirements and challenges. Much was accomplished in FY 2015 as part of the program of record described in this year’s SSMP. The science-based Stockpile Stewardship Program allowed the Secretaries of Energy and Defense to certify for the twentieth time that the stockpile remains safe, secure, and effective without the need for underground nuclear explosive testing. The talented scientists, engineers, and technicians at the three national security laboratories, the four nuclear weapons production plants, and the national security site are primarily responsible for this continued success. Research, development, test, and evaluation programs have advanced NNSA’s understanding of weapons physics, component aging, and material properties through first-of-a-kind shock physics experiments, along with numerous other critical experiments conducted throughout the nuclear security enterprise. The multiple life extension programs (LEPs) that are under way made progress toward their first production unit dates. The W76-1 LEP is past the halfway point in total production, and the B61-12 completed three development flight tests. Critical to this success is the budget. The Administration’s budget request for NNSA’s Weapons Activities has increased for all but one of the past seven years, resulting in a total increase of

Wastewater Disposal Wells, Fracking, and Environmental Injustice in Southern Texas.

Science.gov (United States)

Johnston, Jill E; Werder, Emily; Sebastian, Daniel

2016-03-01

To investigate race and poverty in areas where oil and gas wastewater disposal wells, which are used to permanently inject wastewater from hydraulic fracturing (fracking) operations, are permitted. With location data of oil and gas disposal wells permitted between 2007 and 2014 in the Eagle Ford area, a region of intensive fracking in southern Texas, we analyzed the racial composition of residents living less than 5 kilometers from a disposal well and those farther away, adjusting for rurality and poverty, using a Poisson regression. The proportion of people of color living less than 5 kilometers from a disposal well was 1.3 times higher than was the proportion of non-Hispanic Whites. Adjusting for rurality, disposal wells were 2.04 times (95% confidence interval = 2.02, 2.06) as common in areas with 80% people of color or more than in majority White areas. Disposal wells are also disproportionately sited in high-poverty areas. Wastewater disposal wells in southern Texas are disproportionately permitted in areas with higher proportions of people of color and residents living in poverty, a pattern known as "environmental injustice."

FY2010 ANNUAL REVIEW E-AREA LOW-LEVEL WASTE FACILITY PERFORMANCE ASSESSMENT AND COMPOSITE ANALYSIS

Energy Technology Data Exchange (ETDEWEB)

Butcher, T.; Swingle, R.; Crapse, K.; Millings, M.; Sink, D.

2011-01-01

The E-Area Low-Level Waste Facility (ELLWF) consists of a number of disposal units described in the Performance Assessment (PA)(WSRC, 2008b) and Composite Analysis (CA)(WSRC, 1997; WSRC, 1999): Low-Activity Waste (LAW) Vault, Intermediate Level (IL) Vault, Trenches (Slit Trenches [STs], Engineered Trenches [ETs], and Component-in-Grout [CIG] Trenches), and Naval Reactor Component Disposal Areas (NRCDAs). This annual review evaluates the adequacy of the approved 2008 ELLWF PA along with the Special Analyses (SAs) approved since the PA was issued. The review also verifies that the Fiscal Year (FY) 2010 low-level waste (LLW) disposal operations were conducted within the bounds of the PA/SA baseline, the Savannah River Site (SRS) CA, and the Department of Energy (DOE) Disposal Authorization Statement (DAS). Important factors considered in this review include waste receipts, results from monitoring and research and development (R&D) programs, and the adequacy of controls derived from the PA/SA baseline. Sections 1.0 and 2.0 of this review are a summary of the adequacy of the PA/SA and CA, respectively. An evaluation of the FY2010 waste receipts and the resultant impact on the ELLWF is summarized in Section 3.1. The results of the monitoring program, R&D program, and other relevant factors are found in Section 3.2, 3.3 and 3.4, respectively. Section 4.0 contains the CA annual determination similarly organized. SRS low-level waste management is regulated under DOE Order 435.1 (DOE, 1999a) and is authorized under a DAS as a federal permit. The original DAS was issued by the DOE-Headquarters (DOE-HQ) on September 28, 1999 (DOE, 1999b) for the operation of the ELLWF and the Saltstone Disposal Facility (SDF). The 1999 DAS remains in effect for the regulation of the SDF. Those portions of that DAS applicable to the ELLWF were superseded by revision 1 of the DAS on July 15, 2008 (DOE, 2008b). The 2008 PA and DAS were officially implemented by the facility on October 31, 2008

Geological disposal concept hearings

International Nuclear Information System (INIS)

1996-01-01

The article outlines the progress to date on AECL spent-nuclear fuel geological disposal concept. Hearings for discussion, organised by the federal Environmental Assessment Review Panel, of issues related to this type of disposal method occur in three phases, phase I focuses on broad societal issues related to long term management of nuclear fuel waste; phase II will focus on the technical aspects of this method of disposal; and phase III will consist of community visits in New Brunswick, Quebec, Ontario, Manitoba and Saskatchewan. This article provides the events surrounding the first two weeks of phase I hearings (extracted from UNECAN NEWS). In the first week of hearings, where submissions on general societal issues was the focus, there were 50 presentations including those by Natural Resources Canada, Energy Probe, Ontario Hydro, AECL, Canadian Nuclear Society, Aboriginal groups, environmental activist organizations (Northwatch, Saskatchewan Environmental Society, the Inter-Church Uranium Committee, and the Canadian Coalition for Nuclear responsibility). In the second week of hearings there was 33 presentations in which issues related to siting and implementation of a disposal facility was the focus. Phase II hearings dates are June 10-14, 17-21 and 27-28 in Toronto

Hydrologic resources management program. FY 1995 progress report

International Nuclear Information System (INIS)

Smith, D.K.; Esser, B.K.; Kenneally, J.M.

1996-03-01

This report presents the results of FY 1995 technical studies conducted by the Lawrence Livermore National Laboratory (LLNL) as part of the Hydrology and Radionuclide Migration Program (HRMP), a multi-agency program sponsored by the U.S. Department of Energy, Nevada Operations Office (DOE/NV), to address the environmental consequences of nuclear weapons testing at the Nevada Test Site (NTS). A priority is to better characterize the complex near-field environment in order to assess and predict the movement of radionuclides in groundwater. Other participating organizations include the Los Alamos National Laboratory (LANL), the U.S. Geological Survey (USGS) and the Desert Research Institute (DRI) of the University of Nevada. A radiologic source term in excess of 10 8 curies of tritium, fission products, activation products and actinides is residual from more than three decades of underground nuclear weapons testing at the Nevada Test Site (NTS). Burial depths to insure containment of these explosions necessitated firing approximately one third of the more than 800 underground nuclear tests within one cavity radius or below the static water table. Work at LLNL has focused on studies of radionuclide transport under saturated, partially saturated or unsaturated conditions as well as investigations of the stable, radiogenic and cosmogenic isotope systematics of NTS groundwaters. LLNL has prioritized these studies because of the significance for potential radionuclide migration at the Nevada Test Site. LLNL utilizes expertise in nuclear weapons testing, radiochemical diagnostics, nuclear test phenomenology, mass spectrometry, aqueous geochemistry and field and laboratory studies of radionuclide migration to bring a unique measurement and interpretative capability to this research

Tanks Focus Area (TFA) FY1999 Midyear Review Report

International Nuclear Information System (INIS)

Schlahta, Stephan N.

1999-01-01

The purpose of the Tanks Focus Area (TFA) Midyear Review was to improve the quality and responsiveness of TFA technical solutions to identified user needs. This review goal was achieved through executing a multi-phased review approach. The first phase of the midyear review focused on the subset of FY99 work identified by Department of energy users as having continuing benefit in FY00-01. The TFA FY00-02 Technical Responses identified FY99 work that had continued applicability based on the most current set of site user needs. Each TFA FY00-02 Technical Response which included FY work scope was reviewed by the TFA Technical Advisory Group (TAG), in a meeting held in February 1999. Made up of technical experts from across the country, the TAG provides high-quality, short-turnaround, independent technical reviews for the TFA

FY 1991 report on the Coal Gasification Committee; 1991 nendo sekitan gasuka iinkai hokokusho

Energy Technology Data Exchange (ETDEWEB)

NONE

1992-03-01

The paper reported activities of the Coal Gasification Committee, gasification power generation section and gasification technology section in FY 1991. The 1st Coal Gasification Committee Meeting was held on July 16,1991, and report/discussion were made about an outline of the FY 1991 research plan on the development of coal gasification technology. The 2nd Meeting was held on March 12, 1992, and report/discussion were made about activities of each section meeting and the progress of the development of coal gasification technology. In the section meeting of coal gasification power generation, report/discussion were made about the progress and study object of the development of entrained bed coal gasification power plant and support study for the development of the plant. In the 1st section meeting of coal gasification technology, as to the developmental plan on coal utilization hydrogen production technology, report/discussion were made about design/construction/operational study of pilot plant and support study for pilot plant (study using small equipment, study of trial manufacture of plant use equipment/materials). In the 2nd section meeting, report/discussion were made about the results of the development of coal utilization hydrogen production technology. (NEDO)

Disposal of fly ash

International Nuclear Information System (INIS)

Singh, B.; Foley, C.

1991-01-01

Theoretical arguments and pilot plant results have shown that the transport of fly-furnace ash from the power station to the disposal area as a high concentration slurry is technically viable and economically attractive. Further, lack of free water, when transported as a high concentration slurry, offers significant advantages in environmental management and rehabilitation of the disposal site. This paper gives a basis for the above observations and discusses the plans to exploit the above advantages at the Stanwell Power Station. (4 x 350 MWe). This will be operated by the Queensland Electricity Commission. The first unit is to come into operation in 1992 and other units are to follow progressively on a yearly basis

Performance-assessment progress for the Rozan low-level waste disposal facility

Energy Technology Data Exchange (ETDEWEB)

Smietanski, L.; Mitrega, J.; Frankowski, Z. [Polish Geological Institute, Warsaw (Poland)] [and others

1995-12-31

The paper presents a condensed progress report on the performance assessment of Poland`s low-level waste disposal facility which is operating since 1961. The Rozan repository is of near-surface type with facilities which are the concrete fortifications built about 1910. Site characterization activities supplied information on regional geology, geohydrology, climatic and hydrologic conditions and terrain surface evolution due to geodynamic processes. Field surveys enabled to decode lithological, hydrogeological and geochemical site specific conditions. From the laboratory tests the data on groundwater chemistry and soil geochemical and hydraulic characteristics were obtained. The site geohydrologic main vulnerable element is the upmost directly endangered unconfined aquifer which is perched in relation to the region-wide hydraulic system. Heterogeneity of this system reflects in a wide range of hydraulic conductivity and thickness variations. It strongly affects velocity and flow directions. The chemistry of groundwater is unstable due to large sensitivity to external impacts. Modeling of the migration of the critical long-lived radionuclides Tc-99, U-238 and Pu-239 showed that the nearly 20 m thick unsaturated zone plays crucial role as an effective protective barrier. These radionuclides constitute minor part of the total inventory. Modeling of the development of the H-3 plume pointed out the role the macrodispersion plays in the unsaturated zone beneath the repository.

MFTF-α + T progress report

International Nuclear Information System (INIS)

Nelson, W.D.

1985-04-01

Early in FY 1983, several upgrades of the Mirror Fusion Test Facility (MFTF-B) at Lawrence Livermore National Laboratory (LLNL) were proposed to the fusion community. The one most favorably received was designated MFTF-α+T. The engineering design of this device, guided by LLNL, has been a principal activity of the Fusion Engineering Design Center during FY 1983. This interim progress report represents a snapshot of the device design, which was begun in FY 1983 and will continue for several years. The report is organized as a complete design description. Because it is an interim report, some parts are incomplete; they will be supplied as the design study proceeds. As described in this report, MFTF-α+T uses existing facilities, many MFTF-B components, and a number of innovations to improve on the physics parameters of MFTF-B. It burns deuterium-tritium and has a central-cell Q of 2, a wall loading GAMMA/sub n/ of 2 MW/m 2 (with a central-cell insert module), and an availability of 10%. The machine is fully shielded, allows hands-on maintenance of components outside the vacuum vessel 24 h after shutdown, and has provisions for repair of all operating components

Optimizing Federal Fleet Vehicle Acquisitions: An Eleven-Agency FY 2012 Analysis

Energy Technology Data Exchange (ETDEWEB)

Singer, M. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Daley, R. [National Renewable Energy Lab. (NREL), Golden, CO (United States)

2015-02-01

This report focuses on the National Renewable Energy Laboratory's (NREL) fiscal year (FY) 2012 effort that used the NREL Optimal Vehicle Acquisition (NOVA) analysis to identify optimal vehicle acquisition recommendations for eleven diverse federal agencies. Results of the study show that by following a vehicle acquisition plan that maximizes the reduction in greenhouse gas (GHG) emissions, significant progress is also made toward the mandated complementary goals of acquiring alternative fuel vehicles, petroleum use reduction, and alternative fuel use increase.

Projected Benefits of Federal Energy Efficiency and Renewable Energy Programs. FY 2005 - FY 2050

Energy Technology Data Exchange (ETDEWEB)

None, None

2004-05-01

This report describes a benefits analysis undertaken by EERE to better understand the extent to which the technologies and market improvements funded by its FY 2005 budget request will make energy more affordable, cleaner, and more reliable. It summarizes the results of the analysis, which focused on economic, environmental, and security benefits related to energy. The report identifies specific measures or indicators of estimated benefits for FY 2005.

Results of single borehole hydraulic tests in the Mizunami Underground Research Laboratory project. FY 2012 - FY 2015

International Nuclear Information System (INIS)

Onoe, Hironori; Takeuchi, Ryuji

2016-11-01

This report summarize the results of the single borehole hydraulic tests of 151 sections carried out at the -300 m Stage and the -500 m Stage of the Mizunami Underground Research Laboratory from FY 2012 to FY 2015. The details of each test (test interval depth, geology, etc.) as well as the interpreted hydraulic parameters and analytical methods used are presented in this report. Furthermore, the previous results of the single borehole hydraulic tests carried out in the Regional Hydrogeological Study Project and the Mizunami Underground Research Laboratory Project before FY 2012 are also summarized in this report. (author)

NREL Energy Storage Projects: FY2013 Annual Report

Energy Technology Data Exchange (ETDEWEB)

Pesaran, A.; Ban, C.; Brooker, A.; Gonder, J.; Ireland, J.; Keyser, M.; Kim, G. H.; Long, D.; Neubauer, J.; Santhanagopalan, S.; Smith, K.; Tenent, R.; Wood, E.; Han, T.; Hartridge, S.; Shaffer, C. E.

2014-07-01

In FY13, DOE funded NREL to make technical contributions to various R&D activities. This report summarizes NREL's R&D projects in FY13 in support of the USABC; Battery Testing, Analysis, and Design; ABR; and BATT program elements. The FY13 projects under NREL's Energy Storage R&D program are discussed in depth in this report.

FY 1995 progress report on the ANS thermal-hydraulic test loop operation and results

Energy Technology Data Exchange (ETDEWEB)

Siman-Tov, M.; Felde, D.K.; Farquharson, G.; McDuffee, J.L.; McFee, M.T.; Ruggles, A.E.; Wendel, M.W.; Yoder, G.L.

1997-07-01

The Thermal-Hydraulic Test Loop (THTL) is an experimental facility constructed to support the development of the Advanced Neutron Source Reactor (ANSR) at Oak Ridge National Laboratory (ORNL). The THTL facility was designed and built to provide known thermal-hydraulic (T/H) conditions for a simulated full-length coolant subchannel of the ANS reactor core, thus facilitating experimental determination of FE and CHF thermal limits under expected ANSR T/H conditions. Special consideration was given to allow operation of the system in a stiff mode (constant flow) and in a soft mode (constant pressure drop) for proper implementation of true FE and DNB experiments. The facility is also designed to examine other T/H phenomena, including onset of incipient boiling (IB), single-phase heat transfer coefficients and friction factors, and two-phase heat transfer and pressure drop characteristics. Tests will also be conducted that are representative of decay heat levels at both high pressure and low pressure as well as other quasi-equilibrium conditions encountered during transient scenarios. A total of 22 FE tests and 2 CHF tests were performed during FY 1994 and FY 1995 with water flowing vertically upward. Comparison of these data as well as extensive data from other investigators led to a proposed modification to the Saha and Zuber correlation for onset of significant void (OSV), applied to FE prediction. The modification takes into account a demonstrated dependence of the OSV or FE thermal limits on subcooling levels, especially in the low subcooling regime.

FY 1995 progress report on the ANS thermal-hydraulic test loop operation and results

International Nuclear Information System (INIS)

Siman-Tov, M.; Felde, D.K.; Farquharson, G.; McDuffee, J.L.; McFee, M.T.; Ruggles, A.E.; Wendel, M.W.; Yoder, G.L.

1997-07-01

The Thermal-Hydraulic Test Loop (THTL) is an experimental facility constructed to support the development of the Advanced Neutron Source Reactor (ANSR) at Oak Ridge National Laboratory (ORNL). The THTL facility was designed and built to provide known thermal-hydraulic (T/H) conditions for a simulated full-length coolant subchannel of the ANS reactor core, thus facilitating experimental determination of FE and CHF thermal limits under expected ANSR T/H conditions. Special consideration was given to allow operation of the system in a stiff mode (constant flow) and in a soft mode (constant pressure drop) for proper implementation of true FE and DNB experiments. The facility is also designed to examine other T/H phenomena, including onset of incipient boiling (IB), single-phase heat transfer coefficients and friction factors, and two-phase heat transfer and pressure drop characteristics. Tests will also be conducted that are representative of decay heat levels at both high pressure and low pressure as well as other quasi-equilibrium conditions encountered during transient scenarios. A total of 22 FE tests and 2 CHF tests were performed during FY 1994 and FY 1995 with water flowing vertically upward. Comparison of these data as well as extensive data from other investigators led to a proposed modification to the Saha and Zuber correlation for onset of significant void (OSV), applied to FE prediction. The modification takes into account a demonstrated dependence of the OSV or FE thermal limits on subcooling levels, especially in the low subcooling regime

Development of low-level radioactive waste disposal capacity in the United States - progress or stalemate?

International Nuclear Information System (INIS)

Devgun, J.S.; Larson, G.S.

1995-01-01

It has been fifteen years since responsibility for the disposal of commercially generated low-level radioactive waste (LLW) was shifted to the states by the United States Congress through the Low-Level Radioactive Waste Policy Act of 1980 (LLRWPA). In December 1985, Congress revisited the issue and enacted the Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA). No new disposal sites have opened yet, however, and it is now evident that disposal facility development is more complex, time-consuming, and controversial than originally anticipated. For a nation with a large nuclear power industry, the lack of availability of LLW disposal capacity coupled with a similar lack of high-level radioactive waste disposal capacity could adversely affect the future viability of the nuclear energy option. The U.S. nuclear power industry, with 109 operating reactors, generates about half of the LLW shipped to commercial disposal sites and faces dwindling access to waste disposal sites and escalating waste management costs. The other producers of LLW - industries, government (except the defense related research and production waste), academic institutions, and medical institutions that account for the remaining half of the commercial LLW - face the same storage and cost uncertainties. This paper will summarize the current status of U.S. low-level radioactive waste generation and the status of new disposal facility development efforts by the states. The paper will also examine the factors that have contributed to delays, the most frequently suggested alternatives, and the likelihood of change

Development of low-level radioactive waste disposal capacity in the United States -- Progress or stalemate?

International Nuclear Information System (INIS)

Devgun, J.S.

1995-01-01

It has been fifteen years since responsibility for the disposal of commercially generated low-level radioactive waste (LLW) was shifted to the states by the United States Congress through the Low-Level Radioactive Waste Policy Act of 1980 (LLRWPA). In December 1985, Congress revisited the issue and enacted the Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA). No new disposal sites have opened yet, however, and it is now evident that disposal facility development is more complex, time-consuming, and controversial than originally anticipated. For a nation with a large nuclear power industry, the lack of availability of LLW disposal capacity coupled with a similar lack of high-level radioactive waste disposal capacity could adversely affect the future viability of the nuclear energy option. The US nuclear power industry, with 109 operating reactors, generates about half of the LLW shipped to commercial disposal sites and faces dwindling access to waste disposal sites and escalating waste management costs. The other producers of LLW -- industries, government (except the defense related research and production waste), academic institutions, and medical institutions that account for the remaining half of the commercial LLW -- face the same storage and cost uncertainties. This paper will summarize the current status of US low-level radioactive waste generation and the status of new disposal facility development efforts by the states. The paper will also examine the factors that have contributed to delays, the most frequently suggested alternatives, and the likelihood of change

Analytical Chemistry Laboratory Progress Report for FY 1994

Energy Technology Data Exchange (ETDEWEB)

Green, D.W.; Boparai, A.S.; Bowers, D.L. [and others

1994-12-01

The purpose of this report is to summarize the activities of the Analytical Chemistry Laboratory (ACL) at Argonne National Laboratory (ANL) for Fiscal Year (FY) 1994 (October 1993 through September 1994). This annual report is the eleventh for the ACL and describes continuing effort on projects, work on new projects, and contributions of the ACL staff to various programs at ANL. The Analytical Chemistry Laboratory is a full-cost-recovery service center, with the primary mission of providing a broad range of analytical chemistry support services to the scientific and engineering programs at ANL. The ACL also has a research program in analytical chemistry, conducts instrumental and methods development, and provides analytical services for governmental, educational, and industrial organizations. The ACL handles a wide range of analytical problems. Some routine or standard analyses are done, but it is common for the Argonne programs to generate unique problems that require significant development of methods and adaption of techniques to obtain useful analytical data. The ACL has four technical groups -- Chemical Analysis, Instrumental Analysis, Organic Analysis, and Environmental Analysis -- which together include about 45 technical staff members. Talents and interests of staff members cross the group lines, as do many projects within the ACL. The Chemical Analysis Group uses wet- chemical and instrumental methods for elemental, compositional, and isotopic determinations in solid, liquid, and gaseous samples and provides specialized analytical services. Major instruments in this group include an ion chromatograph (IC), an inductively coupled plasma/atomic emission spectrometer (ICP/AES), spectrophotometers, mass spectrometers (including gas-analysis and thermal-ionization mass spectrometers), emission spectrographs, autotitrators, sulfur and carbon determinators, and a kinetic phosphorescence uranium analyzer.

Conceptual design report for environmental, safety and health phase III FY-91 line item

Energy Technology Data Exchange (ETDEWEB)

NONE

1988-09-01

The Mound Facility (Mound), located in Miamisburg, Ohio, is a Department of Energy (DOE) development and production facility performing support work for DOE`s weapons and energy-related programs. EG&G Mound Applied Technologies (EG&G) is the Operating Contractor (OC) for this Government-Owned, Contractor-Operated (GOCO) facility. The work performed at Mound emphasizes nuclear energy and explosives technology. Mound is currently implementing an Environmental, Safety, and Health (ES&H) Program designed to protect its employees, the public, and the environment from adverse effects caused by the facility`s activities. Design has been completed, and construction is in progress for Phase I of this multiphase program. Phase II has been submitted for fiscal year (FY) 89 funding and Phase IV is being submitted as an FY 92 line item. This Conceptual Design Report (CDR) addresses Phase III of the ES&H program.

Electrochemical Destruction of Nitrates and Organics FY1995 Progress Report

International Nuclear Information System (INIS)

Hobbs, D.T.

1995-01-01

Production of nuclear materials within the DOE complex has yielded large volumes of high-level waste containing hazardous species such as nitrate, nitrite, chromium, and mercury. Processes being developed for the permanent disposal of these wastes are aimed at separating the bulk of the radioactivity, primarily 137-Cs and 90-Sr, into a small volume for incorporation into a vitrified wasteform, with the remainder being incorporated into a low-level wasteform

Summary of NREL's FY13-FY15 Photovoltaic Subprogram

Energy Technology Data Exchange (ETDEWEB)

2017-03-31

In this report, you will find summaries of the completed FY13-FY15 Photovoltaic projects that were funded within NREL. The summaries describe the initial motivation for the project; significant achievements, including publications, intellectual property, and collaborations; and remaining challenges. Among the NREL projects, you will find research of almost every major PV technology - from the next generation of silicon PV to relatively new organic PVs - as well as projects advancing PV module durability and characterization. Each of these projects was designed to support SunShot's goals, putting the United States one step closer to widespread use of low-cost, clean electricity.

Energy Division progress report, fiscal years 1994--1995

Energy Technology Data Exchange (ETDEWEB)

Moser, C.I. [ed.

1996-06-01

At ORNL, the Energy Division`s mission is to provide innovative solutions to energy and related issues of national and global importance through interdisciplinary research and development. Its goals and accomplishments are described in this progress report for FY 1994 and FY 1995. The Division`s expenditures in FY 1995 totaled 44.9 million. Sixty percent of the divisions work was supported by the US DOE. Other significant sponsors include the US DOT, the US DOD, other federal agencies, and some private organizations. The Division`s programmatic activities cover three main areas: (1) analysis and assessment, (2) transportation systems, and (3) energy use and delivery technologies. Analysis and assessment activities involve energy and resource analysis, preparation of environmental assessments and impact statements, and impact statements, research on emergency preparedness, analysis of energy and environmental needs in developing countries, and transportation analysis. Transportation systems research seeks to improve the quality of both civilian and military transportation efforts. Energy use and delivery technologies focus on building equipment, building envelopes, (walls, roofs, attics, and materials), improvement of energy efficiency in buildings, and electric power systems.

FY94 site characterization and multilevel well installation at a west Bear Creek Valley research site on the Oak Ridge Reservation

International Nuclear Information System (INIS)

Moline, G.R.; Schreiber, M.E.

1996-03-01

The goals of this project are to collect data that will assist in determining what constitutes a representative groundwater sample in fractured shale typical of much of the geology underlying the ORR waste disposal sites, and to determine how monitoring-well construction and sampling methods impact the representativeness of the sample. This report details the FY94 field activities at a research site in west Bear Creek Valley on the Oak Ridge Reservation (ORR). These activities funded by the Energy Systems Groundwater Program Office through the Oak Ridge Reservation Hydrologic and Geologic Studies (ORRHAGS) task, focus on developing appropriate sampling protocols for the type of fractured media that underlies many of the ORR waste disposal sites. Currently accepted protocols were developed for porous media and are likely to result in nonrepresentative samples in fractured systems

EST Table: FY036659 [KAIKOcDNA[Archive

Lifescience Database Archive (English)

Full Text Available FY036659 rbmte13c09 11/12/09 GO hit GO:0047800(cysteamine dioxygenase activity)|GO:...f|XP_974899.1| PREDICTED: similar to 2-aminoethanethiol (cysteamine) dioxygenase [Tribolium castaneum] FY036659 bmte ...

Krypton-85 disposal program. Semiannual report, August 15, 1977--March 31, 1978

International Nuclear Information System (INIS)

Klett, R.D.

1979-02-01

The first 7.5 months of the Krypton-85 disposal program are summarized. Included are task definitions and initial progress in geologic disposal system studies, SURF compatibility, augmented heat dissipation, material qualification, exterior canister compatibility, ceramic liners for canisters, and geologic transport. Feasibility studies indicate that Kr-85 can be disposed of at SURF facility or in near-surface geologic repositories

Discrete Fracture Network Modeling and Simulation of Subsurface Transport for the Topopah Springs and Lava Flow Aquifers at Pahute Mesa, FY 15 Progress Report

Energy Technology Data Exchange (ETDEWEB)

Makedonska, Nataliia [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Kwicklis, Edward Michael [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Birdsell, Kay Hanson [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Harrod, Jeremy Ashcraft [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Karra, Satish [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-10-18

This progress report for fiscal year 2015 (FY15) describes the development of discrete fracture network (DFN) models for Pahute Mesa. DFN models will be used to upscale parameters for simulations of subsurface flow and transport in fractured media in Pahute Mesa. The research focuses on modeling of groundwater flow and contaminant transport using DFNs generated according to fracture characteristics observed in the Topopah Spring Aquifer (TSA) and the Lava Flow Aquifer (LFA). This work will improve the representation of radionuclide transport processes in large-scale, regulatory-focused models with a view to reduce pessimistic bounding approximations and provide more realistic contaminant boundary calculations that can be used to describe the future extent of contaminated groundwater. Our goal is to refine a modeling approach that can translate parameters to larger-scale models that account for local-scale flow and transport processes, which tend to attenuate migration.

Sustainable NREL - Site Sustainability Plan FY 2015

Energy Technology Data Exchange (ETDEWEB)

None, None

2015-01-01

NREL's Site Sustainability Plan FY 2015 reports on sustainability plans for the lab for the year 2015 based on Executive Order Goals and provides the status on planned actions cited in the FY 2014 report.

Research on geological disposal

International Nuclear Information System (INIS)

Uchida, Masahiro

2011-01-01

The aims of this research are to develop criteria for reviewing acceptability of the adequacy of the result of Preliminary and Detailed Investigations submitted by the implementor, and to establish a basic policy to secure safety for safety review. In FY 2010, 13 geology/climate related events for development of acceptance criteria for reviewing the adequacy of the result of Preliminary and Detailed Investigations were extracted. And the accuracy of geophysical exploration methods necessary for the Preliminary Investigation was evaluated. Regarding the research for safety review, we developed an idea of safety concept of Japanese geological disposal, and analyzed basic safety functions to secure safety. In order to verify the groundwater flow evaluation methods developed in regulatory research, the hydrological and geochemical data at Horonobe, northern Hokkaido were obtained, and simulated result of regional groundwater flow were compared with measured data. And we developed the safety scenario of geology/climate related events categorized by geological and geomorphological properties. Also we created a system to check the quality of research results in Japan and other countries in order to utilize for safety regulation, and developed a database system to compile them. (author)

Environmental management compliance reengineering project, FY 1997 report

International Nuclear Information System (INIS)

VanVliet, J.A.; Davis, J.N.

1997-09-01

Through an integrated reengineering effort, the Idaho National Engineering and Environmental Laboratory (INEEL) is successfully implementing process improvements that will permit safe and compliant operations to continue during the next 5 years, even though $80 million was removed from the Environmental Management (EM) program budget. A 2-year analysis, design, and implementation project will reengineer compliance-related activities and reduce operating costs by approximately $17 million per year from Fiscal Year (FY) 1998 through 2002, while continuing to meet the INEEL''s environment, safety, and health requirements and milestone commitments. Compliance reengineer''s focus is improving processes, not avoiding full compliance with environmental, safety, and health laws. In FY 1997, compliance reengineering used a three-phase approach to analyze, design, and implement the changes that would decrease operating costs. Implementation for seven specific improvement projects was completed in FY 1997, while five projects will complete implementation in FY 1998. During FY 1998, the three-phase process will be repeated to continue reengineering the INEEL

Environmental management compliance reengineering project, FY 1997 report

Energy Technology Data Exchange (ETDEWEB)

VanVliet, J.A.; Davis, J.N.

1997-09-01

Through an integrated reengineering effort, the Idaho National Engineering and Environmental Laboratory (INEEL) is successfully implementing process improvements that will permit safe and compliant operations to continue during the next 5 years, even though $80 million was removed from the Environmental Management (EM) program budget. A 2-year analysis, design, and implementation project will reengineer compliance-related activities and reduce operating costs by approximately $17 million per year from Fiscal Year (FY) 1998 through 2002, while continuing to meet the INEEL`s environment, safety, and health requirements and milestone commitments. Compliance reengineer`s focus is improving processes, not avoiding full compliance with environmental, safety, and health laws. In FY 1997, compliance reengineering used a three-phase approach to analyze, design, and implement the changes that would decrease operating costs. Implementation for seven specific improvement projects was completed in FY 1997, while five projects will complete implementation in FY 1998. During FY 1998, the three-phase process will be repeated to continue reengineering the INEEL.

Building technical and social confidence in the safety of geological disposal in Japan

International Nuclear Information System (INIS)

Tochiyama, Osamu; Masuda, Sumio

2013-01-01

Geological disposal has been adopted as the most feasible option for the method of long-term management of high-level radioactive waste (HLW) in every country in the world, regardless of the pros and cons of the nuclear power generation. Building stakeholders’ confidence in safety of geological disposal is indispensable to reach the point where the implementation of geological disposal is accepted by the current generation. The safety case is a key input to build confidence in geological disposal stepwise as the program progresses and regarded to play an important role as a common platform in the communication among stakeholders. The aim of this paper is to review arguments relevant to building technical and social confidence in the progress of Japanese research and development activities as well as international discussions. (author)

Federal Research and Development Funding: FY2014

Science.gov (United States)

2014-02-19

1.12 billion for FY2014. The FY2014 request proposed $155 million to replace the agency’s Southeast Poultry Disease Research Laboratory in Athens...formula funding, and special grants. 94 U.S. Department of Agriculture, “Statement by Thomas J

Accelerator/Experiment operations - FY 2006

Energy Technology Data Exchange (ETDEWEB)

Brice, S.; Conrad, J.; Denisov, D.; Ginther, G.; Holmes, S.; James, C.; Lee, W.; Louis, W.; Moore, C.; Plunkett, R.; Raja, R.; /Fermilab

2006-10-01

This Technical Memorandum (TM) summarizes the Fermilab accelerator and experiment operations for FY 2006. It is one of a series of annual publications intended to gather information in one place. In this case, the information concerns the FY 2006 Run II at the Tevatron Collider, the MiniBooNE experiments running in the Booster Neutrino Beam in neutrino and antineutrino modes, MINOS using the Main Injector Neutrino Beam (NuMI), and SY 120 activities.

Lawrence Livermore National Laboratory FY 2016 Laboratory Directed Research and Development Annual Report

Energy Technology Data Exchange (ETDEWEB)

Al-Ayat, R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Gard, E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Sketchley, J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Watkins, L. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2017-10-16

The LDRD annual report for FY2016 consists of two parts: The Overview. This section contains a broad description of the LDRD Program, highlights of recent accomplishments and awards, Program statistics, and the LDRD portfolio-management processes. Project Reports. Project reports are submitted by all principal investigators at the end of the fiscal year. The length and depth of the report depends on the project’s lifecycle. For projects that will be continuing the following year, the principal investigator submits a continuing project report, which is a brief update containing descriptions of the goals, scope, motivation, relevance (to DOE/NNSA and Livermore mission areas), and technical progress achieved in FY16, as well as a list of selected publications and presentations that resulted from the research. For projects that concluded in FY16, a more detailed final report is provided that is technical in nature and includes the background, objectives, scientific approach, accomplishments, and impacts on the Laboratory missions, as well as a list of publications and presentations that resulted from the research. Project reports are listed under their research topics and organized by year and type, such as exploratory research (ER), feasibility study (FS), laboratory-wide competition (LW), and strategic initiative (SI). Each project is assigned a unique tracking code, an identifier that consists of three elements. The first is the fiscal year in which the project began, the second represents the project type, and the third identifies the serial number of the project for that fiscal year. For example, 16-ERD-100 means the project is an exploratory research project that began in FY16. The three-digit number (100) represents the serial number for the project.

Radiation transport: Progress report, July 1, 1987-September 30, 1987

International Nuclear Information System (INIS)

O'Dell, R.D.; Nagy, A.

1988-05-01

Research and development progress in radiation transport for the Los Alamos National Laboratory's Group S-6 for the fourth quarter of FY 87 is reported. Included are unclassified tasks in the areas of Deterministic Radiation Transport, Monte Carlo Radiation Transport, and Cross Sections and Physics. 23 refs., 9 figs

FY 1991 report on the bituminous coal liquefaction section; 1991 nendo rekiseitan ekikabukai hokokusho

Energy Technology Data Exchange (ETDEWEB)

NONE

1992-03-01

The paper reported activities of the bituminous coal liquefaction section in FY 1991. In the 1st bituminous coal liquefaction section meeting, report/discussion were made on the outline of the plan on the FY 1991 research using pilot plant and the support study of pilot plant. In the 2nd section meeting, report was made on 'How the development of coal liquefaction technology should be in the 21st century,' a report made by the joint section of bituminous coal/brown coal liquefaction. In the 3rd section meeting, report/discussion were made on the state of progress of the FY 1991 R and D and results. In the study using the bituminous coal liquefaction pilot plant, report was made on the outline of construction of a 150t/d pilot plant, study on the acquisition of material balance, analytical study of the data on liquefaction tower, testing survey on properties of coal slurry, and testing survey on slurry preheating furnace. In the support study of pilot plant, report was made on the study using 1t/d PUS, study on the development of the optimum coal refining technology and improvement in the distillate distribution, study of conditions for coal liquefaction and study of solvent hydrogenation catalyst. (NEDO)

MFTF-. cap alpha. + T progress report

Energy Technology Data Exchange (ETDEWEB)

Nelson, W.D. (ed.)

1985-04-01

Early in FY 1983, several upgrades of the Mirror Fusion Test Facility (MFTF-B) at Lawrence Livermore National Laboratory (LLNL) were proposed to the fusion community. The one most favorably received was designated MFTF-..cap alpha..+T. The engineering design of this device, guided by LLNL, has been a principal activity of the Fusion Engineering Design Center during FY 1983. This interim progress report represents a snapshot of the device design, which was begun in FY 1983 and will continue for several years. The report is organized as a complete design description. Because it is an interim report, some parts are incomplete; they will be supplied as the design study proceeds. As described in this report, MFTF-..cap alpha..+T uses existing facilities, many MFTF-B components, and a number of innovations to improve on the physics parameters of MFTF-B. It burns deuterium-tritium and has a central-cell Q of 2, a wall loading GAMMA/sub n/ of 2 MW/m/sup 2/ (with a central-cell insert module), and an availability of 10%. The machine is fully shielded, allows hands-on maintenance of components outside the vacuum vessel 24 h after shutdown, and has provisions for repair of all operating components.

Progressive Tinnitus Management Level 3 Skills Education: A 5-Year Clinical Retrospective.

Science.gov (United States)

Edmonds, Catherine M; Ribbe, Cheri; Thielman, Emily J; Henry, James A

2017-09-18

The primary purpose of this study was to determine whether progressive tinnitus management Level 3 skills education workshops conducted at the Bay Pines and Boston Veterans Affairs hospitals result in consistent use of the presented tinnitus management strategies by patients 1-5 years after completing the workshops. In fiscal year (FY) 2015, the tinnitus workshop follow-up form was mailed to all veterans who completed the Level 3 workshops between FY 2010 and FY 2014. Data were compiled to determine which, if any, of the skills taught in the workshops were being used 1-5 years after completion of the workshops and the impact on quality-of-life indicators. All self-management skills were being utilized up to 5 years postcompletion; therapeutic sound was utilized the most. The majority of patients reported an improved ability to manage reactions to tinnitus and improved quality-of-life indicators. Over 90% of patients from both sites recommended the program to others with tinnitus. The self-management skills taught in the progressive tinnitus management Level 3 workshops are sustained over time even when limited resources prevent the full complement of workshops or the involvement of mental health services. The workshops can also be successfully implemented through remote delivery via videoconferencing (telehealth). https://doi.org/10.23641/asha.5370883.

GASIFICATION TEST RUN TC06

Energy Technology Data Exchange (ETDEWEB)

Southern Company Services, Inc.

2003-08-01

This report discusses test campaign TC06 of the Kellogg Brown & Root, Inc. (KBR) Transport Reactor train with a Siemens Westinghouse Power Corporation (Siemens Westinghouse) particle filter system at the Power Systems Development Facility (PSDF) located in Wilsonville, Alabama. The Transport Reactor is an advanced circulating fluidized-bed reactor designed to operate as either a combustor or a gasifier using a particulate control device (PCD). The Transport Reactor was operated as a pressurized gasifier during TC06. Test run TC06 was started on July 4, 2001, and completed on September 24, 2001, with an interruption in service between July 25, 2001, and August 19, 2001, due to a filter element failure in the PCD caused by abnormal operating conditions while tuning the main air compressor. The reactor temperature was varied between 1,725 and 1,825 F at pressures from 190 to 230 psig. In TC06, 1,214 hours of solid circulation and 1,025 hours of coal feed were attained with 797 hours of coal feed after the filter element failure. Both reactor and PCD operations were stable during the test run with a stable baseline pressure drop. Due to its length and stability, the TC06 test run provided valuable data necessary to analyze long-term reactor operations and to identify necessary modifications to improve equipment and process performance as well as progressing the goal of many thousands of hours of filter element exposure.

SOLID WASTE INTEGRATED FORECAST TECHNICAL (SWIFT) REPORT FY2003 THRU FY2046 VERSION 2003.1 VOLUME 2 [SEC 1 & 2

Energy Technology Data Exchange (ETDEWEB)

BARCOT, R.A.

2003-12-01

This report includes data requested on September 10, 2002 and includes radioactive solid waste forecasting updates through December 31, 2002. The FY2003.0 request is the primary forecast for fiscal year FY 2003.

Progress of the research and development on the geological disposal technology of HLW with aid of the industry/university collaboration system and fixed term researcher system

International Nuclear Information System (INIS)

Yamada, Fumitaka; Sonobe, Hitoshi; Igarashi, Hiroshi

2008-02-01

In Japan Atomic Energy Agency (JAEA), various systems associated with the collaboration with industries and universities on the Nuclear Fuel Cycle and the Postdoctoral Fellow system, etc. are enacted. These systems have been operated considering the needs of JAEA's program, industry and academia, resultantly contributed, for example, to basic research and the project development. The activities under these collaboration systems contain personal exchanges, the publication of the accomplishments and utilization of those, in research and development concerning geological disposal technology of high-level radioactive waste (HLW). These activities have progressed in Power Reactor and Nuclear Fuel Development Corporation (PNC) and Japan Nuclear Cycle Development Institute (JNC), which are the successive predecessors of JAEA, through JAEA. The accomplishments from these systems have been not only published as papers in journals and individual technical reports but also integrated into the project reports, accordingly contributed to the advancement of the national program on the geological disposal of HLW. In this report, the progress of the research and development under these systems was investigated from the beginning of the operation of the systems. The contribution to the research and development on geological disposal technology of HLW was also studied. On the basis of these studies, the future utilization of the systems of the collaboration was also discussed from the view point of the management of research and development program. A CD-ROM is attached as an appendix. (J.P.N.)

Subseabed disposal program annual report, January-December 1978. Volume II. Principal investigator progress reports

International Nuclear Information System (INIS)

1979-10-01

The topics covered in this report include: geologic siting considerations for the disposal of radioactive wastes into submarine geologic formations; geologic assessment of the MPG-1 regions Central North Pacific; site mapping; geotechnical aspects of subsurface seabed disposal; heat transfer, thermal and fluid physics in the deep ocean sediments; mechanical response predictive capability; sediment-seawater interaction at 300 0 C, 500 bars; stability of actinides in chloride media; cannister corrosion studies; nuclide sorption and migration; development of apparatus and measurement of thermal conductivity of seabed illite and smectite at temperatures to 500 0 C at simulated depths to 15,000 ft (9000 psi); in-situ heat transfer experiments; preliminary seabed disposal transport modeling studies; radionuclide migration studies; radionuclide distributions in deep ocean cores; benthic biological studies; deep sea microbial studies; activity rates of abyssal communities; Deep-towed RUM III (Sandia Seabed working platform): a third-generation remote underwater manipulator; long coring facility program; transportation; legal, political, and institutional implications of the Seabed Program for radioactive waste disposal

FY1983 HTGR summary level program plan

International Nuclear Information System (INIS)

1983-01-01

The major focus and priority of the FY1983 HTGR Program is the development of the HTGR-SC/C Lead Project through one of the candidate lead utilities. Accordingly, high priority will be given to work described in WBS 04 for site and user specific studies toward the development of the Lead Project. Asessment of advanced HTGR systems will continue during FY1983 in accordance with the High Temperature Process Heat (HTPH) Concept Evaluation Plan. Within the context of that plan, the assessment of the monolithic HTPH concepts has been essentially completed in FY1982 and FY1983 activities and will be limited to documentation only. the major advanced HTGR systems efforts in FY1983 will be focused on the further definition of the Modular Reactor Systems concepts in both the reforming (MRS-R) and Steam Cycle/Cogeneration 9MRS-SC/C) configurations in WBS 41. The effort will concentrate upon key technical issues and trade studies oriented to reduction in expected cost and schedule duration. With regard to the latter, the most significant will be trade study addressing the degree of modularization of reactor plant structures. particular attention will be given to the confinement building which currently defines the critical path for construction

FY2016 Lightweight Materials Annual Progress Report

Energy Technology Data Exchange (ETDEWEB)

None, None

2017-10-31

The Lightweight Materials research and development (R&D) area within the DOE Vehicle Technologies Office (VTO) provides support and guidance for many cutting-edge automotive technologies under development. Research focuses on addressing critical barriers to commercializing lightweight materials for passenger and commercial vehicles. This report describes the progress made on the research and development projects funded by the Lightweight Materials area.

Summary of FY 17 Assessments Sandia National Laboratories: Evaluation of FY16 SNL FCT M2 Milestone Deliverables

Energy Technology Data Exchange (ETDEWEB)

Appel, Gordon John

2017-03-01

This report is the milestone deliverable M4FT-17SN111102091 “Summary of Assessments Performed FY17 by SNL QA POC” for work package FT-17SN11110209 titled “Quality Assurance – SNL”. This report summarizes the FY17 assessment performed on Fuel Cycle Technologies / Spent Fuel and Waste Disposition efforts.

Radiation Area Remedial Action FY 1996 summary report

International Nuclear Information System (INIS)

Hayward, W.M.

1996-11-01

The Radiation Area Remedial Action (RARA) project is responsible for the interim stabilization and maintenance of the majority of the inactive waste sites at the Hanford Site. These waste sites include approximately 400 individual sites and 4,000 acres. Three facilities were removed from the RARA list near the end of fiscal year (FY) 1996P: the 218-W-4B, 218-E-10, and 218-E-12B Burial Grounds. These three facilities are treatment, storage, and disposal (TSD) sites assigned to Fluor Daniel Hanford. Therefore, the RARA project will no longer perform activities on the inactive portions to maintain clear lines of responsibility (fully with Fluor Daniel Hanford). RARA activities are broken into two broad categories: interim stabilization, and surveillance and maintenance (S and M). Interim stabilization addresses major corrective actions for sites with radioactive surface contamination. A site continues to require S and M once it has received interim stabilization. Vegetation management is a significant activity under the RARA project. The goal is to control vegetation that may grow and spread radioactive contamination

1986 Annual report on Low-Level Radioactive Waste Management progress

International Nuclear Information System (INIS)

1987-06-01

This report summarizes the progress of states and compact regions without low-level waste disposal sites (non-sited compact regions and nonmember states) in 1986 in siting new low-level waste disposal facilities. It also reports the volume of low-level waste received for disposal in 1986 by commercially operated low-level waste disposal facilities. 6 figs., 7 tabs

FY 2004 Supplement to the President`s Budget

Data.gov (United States)

Networking and Information Technology Research and Development, Executive Office of the President — ...This Supplement to the Presidents Budget for Fiscal Year (FY) 2004 summarizes the NITRD agencies coordinated research activities and FY 2004 plans, as required by...

Siting of a low-level radioactive waste disposal facility

International Nuclear Information System (INIS)

Alvarado, R.A.

1983-01-01

The Texas Low-Level Radioactive Waste Disposal Authority was established by the 67th Legislature to assure safe and effective disposal of the state's low-level radioactive waste. The Authority operates under provisions of the Texas Low-Level Radioactive Waste Disposal Authority Act, VACS 4590f-1. In Texas, low-level radioactive waste is defined as any radioactive material that has a half-life of 35 years or less or that has less than 10 nanocuries per gram of transuranics, and may include radioactive material not excluded by this definition with a half-life or more than 35 years if special disposal criteria are established. Prior to beginning the siting study, the Authority developed both exclusionary and inclusionary criteria. Major requirements of the siting guidelines are that the site shall be located such that it will not interfere with: (1) existing or near-future industrial use, (2) sensitive environmental and ecological areas, and (3) existing and projected population growth. Therefore, the site should be located away from currently known recoverable mineral, energy and water resources, population centers, and areas of projected growth. This would reduce the potential for inadvertent intruders, increasing the likelihood for stability of the disposal site after closure. The identification of potential sites for disposal of low-level radioactive waste involves a phased progression from statewide screening to site-specific exploration, using a set of exclusionary and preferential criteria to guide the process. This methodology applied the criteria in a sequential manner to focus the analysis on progressively smaller and more favorable areas. The study was divided into three phases: (1) statewide screening; (2) site identification; and (3) preliminary site characterization

FY2011 Annual Progress Report for Propulsion Materials

Energy Technology Data Exchange (ETDEWEB)

Davis, Patrick B. [Office of Energy Efficiency and Renewable Energy (EERE), Washington, DC (United States); Schutte, Carol L. [Office of Energy Efficiency and Renewable Energy (EERE), Washington, DC (United States); Gibbs, Jerry L. [Office of Energy Efficiency and Renewable Energy (EERE), Washington, DC (United States)

2011-12-01

Annual Progress Report for Propulsion Materials focusing on enabling and innovative materials technologies that are critical in improving the efficiency of advanced engines by providing enabling materials support for combustion, hybrid, and power electronics development.

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.

OSU Reactor Sharing Program FY 1995 annual report

International Nuclear Information System (INIS)

Higginbotham, J.F.

1996-10-01

This is the annual report of the activities supported under the Oregon State University Reactor Sharing Program, award number DE-FG06-NE38137. The beginning date for the award was September, 30, 1995 and the end date was September 29, 1996. Work conducted under this award is internally administered at the Radiation Center through a project tasking system. This allows for excellent quality control for the work which is performed from the point of initial contact, through the reactor application, project report generation and financial accounting. For the current fiscal year, FY95, the total cost of the reactor sharing program, including Radiation Center contributions, was $66,323.20 of which $40,000.00 was supplied by the DOE Reactor Sharing Program. The details of individual project costs is given in Table 1. The work performed for the individual projects are described in the brief work descriptions given in Table 2

PDX experimental results in FY82

International Nuclear Information System (INIS)

Kaye, S.M.; Bell, M.; Bol, K.

1983-08-01

This report presents a detailed summary of the major experimental results of PDX in FY82 and represents the efforts of the entire PDX group. Topics covered include β-scaling and fishbone studies, fluctuations, disruptions, impurities and impurity transport, power handling, limiter conditioning, edge studies, plasma fueling, counter-injection, and diagnostic development. A less detailed version will appear as the FY82 PDX contribution to the PPPL Annual Report

2000 Annual Progress Report for Fuels for Advanced CIDI Engines and Fuel Cells

Energy Technology Data Exchange (ETDEWEB)

Chalk, S.

2000-12-11

The Department of Energy's Office of Transportation Technologies Fiscal Year (FY) 2000 Annual Progress Report for the Fuels for Advanced CIDI Engines and Fuel Cells Program highlights progress achieved during FY 2000 and comprises 22 summaries of industry and National Laboratory projects that were conducted. The report provides an overview of the exciting work being conducted to tackle the tough technical challenges associated with developing clean burning fuels that will enable meeting the performance goals of the Emission Control R and D for Advanced CIDI Engines and the Transportation Fuel Cell Power Systems Programs. The summaries cover the effects of CIDI engine emissions and fuel cell power system performance, the effects of lubricants on engine emissions, the effects of fuel and consumed lubricants on exhaust emission control devices and the health and safety, materials compatibility, and economics of advanced petroleum-based fuels.

Final disposal of nuclear waste

Energy Technology Data Exchange (ETDEWEB)

Anon,

1995-10-01

The nuclear industry argues that high level radioactive waste can be safely disposed of in deep underground repositories. As yet, however, no such repositories are in use and the amount of spent nuclear fuel in ponds and dry storage is steadily increasing. Although the nuclear industry further argues that storage is a safe option for up to 50 years and has the merit of allowing the radioactivity of the fuel to decay to a more manageable level, the situation seems to be far from ideal. The real reasons for procrastination over deep disposal seem to have as much to do with politics as safe technology. The progress of different countries in finding a solution to the final disposal of high level waste is examined. In some, notably the countries of the former Soviet Union, cost is a barrier; in others, the problem has not yet been faced. In these countries undertaking serious research into deep disposal there has been a tendency, in the face of opposition from environmental groups, to retreat to sites close to existing nuclear installations and to set up rock laboratories to characterize them. These sites are not necessarily the best geologically, but the laboratories may end up being converted into actual repositories because of the considerable financial investment they represent. (UK).

Final disposal of nuclear waste

International Nuclear Information System (INIS)

Anon.

1995-01-01

The nuclear industry argues that high level radioactive waste can be safely disposed of in deep underground repositories. As yet, however, no such repositories are in use and the amount of spent nuclear fuel in ponds and dry storage is steadily increasing. Although the nuclear industry further argues that storage is a safe option for up to 50 years and has the merit of allowing the radioactivity of the fuel to decay to a more manageable level, the situation seems to be far from ideal. The real reasons for procrastination over deep disposal seem to have as much to do with politics as safe technology. The progress of different countries in finding a solution to the final disposal of high level waste is examined. In some, notably the countries of the former Soviet Union, cost is a barrier; in others, the problem has not yet been faced. In these countries undertaking serious research into deep disposal there has been a tendency, in the face of opposition from environmental groups, to retreat to sites close to existing nuclear installations and to set up rock laboratories to characterize them. These sites are not necessarily the best geologically, but the laboratories may end up being converted into actual repositories because of the considerable financial investment they represent. (UK)

Progress of technological innovation on electric power in FY2014

International Nuclear Information System (INIS)

Nishikawa, Yoshikazu; Fujii, Yutaka; Sasagawa, Toshiro

2015-01-01

This paper overviews the technological development in FY2014 at Tokyo Electric Power Company, Chubu Electric Power Company, Hokuriku Electric Power Company, Shikoku Electric Power Company, and Electric Power Development Company. In this overview, further breakdown was made for the following departments of each company: nuclear power generation, thermal power generation, hydraulic power generation, power transmission, power distribution, transformation, research and development and technological development, and information and communication. In addition, this paper outlines the achievement of technological development at Japan Atomic Power Company, such as the technological development related to the existing power station, development of new technology, and the development of future reactor. Fukushima Daiichi Nuclear Power Station has developed an investigative system using a high altitude survey robot and a movable monitoring system. Hamaoka Nuclear Power Station examined the feasibility of state diagnostic technique based on multi-point analysis, and studied stress corrosion cracking at the newly established Nuclear Safety Research Laboratory. Shika Nuclear Power Station (Unit 1) applied a pipe stress improvement process by means of high frequency induction heating as a stress corrosion cracking countermeasure. Ikata Nuclear Power Station newly adopted high degree cross-linking cation resin, and high cracking strength anion resin as the primary resins. Oma Nuclear Power Station worked on the all reactor core utilization technology of MOX fuel. (A.O.)

Review of Department of Energy HEPA filter test activities, FY 1990--FY 1992

International Nuclear Information System (INIS)

McIntyre, J.A.

1992-01-01

Filter Test Facilities (FTFs) and the FTF Technical Support Group (TSG) continue to provide services to the Department of Energy (DOE). Additional tasks relating to the HEPA filter cycle have been added to the TSG. The tasks include the quality assessment review for the in-place testing of HEPA filters at DOE sites and the formation of an in-place testing standards writing group. Summary of ongoing FTFs and TSG activities for FY 1990-FY 1992 including the technical input for implementation of the High Flow Alternative Test System (HFATS), update of the DOE Standards, the status of the quality assessment review and in-place testing standards writing group are discussed

Organic Tanks Safety Program: Advanced organic analysis FY 1996 progress report

International Nuclear Information System (INIS)

1996-09-01

Major focus during the first part of FY96 was to evaluate using organic functional group concentrations to screen for energetics. Fourier transform infrared and Raman spectroscopy would be useful screening tools for determining C-H and COO- organic content in tank wastes analyzed in a hot cell. These techniques would be used for identifying tanks of potential safety concern that may require further analysis. Samples from Tanks 241-C-106 and -C-204 were analyzed; the major organic in C-106 was B2EHPA and in C-204 was TBP. Analyses of simulated wastes were also performed for the Waste Aging Studies Task; organics formed as a result of degradation were identified, and the original starting components were monitored quantitatively. Sample analysis is not routine and required considerable methods adaptation and optimization. Several techniques have been evaluated for directly analyzing chelator and chelator fragments in tank wastes: matrix-assisted laser desorption/ionization time-of-flight mass spectrometry and liquid chromatography with ultraviolet detection using Cu complexation. Although not directly funded by the Tanks Safety Program, the success of these techniques have implications for both the Flammable Gas and Organic Tanks Safety Programs

Annual report of JMTR, FY 1996. April 1, 1996 - March 31, 1997

Energy Technology Data Exchange (ETDEWEB)

Ooka, Norikazu; Fujiki, Kazuo; Nishiwaki, Kei-ichiro [eds.; Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment; and others

1998-02-01

During FY 1996, the JMTR was operated for 2 complete cycles (118th and 119th cycles) and was utilized for the research and development programs on the reactor technology for LWRs, HTTR and fusion reactor, as well as for basic research of fuels and materials, and for radio-isotope productions. With regard to technology development in the JMTR, improvement of evaluation technique for local neutron spectrum, development of new oxygen sensor for oxide fuel pellet are proceeded. A research on the blanket material for thermonuclear fusion reactor was also progressed. (author)

National Ignition Facility (NIF) FY2015 Facility Use Plan

Energy Technology Data Exchange (ETDEWEB)

Folta, P. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Wisoff, Jeff [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2014-12-18

Major features of the FY2015 NIF Use Plan include: • Performing a record number of layered DT experiments with 28 planned compared with 15 in FY2014. Executing the first plutonium experiments on the NIF in support of the Science Campaigns. • Over 300 targets shots, a 57% increase compared to FY14. This is a stretch goal defined in the 120-Day Study document, and relies upon the success of many shot-rate improvement actions, as well as on the distribution of shot type selected by the users. While the Plan is consistent with this goal, the increased proportion of layered DT experiments described above reduces the margin against this goal. • Commissioning of initial ARC capability, which will support both SSP-HED and SSPICF programs. • Increase in days allocated to Discovery Science to a level that supports an ongoing program for academic use of NIF and an annual solicitation for new proposals. • Six Facility Maintenance and Reconfiguration (FM&R) periods totaling 30 days dedicated to major facility maintenance and modifications. • Utilization of the NIF Facility Advisory Schedule Committee (FASC) to provide stakeholder review and feedback on the NIF schedule. The Use Plan assumes a total FY2015 LLNL NIF Operations funding in MTE 10.7 of $229.465M and in MTE 10.3 of 47.0M. This Use Plan will be revised in the event of significant changes to the FY2015 funding or if NNSA provides FY2016 budget guidance significantly reduced compared to FY2015.

Project Execution Plan for the Remote Handled Low-Level Waste Disposal Project

Energy Technology Data Exchange (ETDEWEB)

Danny Anderson

2014-07-01

As part of ongoing cleanup activities at the Idaho National Laboratory (INL), closure of the Radioactive Waste Management Complex (RWMC) is proceeding under the Comprehensive Environmental Response, Compensation, and Liability Act (42 USC 9601 et seq. 1980). INL-generated radioactive waste has been disposed of at RWMC since 1952. The Subsurface Disposal Area (SDA) at RWMC accepted the bulk of INL’s contact and remote-handled low-level waste (LLW) for disposal. Disposal of contact-handled LLW and remote-handled LLW ion-exchange resins from the Advanced Test Reactor in the open pit of the SDA ceased September 30, 2008. Disposal of remote-handled LLW in concrete disposal vaults at RWMC will continue until the facility is full or until it must be closed in preparation for final remediation of the SDA (approximately at the end of fiscal year FY 2017). The continuing nuclear mission of INL, associated ongoing and planned operations, and Naval spent fuel activities at the Naval Reactors Facility (NRF) require continued capability to appropriately dispose of contact and remote handled LLW. A programmatic analysis of disposal alternatives for contact and remote-handled LLW generated at INL was conducted by the INL contractor in Fiscal Year 2006; subsequent evaluations were completed in Fiscal Year 2007. The result of these analyses was a recommendation to the Department of Energy (DOE) that all contact-handled LLW generated after September 30, 2008, be disposed offsite, and that DOE proceed with a capital project to establish replacement remote-handled LLW disposal capability. An analysis of the alternatives for providing replacement remote-handled LLW disposal capability has been performed to support Critical Decision-1. The highest ranked alternative to provide this required capability has been determined to be the development of a new onsite remote-handled LLW disposal facility to replace the existing remote-handled LLW disposal vaults at the SDA. Several offsite DOE

Accelerator/Experiment Operations - FY 2015

Energy Technology Data Exchange (ETDEWEB)

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

2015-10-01

This Technical Memorandum summarizes the Fermilab accelerator and experiment operations for FY 2015. It is one of a series of annual publications intended to gather information in one place. In this case, the information concerns the FY 2015 NOvA, MINOS+ and MINERvA experiments using the Main Injector Neutrino Beam (NuMI), the activities in the SciBooNE Hall using the Booster Neutrino Beam (BNB), and the SeaQuest experiment and Meson Test Beam (MTest) activities in the 120 GeV external Switchyard beam (SY120).

FY16-20 Strategic Plan.

Energy Technology Data Exchange (ETDEWEB)

Harwell, Amber Suzanne [Sandia National Lab. (SNL-CA), Livermore, CA (United States)

2015-07-01

Welcome to our FY16–FY20 Strategic Plan, which both refects our continued dedication to the work we do and reinforces the importance of the integrated Laboratories’ strategic framework to our future. This document is the result of the leadership team’s journey over the past few years in response to the needs of our nation. In an external environment that continues to change, sometimes in unexpected ways, it is critical that our mission areas and our foundation become increasingly synergistic, forming a whole whose parts are interdependent.

Plans and Progress on Hanford MLLW Treatment and Disposal

International Nuclear Information System (INIS)

McDonald, K. M.; Blackford, L. T.; Nester, D. E.; Connolly, R. R.; McKenney, D. E.; Moy, S. K.

2003-01-01

Mixed low-level waste (MLLW) contains both low-level radioactive materials and low-level hazardous chemicals. The hazardous component of mixed waste has characteristics identified by any or all of the following statutes: the Resource Conservation and Recovery Act of 1976 (RCRA), as amended; the Toxic Substances Control Act of 1976; and Washington State dangerous waste regulations. The Fluor Hanford Waste Management Project (WMP) is responsible for storing, treating, and disposing of solid MLLW, which includes organic and inorganic solids, organics and inorganic lab packs, debris, lead, mercury, long-length equipment, spent melters, and remote-handled (RH) and oversized MLLW. Hanford has 7,000 cubic meters, or about 25%, of the MLLW in storage at U.S. Department of Energy (DOE) sites. Hanford plans to receive 57,000 cubic meters from on-site generators, or about 50% of DOE's newly generated MLLW. In addition, the Hanford Environment Restoration Program and off-site generators having approved Federal Facility Consent Agreement site treatment plans will most likely send 200 cubic meters of waste to be treated and returned to the generators. Volumes of off-site waste receipts will be affected when the MLLW Record of Decision is issued as part of the process for the Hanford Site Solid Waste Environmental Impact Statement (EIS). The WMP objective relative to MLLW is to treat and dispose of ∼8000 cubic meters of existing inventory and newly-generated waste by September 30, 2006

Integrated disposal Facility Sagebrush Habitat Mitigation Project: FY2007 Compensation Area Monitoring Report

Energy Technology Data Exchange (ETDEWEB)

Durham, Robin E.; Sackschewsky, Michael R.

2007-09-01

This report summarizes the first year survival of sagebrush seedlings planted as compensatory mitigation for the Integrated Disposal Facility Project. Approximately 42,600 bare root seedlings and 26,000 pluglings were planted at a mitigation site along Army Loop Road in February 2007. Initial baseline monitoring occurred in March 2007, and first summer survival was assessed in September 2007. Overall survival was 19%, with bare root survival being marginally better than pluglings (21% versus 14%). Likely major factors contributing to low survival were late season planting and insufficient soil moisture during seedling establishment.

Solid Waste Integrated Forecast Technical (SWIFT) Report FY 2001 to FY 2046 Volume 1

International Nuclear Information System (INIS)

BARCOT, R.A.

2001-01-01

In an effort to maintain an up-to-date Solid Waste Forecast, Fluor Hanford, Inc. requested a midyear update to the FY2001 Solid Waste Forecast collected in June 2000. Below is a list of generators reporting significant changes from the baseline FY2001 forecast, as well as approved generators previously not reporting wastes. The updated data was collected in February 2001. The cumulative effect of the changes in the near term was minor. Included in this update are waste generation maps for onsite facilities. The maps are updated annually and use the baseline forecast as a data reference

FY13 Annual Progress Report for SECA Core Technology Program

Energy Technology Data Exchange (ETDEWEB)

Stevenson, Jeffry W. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Koeppel, Brian J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2014-01-31

This progress report covers technical work performed during fiscal year 2013 at PNNL under Field Work Proposal (FWP) 40552. The report highlights and documents technical progress in tasks related to advanced cell and stack component materials development and computational design and simulation.

Commercial LFCM vitrification technology. Quarterly progress report, October-December 1984

Energy Technology Data Exchange (ETDEWEB)

Burkholder, H.C.; Jarrett, J.H. (comps.)

1985-07-01

This report is the first in a series of quarterly reports compiled by the Nuclear Waste Treatment Program Office at Pacific Northwest Laboratory to document progress on commercial liquid-fed ceramic melter (LFCM) vitrification technology. Progress in the following technical subject areas during the first quarter of FY 1985 is discussed: pretreatment systems, melting process chemistry, glass development and characterization, feed preparation and transfer systems, melter systems, canister filling and handling systems, off-gas systems, process/product modeling and control, and supporting studies. 33 figs., 12 tabs.

Present status of technology development on decommissioning and waste management in Nuclear Cycle Backend Directorate. Progress in 2009

International Nuclear Information System (INIS)

Takahashi, Kuniaki; Ishigami, Tsutomu; Funabashi, Hideyuki; Meguro, Yoshihiro; Tachibana, Mitsuo

2010-11-01

It is an important issue to take measures against the matters on decommissioning of retired nuclear facilities and management of low-level radioactive waste arising from research activities and operation of nuclear facilities, and the measures must be taken with rational way by ensuring the safety. As the development, improvement, and proper deployment of technologies will be key factors, a technology development program is under way in Nuclear Cycle Backend Directorate taking account of these matters in cooperation with research and development institutes/centers in Japan Atomic Energy Agency. The technology development items are selected from the viewpoints of systematic implementation of measures and cost reduction; these include the development of computer systems for planning and evaluation of decommissioning programs, supercritical CO 2 fluid leaching method for decontamination, nitrate-ion degradation method, simple and rapid determination method for radioactivity of radioactive waste, safety assessment for waste disposal and so on. This report describes outline and progress of the technology development program conducted in FY2009 by the research and development unit. (author)

76 FR 9399 - Department of State FY10 Service Contract Inventory

Science.gov (United States)

2011-02-17

... DEPARTMENT OF STATE [Public Notice 7321] Department of State FY10 Service Contract Inventory... Contract Inventory. SUMMARY: The Department of State has publically released its Service Contract Inventory for FY10. Section 743 of Division C of the FY 2010 Consolidated Appropriations Act, Public Law 111-117...

Isotope and Nuclear Chemistry Division annual report FY 1986, October 1985-September 1986

International Nuclear Information System (INIS)

Heiken, J.H.

1987-06-01

This report describes progress in the major research and development programs carried out in FY 1986 by the Isotope and Nuclear Chemistry Division. The report includes articles on radiochemical diagnostics and weapons tests; weapons radiochemical diagnostics research and development; other unclassified weapons research; stable and radioactive isotope production and separation; chemical biology and nuclear medicine; element and isotope transport and fixation; actinide and transition metal chemistry; structural chemistry, spectroscopy, and applications; nuclear structure and reactions; irradiation facilities; advanced concepts and technology; and atmospheric chemistry

Isotope and Nuclear Chemistry Division annual report FY 1986, October 1985-September 1986

Energy Technology Data Exchange (ETDEWEB)

Heiken, J.H. (ed.)

1987-06-01

This report describes progress in the major research and development programs carried out in FY 1986 by the Isotope and Nuclear Chemistry Division. The report includes articles on radiochemical diagnostics and weapons tests; weapons radiochemical diagnostics research and development; other unclassified weapons research; stable and radioactive isotope production and separation; chemical biology and nuclear medicine; element and isotope transport and fixation; actinide and transition metal chemistry; structural chemistry, spectroscopy, and applications; nuclear structure and reactions; irradiation facilities; advanced concepts and technology; and atmospheric chemistry.

Industrial feasibility study of a spent nuclear fuel package for direct deep disposal

International Nuclear Information System (INIS)

Le Lous, K.; Loubrieu, J.; Chupeau, J.; Serpantie, J.P.; Becle, D.; Aubry, S.

2001-01-01

EDF has undertaken to study the industrial feasibility of a spent nuclear fuel package meeting direct disposal requirements. In this context, a disposal concept has been defined in which packages are cooled in place until the module is finally sealed. Indeed, one of the objectives of that disposal concept is to reduce the underground area occupied by the repository. A functional analysis has been performed within the framework of that ventilated disposal concept, taking into account the phases of the package lifetime from its conditioning until the disposal post-closure phase. An industrial feasibility study is in progress, which takes into account the functional specifications and some preliminary studies. (author)

FY2014 Fuel & Lubricant Technologies Annual Progress Report

Energy Technology Data Exchange (ETDEWEB)

Stork, Kevin [Office of Energy Efficiency and Renewable Energy (EERE), Washington, DC (United States)

2016-02-01

Annual progress report for Fuel & Lubricant Technologies. The Fuel & Lubricant Technologies Program supports fuels and lubricants research and development (R&D) to provide vehicle manufacturers and users with cost-competitive options that enable high fuel economy with low emissions, and contribute to petroleum displacement.

Interactive reliability analysis project. FY 80 progress report

International Nuclear Information System (INIS)

Rasmuson, D.M.; Shepherd, J.C.

1981-03-01

This report summarizes the progress to date in the interactive reliability analysis project. Purpose is to develop and demonstrate a reliability and safety technique that can be incorporated early in the design process. Details are illustrated in a simple example of a reactor safety system

CEMENTITIOUS BARRIERS PARTNERSHIP FY13 MID-YEAR REPORT

Energy Technology Data Exchange (ETDEWEB)

Burns, H.; Flach, G.; Langton, C.; KOSSON, D.; BROWN, K.; SAMSON, E.; MEEUSSEN, J.; SLOOT, H.; GARBOCZI, E.

2013-05-01

In FY2013, the Cementitious Barriers Partnership (CBP) is continuing in its effort to develop and enhance software tools demonstrating tangible progress toward fulfilling the objective of developing a set of tools to improve understanding and prediction of the long-term structural, hydraulic and chemical performance of cementitious barriers used in nuclear applications. In FY2012, the CBP released the initial inhouse “Beta-version” of the CBP Software Toolbox, a suite of software for simulating reactive transport in cementitious materials and important degradation phenomena. The current primary software components are LeachXS/ORCHESTRA, STADIUM, and a GoldSim interface for probabilistic analysis of selected degradation scenarios. THAMES is a planned future CBP Toolbox component (FY13/14) focused on simulation of the microstructure of cementitious materials and calculation of resultant hydraulic and constituent mass transfer parameters needed in modeling. This past November, the CBP Software Toolbox Version 1.0 was released that supports analysis of external sulfate attack (including damage mechanics), carbonation, and primary constituent leaching. The LeachXS component embodies an extensive material property measurements database along with chemical speciation and reactive mass transport simulation cases with emphasis on leaching of major, trace and radionuclide constituents from cementitious materials used in DOE facilities, such as Saltstone (Savannah River) and Cast Stone (Hanford), tank closure grouts, and barrier concretes. STADIUM focuses on the physical and structural service life of materials and components based on chemical speciation and reactive mass transport of major cement constituents and aggressive species (e.g., chloride, sulfate, etc.). The CBP issued numerous reports and other documentation that accompanied the “Version 1.0” release including a CBP Software Toolbox User Guide and Installation Guide. These documents, as well as, the

FY2012 CoC Competition Grants (New and Renewal)

Data.gov (United States)

Department of Housing and Urban Development — This report displays the FY2012 renewal and new homeless assistance projects awarded by HUD for the FY2012 Continuum of Care (CoC) Program competition. Approximately...

Planning integration FY 1996 program plan. Revision 1

International Nuclear Information System (INIS)

1995-09-01

This Multi-Year Program Plan (MAP) Planning Integration Program, Work Breakdown Structure (WBS) Element 1.8.2, is the primary management tool to document the technical, schedule, and cost baseline for work directed by the US Department of Energy (DOE), Richland Operations Office (RL). As an approved document, it establishes an agreement between RL and the performing contractors for the work to be performed. It was prepared by Westinghouse Hanford Company (WHC) and Pacific Northwest Laboratory (PNL). The MYPPs for the Hanford Site programs are to provide a picture from fiscal year (FY) 1996 through FY 2002. At RL Planning and Integration Division (PID) direction, only the FY 1996 Planning Integration Program work scope has been planned and presented in this MAP. Only those known significant activities which occur after FY 1996 are portrayed in this MAP. This is due to the uncertainty of who will be accomplishing what work scope when, following the award of the Management and Integration (M ampersand I) contract

Mixed Waste Management Facility, revised FY94 Plan

International Nuclear Information System (INIS)

Streit, R.

1994-01-01

This revision of the FY94 Plan incorporates changes to work during FY94 in response to the DOE request in the DOE KD-1 decision letter of June 28,1994. This letter provided guidance of both scope and budget profile in response to the Conceptual Design Report (CDR) issued by the MWMF Project in April, 1994. This work plan only addresses work for the remainder of FY94. A revised plan for the complete project is in development and will be issued separately. Since February, 1994, the MWMF Project has been operating on DOE guidance directing that work on the CDR be completed, that only other essential work be continued to maintain the project, and that costs be maintained at approximately the January, 1994 spending levels until a KD-1 decision was made. This has formed the basis for monthly reports through June, 1994. The baseline contained in this report will become the basis for reports during the remainder of FY94

Hangman Restoration Project Year-End Report FY2008.

Energy Technology Data Exchange (ETDEWEB)

Coeur d' Alene Tribe Department of Natural Resources.

2008-11-12

This report covers the main goals of FY2008 from which the Work Elements were derived. The goals and products are listed by heading and the associated work elements are referenced in the text. A list of the FY2008 Work Elements is included as Appendix A. FY2008 witnessed the completion of the hntkwipn Management Plan and the first substantive efforts to restore the important habitats encompassed by the mitigation properties in the Upper Hangman Watershed. Native grasses were planted and germination was evaluated. Also, drain tiles that greatly altered the hydrologic function of the Sheep and Hangman Creek Flood Plains were removed and/or disrupted. Preparation for future restoration efforts were also made in FY2008. Designs were produced for the realignment of Sheep Creek and the decommissioning of seven drainage ditches within hntkwipn. A prioritization plan was drafted that greatly expands the area of focus for restoring native fish population in Hangman Creek.

Project quality assurance plan for research and development services provided by Oak Ridge National Laboratory in support of the Hanford Grout Disposal Program

Energy Technology Data Exchange (ETDEWEB)

Spence, R.D.; Gilliam, T.M.

1991-11-01

This Project Quality Assurance Plan (PQAP) is being published to provide the sponsor with referenceable documentation for work conducted in support of the Hanford WHC Grout Disposal Program. This plan, which meets NQA-1 requirements, is being applied to work performed at Oak Ridge National Laboratory (ORNL) during FY 1991 in support of this program. It should also be noted that with minor revisions, this plan should be applicable to other projects involving research and development that must comply with NQA-1 requirements.

Project quality assurance plan for research and development services provided by Oak Ridge National Laboratory in support of the Hanford Grout Disposal Program

International Nuclear Information System (INIS)

Spence, R.D.; Gilliam, T.M.

1991-11-01

This Project Quality Assurance Plan (PQAP) is being published to provide the sponsor with referenceable documentation for work conducted in support of the Hanford WHC Grout Disposal Program. This plan, which meets NQA-1 requirements, is being applied to work performed at Oak Ridge National Laboratory (ORNL) during FY 1991 in support of this program. It should also be noted that with minor revisions, this plan should be applicable to other projects involving research and development that must comply with NQA-1 requirements

The America COMPETES Act and the FY2009 Budget

National Research Council Canada - National Science Library

Stine, Deborah D

2008-01-01

.... An issue for Congress is whether FY2009 appropriations will. The Presidents s Office of Science and Technology Policy reports that the FY2009 budget request includes funding for America COMPETES Act initiatives at 88...

Studies of reactor waste conditioning and disposal at CRNL

International Nuclear Information System (INIS)

Beamer, N.V.; Bourne, W.T.; Buckely, L.P.; Pettipas, W.H.; Burrill, K.A.; Dixon, D.F.; Charlesworth, D.H.

1982-09-01

This report is a compilation of five papers presented at the Second Annual Meeting of the Canadian Nuclear Society in Ottawa, 1981 June. These papers describe recent progress in studies being conducted at the Chalk River Nuclear Laboratories related to the permanent disposal of low-and intermediate-level wastes arising in the Canadian nuclear industry. The principal topics discussed include waste processing by incineration, ultrafiltration and reverse osmosis, immobilization in bitumen and glass, and also the strategy for disposal of the conditioned wastes

Disposal of children's stools and its association with childhood diarrhea in India.

Science.gov (United States)

Bawankule, Rahul; Singh, Abhishek; Kumar, Kaushalendra; Pedgaonkar, Sarang

2017-01-05

Children's stool disposal is often overlooked in sanitation programs of any country. Unsafe disposal of children's stool makes children susceptible to many diseases that transmit through faecal-oral route. Therefore, the study aims to examine the magnitude of unsafe disposal of children's stools in India, the factors associated with it and finally its association with childhood diarrhea. Data from the third round of the National Family Health Survey (NFHS-3) conducted in 2005-06 is used to carry out the analysis. The binary logistic regression model is used to examine the factors associated with unsafe disposal of children's stool. Binary logistic regression is also used to examine the association between unsafe disposal of children's stool and childhood diarrhea. Overall, stools of 79% of children in India were disposed of unsafely. The urban-rural gap in the unsafe disposal of children's stool was wide. Mother's illiteracy and lack of exposure to media, the age of the child, religion and caste/tribe of the household head, wealth index, access to toilet facility and urban-rural residence were statistically associated with unsafe disposal of stool. The odds of diarrhea in children whose stools were disposed of unsafely was estimated to be 11% higher (95% CI: 1.01-1.21) than that of children whose stools were disposed of safely. An increase in the unsafe disposal of children's stool in the community also increased the risk of diarrhea in children. We found significant statistical association between children's stool disposal and diarrhea. Therefore, gains in reduction of childhood diarrhea can be achieved in India through the complete elimination of unsafe disposal of children's stools. The sanitation programmes currently being run in India must also focus on safe disposal of children's stool.

Repository Technology Program activities, FY 1988

International Nuclear Information System (INIS)

Yow, J.L. Jr.; Wijesinghe, A.M.; Thorpe, R.K.; Knapp, R.B.

1989-07-01

Our technical activities in FY 1988 included instrument selection and evaluation, calculational work, and simulator development. Near the end of the fiscal year, we began preparing several topical reports to document our results. This fiscal year, we continued developing three-dimensional numerical simulators to model coupled hydrologic-and mechanical-rock mass responses and, thus, to provide representative numerical tools for understanding and calculating these in situ processes. We also began scoping calculations in the second half of FY 1988 to evaluate ERE design criteria, but this work was redirected late in the year when the DOE/AECL Subsidiary Agreement was set aside. Our work in developing and evaluating experimental techniques focused on total pressure measurements, moisture content measurement, and tracer detection instrumentation for sealing experiments and for rock-mass-response field tests. At the end of the fiscal year, we completed a review of measurement technology for instrumenting migration/sorption tests to help define the technological requirements in these areas. By the end of FY 1988, we had completed a review of the existing codes for simulating reactive transport; we are using the results of this review to help formulate plans for future activities in this area. The following sections describe the major RTP tasks and activities at LLNL in more detail, and they include our FY 1988 accomplishments in these areas. 8 refs., 22 figs

FY11 Facility Assessment Study for Aeronautics Test Program

Science.gov (United States)

Loboda, John A.; Sydnor, George H.

2013-01-01

This paper presents the approach and results for the Aeronautics Test Program (ATP) FY11 Facility Assessment Project. ATP commissioned assessments in FY07 and FY11 to aid in the understanding of the current condition and reliability of its facilities and their ability to meet current and future (five year horizon) test requirements. The principle output of the assessment was a database of facility unique, prioritized investments projects with budgetary cost estimates. This database was also used to identify trends for the condition of facility systems.

Progress of R and D on seismic emergency information system

International Nuclear Information System (INIS)

2000-09-01

After the Great Hansin-Awaji Earthquake Disaster occurred in 1995, the Science and Technology Agency commenced 'Frontier Research Program on Earthquake' in FY1996. As a part of this research program, four-year program on 'Research on Real-time Earthquake Information Transmission' has been carried out at JAERI since FY1997. Through the experience of the above earthquake disaster, the importance of accurate and prompt seismic information transmission immediately after the occurrence of the earthquake has been recognized from the viewpoint of disaster mitigation. Under this circumstance, the main activity in Real-time Earthquake Information Transmission Research at JAERI has been placed on the development of a seismic emergency information system. In order to respond to the above R and D, Seismic Emergency Information System Research Team was organized in JAERI in FY1998. In the meantime a part of this R and D program is performed under the coordinated research between JAERI and NIED(National Research Institute for Science and Disaster Prevention). This report describes the recent progress of R and D until FY1999. In the R and D, estimation techniques of hypocenter, fault and earthquake motion parameters, in which the latest results in the field of earthquake engineering were involved, were developed. Until the end of FY1999, the main part of the system, in which the above estimation techniques are introduced, is completed. By this system the seismic information is being transmitted using E-mail and homepage through the inter-net. In addition the databases on the estimated earthquake motion parameter distribution under scenario earthquakes and the surface soil amplification function around JAERI-Tokai site are prepared to examine the applicability of the system. (author)

Environmental Sciences Division annual progress report for period ending September 30, 1993

Energy Technology Data Exchange (ETDEWEB)

1994-05-01

This progress report summarizes the research and development activities conducted in the Environmental Sciences Division (ESD) of Oak Ridge National Laboratory during fiscal year (FY) 1993, which extended from October 1, 1992, through September 30, 1993. The report is structured to provide descriptions of current activities and accomplishments in each of the division`s major organizational units. Following the sections describing the organizational units are sections highlighting ESD Scientific, Technical, and Administrative Achievement awards and listing information necessary to convey the scope of the work in the division. An organizational chart of staff and long-term guests who were in ESD and the end of FY 1993 is located in the final section of the report.

Environmental Sciences Division annual progress report for period ending September 30, 1994

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-12-31

This progress report summarizes the research and development activities conducted in the Environmental Sciences Division (ESD) of Oak Ridge National Laboratory during fiscal year (FY) 1994, which extended from October 1, 1993, through September 30, 1994. The report is structured to provide descriptions of current activities and accomplishments in each of the division`s major organizational units. Following the sections describing the organizational units are sections highlighting ESD Scientific, Technical, and Administrative Achievement awards and listing information necessary to covey the scope of the work in the division. An organizational chart of staff and long-term guests who wee in ESD at the end of FY 1994 is located in the final section of the report.

Environmental Sciences Division annual progress report for period ending September 30, 1994

International Nuclear Information System (INIS)

1994-01-01

This progress report summarizes the research and development activities conducted in the Environmental Sciences Division (ESD) of Oak Ridge National Laboratory during fiscal year (FY) 1994, which extended from October 1, 1993, through September 30, 1994. The report is structured to provide descriptions of current activities and accomplishments in each of the division's major organizational units. Following the sections describing the organizational units are sections highlighting ESD Scientific, Technical, and Administrative Achievement awards and listing information necessary to covey the scope of the work in the division. An organizational chart of staff and long-term guests who wee in ESD at the end of FY 1994 is located in the final section of the report

Environmental Sciences Division annual progress report for period ending September 30, 1993

International Nuclear Information System (INIS)

1994-05-01

This progress report summarizes the research and development activities conducted in the Environmental Sciences Division (ESD) of Oak Ridge National Laboratory during fiscal year (FY) 1993, which extended from October 1, 1992, through September 30, 1993. The report is structured to provide descriptions of current activities and accomplishments in each of the division's major organizational units. Following the sections describing the organizational units are sections highlighting ESD Scientific, Technical, and Administrative Achievement awards and listing information necessary to convey the scope of the work in the division. An organizational chart of staff and long-term guests who were in ESD and the end of FY 1993 is located in the final section of the report

FY 1993 task plans for the Hanford Environmental Dose Reconstruction Project

International Nuclear Information System (INIS)

Shipler, D.B.

1991-10-01

The purpose of the Hanford Environmental Dose Reconstruction (HEDR) Project is to estimate radiation doses from Hanford Site operations since 1944 to individuals and populations. The primary objective of work to be performed in FY 1993 is to complete the source term estimates and dose estimates for key radionuclides for the air and river pathways. At the end of FY 1993, the capability will be in place to estimate doses for individuals in the extended (32-county) study area, 1944--1991. Native American research will continue to provide input for tribal dose estimates. In FY 1993, the Technical Steering Panel (TSP) will decide whether demographic and river pathways data collection should be extended beyond FY 1993 levels. The FY 1993 work scopes and milestones in this document are based on the work plan discussed at the TSP Budget/Fiscal Subcommittee meeting on August 19--20, 1991. Table 1 shows the FY 1993 milestones; Table 2 shows estimated costs. The subsequent work scope descriptions are based on the milestones. This document and the FY 1992 task plans will form the basis for a contract with Battelle and the Centers for Disease Control (CDC). The 2-year dose reconstruction contract is expected to begin in February 1992. This contract will replace the current arrangement, whereby the US Department of Energy directly funds the Pacific Northwest Laboratory to conduct dose reconstruction work. In late FY 1992, the FY 1993 task plans will be more fully developed with detailed technical approaches, data quality objectives, and budgeted labor hours. The task plans will be updated again in July 1993 to reflect any scope, milestone, or cost changes directed during the year by the TSP. 2 tabs

Isotope and Nuclear Chemistry Division annual report FY 1985, October 1984-September 1985

International Nuclear Information System (INIS)

Heiken, J.H.

1986-04-01

This report describes progress in the major research and development programs carried out in FY 1985 by the Isotope and Nuclear Chemistry Division. It covers radiochemical diagnostics of weapons tests; weapons radiochemical diagnostics research and development; other unclassified weapons research; stable and radioactive isotope production, separation, and applications (including biomedical applications); element and isotope transport and fixation; actinide and transition metal chemistry; structural chemistry, spectroscopy, and applications; nuclear structure and reactions; irradiations facilities; advanced analytical techniques; development and applications; atmospheric chemistry and transport; and earth and planetary processes

Projects at the component development and integration facility. Quarterly technical progress report, April 1, 1994--June 30, 1994

International Nuclear Information System (INIS)

1994-01-01

This quarterly technical progress report presents progress on the projects at the Component Development and Integration Facility (CDIF) during the third quarter of FY94. The CDIF is a major Department of Energy test facility in Butte, Montana, operated by MSE, Inc. Projects in progress include: Biomass Remediation Project; Heavy Metal-Contaminated Soil Project; MHD Shutdown; Mine Waste Technology Pilot Program; Plasma Projects; Resource Recovery Project; and Spray Casting Project

Stabilization and isolation of low-level liquid waste disposal sites

International Nuclear Information System (INIS)

Phillips, S.J.; Gilbert, T.W.

1987-01-01

Rockwell Hanford Operations is developing and testing equipment for stabilization and isolation of low-level radioactive liquid waste disposal sites. Stabilization and isolation are accomplished by a dynamic consolidation and particulate grout injection system. System equipment components include: a mobile grout plant for transport, mixing, and pumping of particulate grout; a vibratory hammer/extractor for consolidation of waste, backfill, and for emplacement of the injector; dynamic consolidation/injector probe for introducing grout into fill material; and an open-void surface injector that uses surface or subsurface mechanical or pneumatic packers and displacement gas filtration for introducing grout into disposal structure access piping. Treatment of a liquid-waste disposal site yields a physically stable, cementitious monolith. Additional testing and modification of this equipment for other applications to liquid waste disposal sites is in progress

R and D programme for HLW disposal in Japan

International Nuclear Information System (INIS)

Tsuboya, Takao

1997-01-01

The Power Reactor and Nuclear Fuel Development Corporation (PNC) has been active in developing an R and D programme for high-level radioactive waste (HLW) disposal in accordance with the overall HLW management programme defined by the Atomic Energy Commission (AEC) of Japan. The aim of the R and D activities at the current stage is to provide a scientific and technical basis for the geological disposal of HLW in Japan, which is turn promotes understanding of the safety concept not only in the scientific and technical community but also by the general public. As a major milestone in the R and D programme, PNC submitted a first progress report, referred to as H3, in September 1992. H3 summarised the results of R and D activities up to March 1992 and identified priority issues for further study. The second progress report, scheduled to be submitted around 2000, and should demonstrated more rigorously and transparently the feasibility of the specified disposal concept. It should also provide input for the siting and regulatory processes, which will be set in motion after the year 2000. (author). 10 refs., 4 figs

Theoretical Division annual report, FY 1975

International Nuclear Information System (INIS)

Carruthers, P.A.

1976-02-01

This report presents an overview of the activities in the Theoretical Division and a summary of research highlights during FY 1975. It is intended to inform a wide audience about the theoretical work of the LASL and, therefore, contains introductory material which places recent advances in a broader context. The report is organized into two special interest reports: reactor safety research and the Advanced Research Committee, and 11 reports from the T-Division group leaders on the work of their respective groups. Main interests and responsibilities are outlined including the relationship of the group's work to the work of other T-Division groups and other divisions at the Laboratory. The description of research highlights for FY 1975 explains in a fairly simple, straightforward manner the major recent advances and their significance. Each group report is followed by a publication list for FY 1975 (330 references) and a list of talks given outside the Laboratory (140 references). 29 figures

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

Energy Technology Data Exchange (ETDEWEB)

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

2012-02-03

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

1st Quarter Transportation Report FY 2015: Radioactive Waste Shipments to and from the Nevada National Security Site (NNSS)

Energy Technology Data Exchange (ETDEWEB)

Gregory, Louis [National Security Technologies, LLC, Las Vegas, NV (United States)

2015-02-20

This report satisfies the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO) commitment to prepare a quarterly summary report of radioactive waste shipments to and from the Nevada National Security Site (NNSS) Radioactive Waste Management Complex (RWMC) at Area 5. There were no shipments sent for offsite treatment and returned to the NNSS this quarter. This report summarizes the 1st quarter of Fiscal Year (FY) 2015 low-level radioactive waste (LLW) and mixed low-level radioactive waste (MLLW) shipments. Tabular summaries are provided which include the following: Sources of and carriers for LLW and MLLW shipments to and from the NNSS; Number and external volume of LLW and MLLW shipments; Highway routes used by carriers; and Incident/accident data applicable to LLW and MLLW shipments. In this report shipments are accounted for upon arrival at the NNSS, while disposal volumes are accounted for upon waste burial. The disposal volumes presented in this report include minor volumes of non-radioactive classified waste/material that were approved for disposal (non-radioactive classified or nonradioactive classified hazardous). Volume reports showing cubic feet generated using the Low-Level Waste Information System may vary slightly due to rounding conventions for volumetric conversions from cubic meters to cubic feet.

A Summary of Properties Used to Evaluate INEEL Calcine Disposal in the Yucca Mountain Repository

International Nuclear Information System (INIS)

Dahl, C.A.

2003-01-01

To support evaluations of the direct disposal of Idaho National Engineering and Environmental Laboratory calcines to the repository at Yucca Mountain, an evaluation of the performance of the calcine in the repository environment must be performed. This type of evaluation demonstrates, through computer modeling and analysis, the impact the calcine would have on the ability of the repository to perform its function of containment of materials during the repository lifetime. This report discusses parameters that were used in the scoping evaluation conducted in FY 2003. It provides nominal values for the parameters, with explanation of the source of the values, and how the values were modified for use in repository analysis activities

InterProScan Result: FY739668 [KAIKOcDNA[Archive

Lifescience Database Archive (English)

Full Text Available FY739668 FY739668_1_ORF1 51F1790620AF007E PANTHER PTHR21347 CLEFT LIP AND PALATE ASSOCIATED TRANSME...MBRANE PROTEIN-RELATED 1.4e-64 T IPR008429 Cleft lip and palate transmembrane 1 ...

Whither nuclear waste disposal?

Energy Technology Data Exchange (ETDEWEB)

Cotton, T A [JK Research Associates, Silver Spring, MD (United States)

1990-07-01

With respect to the argument that geologic disposal has failed, I do not believe that the evidence is yet sufficient to support that conclusion. It is certainly true that the repository program is not progressing as hoped when the Nuclear Waste Policy Act of 1982 established a 1998 deadline for initial operation of the first repository. The Department of Energy (DOE) now expects the repository to be available by 2010, and tat date depends upon a finding that the Yucca Mountain site - the only site that DOE is allowed by law to evaluate - is in fact suitable for use. Furthermore, scientific evaluation of the site to determine its suitability is stopped pending resolution of two lawsuits. However, I believe it is premature to conclude that the legal obstacles are insuperable, since DOE just won the first of the two lawsuits, and chances are good it will win the second. The concept of geologic disposal is still broadly supported. A recent report by the Board on Radioactive Waste Management of the National Research Council noted that 'There is a worldwide scientific consensus that deep geological disposal, the approach being followed in the United States, is the best option for disposing of high-level radioactive waste'. The U.S. Nuclear Regulatory Commission (USNRC) recently implicitly endorsed this view in adopting an updated Waste Confidence position that found confidence that a repository could be available in the first quarter of the next century - sufficient time to allow for rejection of Yucca Mountain and evaluation of a new site.

Whither nuclear waste disposal?

International Nuclear Information System (INIS)

Cotton, T.A.

1990-01-01

With respect to the argument that geologic disposal has failed, I do not believe that the evidence is yet sufficient to support that conclusion. It is certainly true that the repository program is not progressing as hoped when the Nuclear Waste Policy Act of 1982 established a 1998 deadline for initial operation of the first repository. The Department of Energy (DOE) now expects the repository to be available by 2010, and tat date depends upon a finding that the Yucca Mountain site - the only site that DOE is allowed by law to evaluate - is in fact suitable for use. Furthermore, scientific evaluation of the site to determine its suitability is stopped pending resolution of two lawsuits. However, I believe it is premature to conclude that the legal obstacles are insuperable, since DOE just won the first of the two lawsuits, and chances are good it will win the second. The concept of geologic disposal is still broadly supported. A recent report by the Board on Radioactive Waste Management of the National Research Council noted that 'There is a worldwide scientific consensus that deep geological disposal, the approach being followed in the United States, is the best option for disposing of high-level radioactive waste'. The U.S. Nuclear Regulatory Commission (USNRC) recently implicitly endorsed this view in adopting an updated Waste Confidence position that found confidence that a repository could be available in the first quarter of the next century - sufficient time to allow for rejection of Yucca Mountain and evaluation of a new site

Federal Research and Development Funding: FY2011

Science.gov (United States)

2011-03-25

NSF’s offices in 54 Arden L. Bement, Jr., Transformative Research: The Artistry and Alchemy of the 21st... financing for the Technology Innovation Program (TIP) increases 14.3% over FY2010 funding to $79.9 million. The construction budget declines 15.1% to $124.8...Extension Partnership Program received $124.7 million, 13.4% more than FY2009, while financing for TIP increased 7.5% to $69.9 million. Construction

EST Table: FY033047 [KAIKOcDNA[Archive

Lifescience Database Archive (English)

Full Text Available FY033047 rbmte3b19 11/12/09 n.h 11/11/04 43 %/139 aa ref|XP_974421.1| PREDICTED: similar to synoviolin...staneum] 11/11/04 n.h 11/11/04 n.h 11/11/04 n.h 11/11/04 n.h 11/11/04 39 %/139 aa gi|91087035|ref|XP_974421.1| PREDICTED: similar to synoviolin [Tribolium castaneum] FY033047 bmte ...

Site Maintenance Plan: Part 2, Site Maintenance Action Plan for FY 1994

Energy Technology Data Exchange (ETDEWEB)

Fisk, E.L.

1994-06-01

This Fiscal Year (FY) 1994 Site Maintenance Action Plan (SMAP) is Part II of the Site Maintenance Plan, and has been written by Westinghouse Hanford Company (WHC) to outline the requirements stated in DOE Order 4330.4B, Maintenance Management Program, Chapter 1, Paragraph 3.3.1. The SMAP provides an annual status of maintenance initiatives completed and planned, a summary of performance indicators, a summary of maintenance backlog, a listing of real property and capital equipment maintenance cost estimates that were used to create the FY 1996 infrastructure and maintenance budget input, and a listing of proposed line item and general plant projects. Additionally, assumptions for various Site programs are listed to bring the Site Maintenance Plan into focus with overall Site activities. The primary mission at Hanford is to clean up the Site. In this cleanup process WHC will provide scientific and technological expertise to meet global needs, and partnership with stakeholders in the region to develop regional economic diversification. Other missions at the Hanford Site include energy research and development, and waste management and disposal activities. Their primary mission has a 30-year projected life span and will direct the shutting down and cleanup of defense production facilities and the Fast Flux Test Facility. This long-term mission requires continuous maintenance and in many instances, replacement of existing basic infrastructure, support facilities, and utilities. Without adequate maintenance and capital funding these infrastructure, support facilities, and utilities will continue to deteriorate causing an increase in backlogged work.

Site Maintenance Plan: Part 2, Site Maintenance Action Plan for FY 1994

International Nuclear Information System (INIS)

Fisk, E.L.

1994-06-01

This Fiscal Year (FY) 1994 Site Maintenance Action Plan (SMAP) is Part II of the Site Maintenance Plan, and has been written by Westinghouse Hanford Company (WHC) to outline the requirements stated in DOE Order 4330.4B, Maintenance Management Program, Chapter 1, Paragraph 3.3.1. The SMAP provides an annual status of maintenance initiatives completed and planned, a summary of performance indicators, a summary of maintenance backlog, a listing of real property and capital equipment maintenance cost estimates that were used to create the FY 1996 infrastructure and maintenance budget input, and a listing of proposed line item and general plant projects. Additionally, assumptions for various Site programs are listed to bring the Site Maintenance Plan into focus with overall Site activities. The primary mission at Hanford is to clean up the Site. In this cleanup process WHC will provide scientific and technological expertise to meet global needs, and partnership with stakeholders in the region to develop regional economic diversification. Other missions at the Hanford Site include energy research and development, and waste management and disposal activities. Their primary mission has a 30-year projected life span and will direct the shutting down and cleanup of defense production facilities and the Fast Flux Test Facility. This long-term mission requires continuous maintenance and in many instances, replacement of existing basic infrastructure, support facilities, and utilities. Without adequate maintenance and capital funding these infrastructure, support facilities, and utilities will continue to deteriorate causing an increase in backlogged work

Fabrication Equipment for Periodic Material Assemblies and Ph Assemblies and Photonic Crystals (DURIP FY06)

Science.gov (United States)

2008-04-29

An exhaust hood is necessary for binder removal. Cooling requires a fan at a second speed setpoint . Firing profiles need to be precisely...29,935.06 from Ohio match. Plasmalab 80 Plus Compact etching system (left) and heater/ chiller unit (right). CAHN TherMax 500 High Pressure TGA...the current research is aimed to optimize parameters of the structure, in order to improve the resonant properties of the periodic layered structures

Lead Slowing-Down Spectrometry Time Spectral Analysis for Spent Fuel Assay: FY12 Status Report

Energy Technology Data Exchange (ETDEWEB)

Kulisek, Jonathan A.; Anderson, Kevin K.; Casella, Andrew M.; Siciliano, Edward R.; Warren, Glen A.

2012-09-28

Executive Summary Developing a method for the accurate, direct, and independent assay of the fissile isotopes in bulk materials (such as used fuel) from next-generation domestic nuclear fuel cycles is a goal of the Office of Nuclear Energy, Fuel Cycle R&D, Material Protection and Control Technology (MPACT) Campaign. To meet this goal, MPACT supports a multi-institutional collaboration, of which PNNL is a part, to study the feasibility of Lead Slowing Down Spectroscopy (LSDS). This technique is an active nondestructive assay method that has the potential to provide independent, direct measurement of Pu and U isotopic masses in used fuel with an uncertainty considerably lower than the approximately 10% typical of today’s confirmatory methods. This document is a progress report for FY2012 PNNL analysis and algorithm development. Progress made by PNNL in FY2012 continues to indicate the promise of LSDS analysis and algorithms applied to used fuel assemblies. PNNL further refined the semi-empirical model developed in FY2011 based on singular value decomposition (SVD) to numerically account for the effects of self-shielding. The average uncertainty in the Pu mass across the NGSI-64 fuel assemblies was shown to be less than 3% using only six calibration assemblies with a 2% uncertainty in the isotopic masses. When calibrated against the six NGSI-64 fuel assemblies, the algorithm was able to determine the total Pu mass within <2% uncertainty for the 27 diversion cases also developed under NGSI. Two purely empirical algorithms were developed that do not require the use of Pu isotopic fission chambers. The semi-empirical and purely empirical algorithms were successfully tested using MCNPX simulations as well applied to experimental data measured by RPI using their LSDS. The algorithms were able to describe the 235U masses of the RPI measurements with an average uncertainty of 2.3%. Analyses were conducted that provided valuable insight with regard to design requirements (e

Strategy for Meeting the Secretary of Energy and Hanford Site FY 2001 Pollution Prevention Goals

International Nuclear Information System (INIS)

CLARK, D.E.

2000-01-01

The purpose of this strategy is to identify the Fiscal Year (FY) 2001 Hanford Site waste reduction, sanitary recycling and affirmative procurement goals and identify the action required to ensure that the Secretary of Energy's FY 2005 pollution prevention and the FY 2001 Hanford Site goals are met. The strategy and plan to ensure that the Secretary of Energy's routine waste reduction, recycling, cleanup/stabilization waste and affirmative procurement goals are met consists of four phases. The first phase is to ensure that the infrastructure is in place to support planning and organization. This phase involves ensuring that roles and responsibilities are identified; requirement documents are current; goals and successes are communicated; and accurate and current waste information is available. Roles and responsibilities are identified and the RL requirement documents (i.e., the Hanford Site Waste Minimization and Pollution Prevention Awareness Program Plan and Hanford Site Guide for Preparing and Maintaining Generator Group Pollution Prevention Program Documentation) will specify the Secretary of Energy's goals. Goals will be communicated formally and informally via the Hanford Reach, training sessions, meetings and correspondence. Sharing of pollution prevention successes and goal progress are encouraged at the Pollution Prevention/Waste Minimization (PZ/WMin) quarterly meetings. Existing site waste generation databases will be utilized to provide current waste generation data. The second phase of the strategy and plan is to establish and allocate goals by prime contractor (i.e. Fluor Hanford, Inc. (FH), Pacific Northwest National Laboratory (PNNL), Bechtel Hanford Inc. (BHI), and CH2MHill Hanford Group (CHG)). This requires determining current status toward meeting the Secretary of Energy's goals; establishing the Hanford Site FY goals, and allocating waste reduction goals by prime contractor. The third phase of the strategy and plan is goal implementation. This

InterProScan Result: FY753977 [KAIKOcDNA[Archive

Lifescience Database Archive (English)

Full Text Available FY753977 FY753977_4_ORF1 DC54D40DFB54A4B1 PFAM PF05753 TRAP_beta NA ? IPR008856 unintegrated Cellular... Component: endoplasmic reticulum (GO:0005783)|Cellular Component: integral to membrane (GO:0016021) ...

Controller's 2006 annual report : fiscal year ending September 30, 2006.

Energy Technology Data Exchange (ETDEWEB)

Crooks, Jennifer Shuk-Ian

2007-02-01

I am pleased to present the CFO's FY06 Financial Report for Sandia National Laboratories (SNL). As a contractor to DOE and other government agencies, the bulk of SNL's revenue is from tax dollars. SNL's FY06 total revenue, total expenditures, and total employment levels were slightly below the FY05 record high levels. Throughout FY06, SNL business staff continued to improve SNL's financial stewardship of entrusted taxpayer funds through implementation of best-in-class practices in financial business operations and internal control policies and procedures to ensure compliance with all accounting standards and provide accountability to our customers. Our FY06 efforts focused on process certification and improvement, implementing OMB Circular A-123, achieving assurance activities, implementation of a Financial Management Competency Program throughout SNL, and continuous assessment of trends and emerging issues.

Pinellas Plant FY1990 site specific implementation plan

International Nuclear Information System (INIS)

Klein, R.D.

1990-02-01

This Site Specific Implementation Plan describes the Corrective Action, Environmental Restoration, and Waste Management activities to be performed at the Pinellas Plant in FY1990 (October 1, 1989 to September 30, 1989). These FY1990 activities are described in the Pinellas Plant FY1991--95 Five-Year Plan. The information used to prepare this plan reflects the best estimate of the project scope, schedules, regulatory, and funding requirements at the time of plan preparation. The Environmental Restoration/Waste Management Five-Year Plan is a dynamic document and will be modified each year; the Site Specific Implementation Plan will, in turn, be modified each year to reflect new findings, information, and knowledge of the various projects. 4 figs., 11 tabs

The Chinese FY-1 Meteorological Satellite Application in Observation on Oceanic Environment

Science.gov (United States)

Weimin, S.

meteorological satellite is stated in this paper. exploration of the ocean resources has been a very important question of global strategy in the world. The exploration of the ocean resources includes following items: Making full use of oceanic resources and space, protecting oceanic environment. to observe the ocean is by using of satellite. In 1978, US successfully launched the first ocean observation satellite in the world --- Sea Satellite. It develops ancient oceanography in to advanced space-oceanography. FY-1 B and FY- IC respectively. High quality data were acquired at home and abroad. FY-1 is Chinese meteorological satellite, but with 0.43 ~ 0.48 μm ,0.48 ~ 0.53 μm and 0.53 ~ 0.58 μm three ocean color channels, actually it is a multipurpose remote sensing satellite of meteorology and oceanography. FY-1 satellite's capability of observation on ocean partly, thus the application field is expanded and the value is increased. With the addition of oceanic channels on FY-1, the design of the satellite is changed from the original with meteorological observation as its main purpose into remote sensing satellite possessing capability of observing meteorology and ocean as well. Thus, the social and economic benefit of FY-1 is increased. the social and economic benefit of the development of the satellite is the key technique in the system design of the satellite. technically feasible but also save the funds in researching and manufacturing of the satellite, quicken the tempo of researching and manufacturing satellite. the scanning radiometer for FY-1 is conducted an aviation experiment over Chinese ocean. This experiment was of vital importance to the addition of oceanic observation channel on FY-1. FY-1 oceanic channels design to be correct. detecting ocean color. This is the unique character of Chinese FY-1 meteorological satellite. meteorological remote sensing channel on FY-1 to form detecting capability of three visible channels: red, yellow and blue

Nevada Test Site-Directed Research and Development: FY 2006 Report

International Nuclear Information System (INIS)

Wil Lewis, editor

2007-01-01

The Nevada Test Site Directed Research and Development (SDRD) program completed its fifth successful year of research and development activities in FY 2006. Forty new projects were selected for funding this year, and ten FY 2005 projects were brought to conclusion. The total funds expended by the SDRD program were $6 million, for an average per-project cost of $120 thousand. Beginning in May, 2006 programmatic burden rates were applied to SDRD project costs. An external audit conducted in September 2006 verified that appropriate accounting practices were applied to the SDRD program. Highlights for the year included: the filing of 27 invention disclosures for intellectual property generated by FY 2006 projects; programmatic adoption of four FY 2005 SDRD-developed technologies; participation in the tri-Lab Laboratory Directed Research and Development (LDRD) and SDRD program review that was broadly attended by NTS, NNSA, LDRD, and U.S. Department of Homeland Security representatives; peer reviews of all FY 2006 projects; and the successful completion of 50 R and D projects, as presented in this report

Nevada Test Site-Directed Research and Development: FY 2006 Report

Energy Technology Data Exchange (ETDEWEB)

Wil Lewis, editor

2007-08-01

The Nevada Test Site–Directed Research and Development (SDRD) program completed its fifth successful year of research and development activities in FY 2006. Forty new projects were selected for funding this year, and ten FY 2005 projects were brought to conclusion. The total funds expended by the SDRD program were $6 million, for an average per-project cost of $120 thousand. Beginning in May, 2006 programmatic burden rates were applied to SDRD project costs. An external audit conducted in September 2006 verified that appropriate accounting practices were applied to the SDRD program. Highlights for the year included: the filing of 27 invention disclosures for intellectual property generated by FY 2006 projects; programmatic adoption of four FY 2005 SDRD-developed technologies; participation in the tri-Lab Laboratory Directed Research and Development (LDRD) and SDRD program review that was broadly attended by NTS, NNSA, LDRD, and U.S. Department of Homeland Security representatives; peer reviews of all FY 2006 projects; and the successful completion of 50 R&D projects, as presented in this report.

Annual report 2000. Department of wastes disposal and storage

International Nuclear Information System (INIS)

2001-01-01

This annual report presents the missions, the organization, the researches progress, the events, the publications and the personnel formation of the Department of wastes disposal and storage in the year 2000, one of the CEA fuel cycle Direction. (A.L.B.)

Advanced Industrial Materials (AIM) program. Annual progress report. FY 1996

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-04-01

The Advanced Industrial Materials (AIM) Program underwent a major transformation in Fiscal Year 1995 and these changes have continued to the present. When the Program was established in 1990 as the Advanced Industrial Concepts (AIC) Materials Program, the mission was to conduct applied research and development to bring materials and processing technologies from the knowledge derived from basic research to the maturity required for the end use sectors for commercialization. In 1995, the Office of Industrial Technologies (OIT) made radical changes in structure and procedures. All technology development was directed toward the seven `Vision Industries` that use about 80% of industrial energy and generated about 90% of industrial wastes. These are: aluminium; chemical; forest products; glass; metal casting; refineries; and steel. OIT is working with these industries, through appropriate organizations, to develop Visions of the desired condition of each industry some 20 or 25 years in the future and then to prepare Road Maps and Implementation Plans to enable them to reach their goals. The mission of AIM has, therefore, changed to `Support development and commercialization of new or improved materials to improve productivity, product quality, and energy efficiency in the major process industries.` Though AIM remains essentially a National Laboratory Program, it is necessary that each project have industrial partners, including suppliers to, and customers of, the seven industries. Now, well into FY 1996, the transition is nearly complete and the AIM Program remains healthy and productive, thanks to the superb investigators and Laboratory Program Managers. Separate abstracts have been indexed into the energy database for articles from this report.

NREL Partnership Survey - FY 2016 Results

Energy Technology Data Exchange (ETDEWEB)

2016-09-01

The National Renewable Energy Laboratory (NREL) conducts an annual partnership satisfaction survey in which we ask our clients to rate NREL in a number of areas. As a national laboratory, the principal areas we focus on include value, timeliness, quality, price, and capabilities. This fact sheet shows the results of a survey with 300 customers responding to 11 questions using ratings that vary from 'strongly agree' to 'strongly disagree.' In FY 16, 100% of the scores improved or were equal to FY 15 numbers.

Hanford Site Environment Safety and Health (ES and H) FY 1999 and FY 2000 Execution Commitment Summary

Energy Technology Data Exchange (ETDEWEB)

REEP, I.E.

1999-12-01

All sites in the U.S. Department of Energy (DOE) Complex prepare this report annually for the DOE Office of Environment, Safety and Health (EH). The purpose of this report is to provide a summary of the previous and current year's Environment, Safety and Health (ES&H) execution commitments and the S&H resources that support these activities. The fiscal year (FY) 1999 and 2000 information (Sieracki 1999) and data contained in the ''Hanford Site Environment, Safety and Health Fiscal Year 2001 Budget-Risk Management Summary'' (RL 1999) were the basis for preparing this report. Fiscal year 2000 finding of Office of Environmental Management (EM) and Office of Nuclear Energy, Science and Technology (NE) activities is based on the President's budget of $1,065.1 million and $28.0 million, plus $2.7 million carryover finding, respectively, as of October 31, 1999. Any funding changes as a result of the Congressional appropriation process will be reflected in the Fiscal Year 2002 ES&H Budget-Risk Management Summary to be issued in May 2000. This report provides the end-of-year status of FY 1999 ES&H execution commitments, including actual S&H expenditures, and describes planned FY 2000 ES&H execution commitments and the S&H resources needed to support those activities. This requirement is included in the ES&H ''Guidance for FY200l Budget Formulations and Execution'' (DOE 1999).

Cleanliness of disposable vs nondisposable electrocardiography lead wires in children.

Science.gov (United States)

Addison, Nancy; Quatrara, Beth; Letzkus, Lisa; Strider, David; Rovnyak, Virginia; Syptak, Virginia; Fuzy, Lisa

2014-09-01

Mediastinitis costs hospitals thousands of dollars a year and increases the incidence of patient morbidity and mortality. No studies have been done to evaluate adenosine triphosphate (ATP) counts on disposable and nondisposable electrocardiography (ECG) lead wires in pediatric patients. To compare the cleanliness of disposable and nondisposable ECG lead wires in postoperative pediatric cardiac surgery patients by measuring the quantity of ATP (in relative luminescence units [RLUs]). ATP levels correlate with microbial cell counts and are used by institutions to assess hospital equipment and cleanliness. A prospective, randomized trial was initiated with approval from the institutional review board. Verbal consent was obtained from the parents/guardians for each patient. Trained nurses performed ATP swabs on the right and left upper ECG cables on postoperative days 1, 2, and 3. This study enrolled 51 patients. The disposable ECG lead wire ATP count on postoperative day 1 (median, 157 RLUs) was significantly lower (P disposable ECG lead wires (median, 200 RLUs) was also lower (P = .06) than the count for the nondisposable ECG lead wires (median, 453 RLUs). Results of this study support the use of disposable ECG lead wires in postoperative pediatric cardiac surgery patients for at least the first 48 hours as a direct strategy to reduce the ATP counts on ECG lead wires. ©2014 American Association of Critical-Care Nurses.

Human Factors Regulatory Research Program Plan, FY 1989--FY 1992

International Nuclear Information System (INIS)

Coffman, F.; Persensky, J.; Ryan, T.; Ramey-Smith, A.; Goodman, C.; Serig, D.; Trager, E; Nuclear Regulatory Commission, Washington, DC; Nuclear Regulatory Commission, Washington, DC; Nuclear Regulatory Commission, Washington, DC

1989-10-01

This report describes the currently ongoing (FY 1989) and planned (FY 1989-1992) Human Factors Regulatory Research Program in the NRC Office of Nuclear Regulatory Research (RES). Examples of the influence of human factors on nuclear safety are presented, and the role of personnel is discussed. Current regulatory issues associated with human factors in the nuclear system and the purpose of the research plan are provided. The report describes the research process applied to the human factors research issues and the program activities: Personnel Performance Measurement, Personnel Subsystem, Human-System Interface. Organization and Management, and Reliability Assessment. The research being conducted within each activity is summarized along with the objectives, background information, and expected regulatory products. Budget and personnel forecasts are provided along with a summary of contractors performing some of the ongoing research. Appendices contain a chronology of human factors research at NRC, a description of the research approach, an update on human factors programs and initiatives in RES and other NRC offices, and the integration among these programs. 46 refs., 5 tabs

Oak Ridge National Laboratory Institutional Plan FY 1984-FY 1989

International Nuclear Information System (INIS)

1983-11-01

In this plan, Oak Ridge National Laboratory (ORNL) continues to be committed to scientific and technological research that is based on technical excellence and innovation and that provides a foundation for and a stimulus to broader and more sustained economic growth. DOE is being asked to assist in establishing a new program for Laboratory cooperation with industry, beginning with an initial focus on materials science. The current Institutional Plan thus projects growth in the materials science area as well as in other basic physical science areas and suggests a new initiative designed to extend the various technology transfer activities and to make them more effective by using ORNL as the trial Laboratory for some of these different approaches. This Institutional Plan projects a stable future for ORNL, with only modest amounts of growth in selected areas of research for the FY 1984-FY 1989 planning cycle. Summaries of the overall picture of the proposed budget and personnel levels for the current planning cycle are included. Scientific programs, laboratory resource development, and private sector interactions are discussed

Technology Development, Evaluation, and Application (TDEA) FY 1995 progress report - Environmental, Safety, and Health (ESH) division

Energy Technology Data Exchange (ETDEWEB)

Andrews, L.L.

1996-09-01

This report covers six months of effort, including startup time. Five projects were supported by the division: Pilot Program for the Risk-Based Surveillance of Lung Cancer in Los Alamos National Laboratory Workers, Optimization of Placement of Workplace Continuous Air Monitoring Instrumentation, A Polymeric Barrier Monitor to Protect Workers, Evaluation of a Real-Time Beryllium Detection Instrument and the Implications of Its Use, and High-Energy Dosimetry. A project summary for each is provided. An appendix to the report includes the 1995 Request for Proposals, Committee Members, Priority Technical Areas of Interest for FY95, Relative Prioritization and Weighting Factors, Format for Proposals, and Charter.

Technology Development, Evaluation, and Application (TDEA) FY 1995 progress report - Environmental, Safety, and Health (ESH) division

International Nuclear Information System (INIS)

Andrews, L.L.

1996-09-01

This report covers six months of effort, including startup time. Five projects were supported by the division: Pilot Program for the Risk-Based Surveillance of Lung Cancer in Los Alamos National Laboratory Workers, Optimization of Placement of Workplace Continuous Air Monitoring Instrumentation, A Polymeric Barrier Monitor to Protect Workers, Evaluation of a Real-Time Beryllium Detection Instrument and the Implications of Its Use, and High-Energy Dosimetry. A project summary for each is provided. An appendix to the report includes the 1995 Request for Proposals, Committee Members, Priority Technical Areas of Interest for FY95, Relative Prioritization and Weighting Factors, Format for Proposals, and Charter

The diversity of waste disposal planning in Switzerland

International Nuclear Information System (INIS)

McCombie, C.

1989-01-01

In this overview of radioactive waste disposal planning in Switzerland, emphasis is placed upon describing the diversity of the planning and explaining the strategic thinking which has resulted in this diversity. Although Switzerland is a small country and has only a modest nuclear programme in absolute terms, planning and preparation for final disposal projects has been progressing for the last 10 or more years on a very broad front. The reasons for this breadth of approach are partly technical and partly determined by political and public pressures. Following a summary of the requirements for disposal and of the relevant boundary conditions, the resulting concepts are described and the controversial issue of repository siting is discussed. The current status of projects for disposal of low and intermediate-level wastes (L/ILW) and of high-level wastes (HLW) is noted; we conclude with some remarks on the advantages and disadvantages from the side of the organization responsible for implementation of repository projects of proceeding on such a broad technical front. (aughor). 2 figs.; 1 tab

InterProScan Result: FY040353 [KAIKOcDNA[Archive

Lifescience Database Archive (English)

Full Text Available FY040353 FY040353_5_ORF1 5F3C43B91532A0C1 PANTHER PTHR21347 CLEFT LIP AND PALATE ASSOCIATED TRANSME...MBRANE PROTEIN-RELATED 2.9e-112 T IPR008429 Cleft lip and palate transmembrane 1 ...

Pilot chargeback system program plan

International Nuclear Information System (INIS)

Smith, P.

1997-03-01

This planning document outlines the steps necessary to develop, test, evaluate, and potentially implement a pilot chargeback system at the Idaho National Engineering and Environmental Laboratory for the treatment, storage, and disposal of current waste. This pilot program will demonstrate one system that can be used to charge onsite generators for the treatment and disposal of low-level radioactive waste. In FY 1997, mock billings will begin by July 15, 1997. Assuming approvals are received to do so, FY 1998 activities will include modifying the associated automated systems, testing and evaluating system performance, and estimating the amount generators will spend for waste storage, treatment, and disposal in FY 1999. If the program is fully implemented in FY 1999, generators will pay actual, automated bills for waste management services from funds transferred to their budgets from Environmental Management

LFCM [liquid-fed ceramic melter] vitrification technology: Quarterly progress report, January--March 1987

International Nuclear Information System (INIS)

Brouns, R. A.; Allen, C. R.; Powell, J. A.

1988-05-01

This report is compiled by the Nuclear Waste Treatment Program and the Hanford Waste Vitrification Program at Pacific Northwest Laboratory to describe the progress in developing, testing, applying and documenting liquid-fed ceramic melter vitrification technology. Progress in the following technical subject areas during the second quarter of FY 1987 is discussed: melting process chemistry and glass development, feed preparation and transfer systems, melter systems, canister filling and handling systems, and process/product modeling. 23 refs., 14 figs., 10 tabs

The development and status of performance assessment in radioactive waste disposal

International Nuclear Information System (INIS)

McCombie, C.; Papp, T.; Coplan, S.

1990-01-01

The development of formal performance assessment in radioactive waste disposal has been in progress for around 10-15 years now. The time is particularly opportune for a review of the state-of-the-art because of current changes in the status of repository planning and implementation world-wide. Several major feasibility-type studies have been completed, the first full site-specific safety analyses are being performed for engineered underground disposal facilities for L/ILW, and - for HLW - the die are now being cast by implementers and regulators determining how the safety analyses for licensing are to be performed and assessed. This introductory paper reviews the development of performance assessment, including a reiteration of the aims and a recapitulation of the technical progress and achievements to date. The most important purpose, however, is to identify some key issues occupying safety analysts and regulatory reviewers involved in waste disposal today. The objective is to present the generally accepted consensus on the state of the art in performance assessment. 40 refs., 2 figs

Department of Defense Manpower Requirements Report, FY 1985. Volume III. Force Readiness Report.

Science.gov (United States)

1984-02-01

normally on a reimburs - able basis unless they support the mission of DoD. The Army Reserve increase in FY 1985 is a result of increased support of...Normally, such cross assignment is made on a reimbursable basis. Navy Federal Agency Support Manpower (End Strength in Thousands) FY 83 FY 84 FY 85 (Actual... reimburses the Air Force Industrial Funds for depot maintenance costs with the exception of military personnel costs. For items procured from the Stock

Accelerator/Experiment Operations - FY 2016

International Nuclear Information System (INIS)

Blake, A.; Convery, M.; Geer, S.; Geesaman, D.; Harris, D.; Johnson, D.; Lang, K.; McFarland, K.; Messier, M.; Moore, C. D.; Newhart, D.; Reimer, P. E.; Plunkett, R.; Rominsky, M.; Sanchez, M.; Schmidt, J. J.; Shanahan, P.; Tate, C.; Thomas, J.; Donatella Torretta, Donatella Torretta; Matthew Wetstein, Matthew Wetstein

2016-01-01

This Technical Memorandum summarizes the Fermilab accelerator and experiment operations for FY 2016. It is one of a series of annual publications intended to gather information in one place. In this case, the information concerns the FY 2016 NOvA, MINOS+ and MINERvA experiments using the Main Injector Neutrino Beam (NuMI), the MicroBooNE experiment and the activities in the SciBooNE Hall using the Booster Neutrino Beam (BNB), and the SeaQuest experiment, LArIAT experiment and Meson Test Beam activities in the 120 GeV external switchyard beam (SY120). Each section was prepared by the relevant authors, and was then edited for inclusion in this summary.

Accelerator/Experiment Operations - FY 2016

Energy Technology Data Exchange (ETDEWEB)

Blake, A. [Argonne National Lab. (ANL), Argonne, IL (United States); Convery, M. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Geer, S. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Geesaman, D. [Argonne National Lab. (ANL), Argonne, IL (United States); Harris, D. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Johnson, D. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Lang, K. [Argonne National Lab. (ANL), Argonne, IL (United States); McFarland, K. [Argonne National Lab. (ANL), Argonne, IL (United States); Messier, M. [Argonne National Lab. (ANL), Argonne, IL (United States); Moore, C. D. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Newhart, D. [Fermilab; Reimer, P. E. [Argonne; Plunkett, R. [Fermilab; Rominsky, M. [Fermilab; Sanchez, M. [Iowa State U.; Schmidt, J. J. [Fermilab; Shanahan, P. [Fermilab; Tate, C. [Fermilab; Thomas, J. [University Coll. London; Donatella Torretta, Donatella Torretta [Fermilab; Matthew Wetstein, Matthew Wetstein [Iowa State University

2016-10-01

This Technical Memorandum summarizes the Fermilab accelerator and experiment operations for FY 2016. It is one of a series of annual publications intended to gather information in one place. In this case, the information concerns the FY 2016 NOvA, MINOS+ and MINERvA experiments using the Main Injector Neutrino Beam (NuMI), the MicroBooNE experiment and the activities in the SciBooNE Hall using the Booster Neutrino Beam (BNB), and the SeaQuest experiment, LArIAT experiment and Meson Test Beam activities in the 120 GeV external switchyard beam (SY120). Each section was prepared by the relevant authors, and was then edited for inclusion in this summary.

Study on the development of safety regulations for geological disposal of high-level radioactive waste

International Nuclear Information System (INIS)

Wei Fangxin

2012-01-01

The development of regulations under Regulations on Safety Management of Radioactive Waste has become necessary as the issuance of it. The regulations related to geological disposal of high-level radioactive waste can promote the progress of research and development on geological disposal of high-level radioactive waste in China. This paper has present suggestions on development of regulations on geological disposal of high-level radioactive waste by analyzing development of safety regulations on geological disposal of high-level radioactive waste in foreign countries and problems occurred in China and discussed important issues related to the development of safety regulations on geological disposal of high-level radioactive waste. (author)

Voluntary research results for five years along the master plan on nuclear safety research. FY 2001 - 2005

International Nuclear Information System (INIS)

Sato, Yoshinori

2006-05-01

Safety Research has been conducted from FY 2001 to FY 2005 according to the Master Plan on Nuclear Safety Research (FY 2001-2005) in Japan Atomic Energy Agency which took over former Japan Nuclear Cycle Development Institute. This report shows the voluntary research results for five years conducted from FY 2001 to FY 2005 according to the Master Plan on Nuclear Safety Research (FY 2001-2005). (author)

Nevada Test Site-Directed Research, Development, and Demonstration. FY2005 report

Energy Technology Data Exchange (ETDEWEB)

Lewis, Will [comp.

2006-09-01

The Nevada Test Site-Directed Research, Development, and Demonstration (SDRD) program completed a very successful year of research and development activities in FY 2005. Fifty new projects were selected for funding this year, and five FY 2004 projects were brought to conclusion. The total funds expended by the SDRD program were $5.4 million, for an average per project cost of just under $100,000. Two external audits of SDRD accounting practices were conducted in FY 2005. Both audits found the program's accounting practices consistent with the requirements of DOE Order 413.2A, and one included the observation that the NTS contractor ''did an exceptional job in planning and executing year-start activities.'' Highlights for the year included: the filing of 18 invention disclosures for intellectual property generated by FY 2005 projects; programmatic adoption of 17 FY 2004 SDRD-developed technologies; participation in the tri-lab Laboratory Directed Research and Development (LDRD) and SDRD program review that was broadly attended by NTS, NNSA, LDRD, and U.S. Department of Homeland Security representatives; peer reviews of all FY 2005 projects; and the successful completion of 55 R&D projects, as presented in this report.

Research on deep electromagnetic induction methods (Fy 1985)

Energy Technology Data Exchange (ETDEWEB)

Murakami, Hiroshi; Uchida, Toshihiro; Tanaka, Shin' ichi

1987-06-01

Geological Survey of Japan started from FY 1984 a research of deep electomagnetic induction methods as a part of the research on deep geothermal resources prospecting technology, the Sunshine Project. This article is the report of its second fiscal year. These methods are a generic term of the methods to survey specific resistance structure in the deep part of the earth by utilizing the technique of the electromagnetic induction method and the time domain CSMT method aiming to survey about estimated depth of 5Km as well as the CA method to estimate the general structure of the earth of the depth of 5Km or more are now being developed. This article reports the respective methods separately. Concerning the former, the reception of useful signals were successfully made during the FY 1984 field experiment and based on this, field experiments in a geothermal area were conducted in FY 1985 verifying its effectivenss. With regard to the latter, following FY 1984, CA observations were conducted in the northern part of Tohoku Region and the deep specific resistance structure in a wide area was surveyed. (43 figs, 1 tab, 11 refs)

LANL C10.2 Projects in FY13

International Nuclear Information System (INIS)

Batha, Steven H.; Fincke, James R.; Schmitt, Mark J.

2012-01-01

LANL has two projects in C10.2: Defect-Induced Mix Experiment (DIME) (ongoing, several runs at Omega; NIF shots this summer); and Shock/Shear (tested at Omega for two years; NIF shots in second half of FY13). Each project is jointly funded by C10.2, other C10 MTEs, and Science Campaigns. DIME is investigating 4π and feature-induced mix in spherically convergent ICF implosions by using imaging of the mix layer. DIME prepared for NIF by demonstrating its PDD mix platform on Omega including imaging mid-Z doped layers and defects. DIME in FY13 will focus on PDD symmetry-dependent mix and moving burn into the mix region for validation of mix/burn models. Re-Shock and Shear are two laser-driven experiments designed to study the turbulent mixing of materials. In FY-2012 43 shear and re-shock experimental shots were executed on the OMEGA laser and a complete time history obtained for both. The FY-2013 goal is to transition the experiment to NIF where the larger scale will provide a longer time period for mix layer growth.

Conceptual design study of fusion experimental reactor (FY86 FER)

International Nuclear Information System (INIS)

Saito, Ryusei; Kashihara, Shin-ichiro; Itoh, Shin-ichi

1987-08-01

This report describes the results of conceptual design study on plant systems for the Fusion Experimental Reactor (FY86 FER). Design studies for FER plant systems have been continued from FY85, especially for design modifications made in accordance with revisions of plasma scaling parameters and system improvements. This report describes 1) system construction, 2) site and reactor building plan, 3) repaire and maintenance system, 4) tritium circulation system, 5) heating, ventilation and air conditioning system, 6) tritium clean-up system, 7) cooling and baking system, 8) waste treatment and storage system, 9) control system, 10) electric power system, 11) site factory plan, all of which are a part of FY86 design work. The plant systems described in this report generally have been based on the FY86 FER (ACS Reactor) which is an one of the six candidates for FER. (author)

Final disposal of nuclear waste. An investigated issue

International Nuclear Information System (INIS)

Palmu, J.; Nikula, A.

1996-01-01

Since 1978, the nuclear power companies have co-ordinated joint studies of nuclear waste disposal through the Nuclear Waste Commission of Finnish Power Companies. The studies are done primarily to gather basic data, with a view to implementing nuclear waste management in a safe, economical and timely way. The power companies' research, development and design work with regard to nuclear waste has been progressing according to the schedule set by the Government, and Finland has received international recognition for its advanced nuclear waste management programme. Last year, the nuclear power companies set up a joint company, Posiva Oy, to manage the final disposal of spent uranium fuel. (orig.)

1992 annual report on low-level radioactive waste management progress

International Nuclear Information System (INIS)

1993-11-01

This report summarizes the progress States and compact regions made during 1992 in establishing new low-level radioactive waste disposal facilities. It also provides summary information on the volume of low-level radioactive waste received for disposal in 1992 by commercially operated low-level radioactive waste disposal facilities. This report is in response to section 7 (b) of the Low-Level Radioactive Waste Policy Act

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

International Nuclear Information System (INIS)

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

1991-07-01

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

Thermal analysis in the near field for geological disposal of high-level radioactive waste. Establishment of the disposal tunnel spacing and waste package pitch on the 2nd progress report for the geological disposal of HLW in Japan

International Nuclear Information System (INIS)

Taniguchi, Wataru; Iwasa, Kengo

1999-11-01

For the underground facility of the geological disposal of high-level radioactive waste (HLW), the space is needed to set the engineered barrier, and the set engineered barrier and rock-mass of near field are needed to satisfy some conditions or constraints for their performance. One of the conditions above mentioned is thermal condition arising from heat outputs of vitrified waste and initial temperature at the disposal depth. Hence, it is needed that the temperature of the engineered barrier and rock mass is less degree than the constraint temperature of each other. Therefore, the design of engineered barrier and underground facility is conducted so that the temperature of the engineered barrier and rock mass is less degree than the constraint temperature of each other. One of these design is establishment of the disposal tunnel spacing and waste package pitch. In this report, thermal analysis is conducted to establish the disposal tunnel spacing and waste package pitch to satisfy the constraint temperature in the near field. Also, other conditions or constraints for establishment of the disposal tunnel spacing and waste package pitch are investigated. Then, design of the disposal tunnel spacing and waste package pitch, considering these conditions or constraints, is conducted. For the near field configuration using the results of the design above mentioned, the temperature with time dependency is studied by analysis, and then the temperature variation due to the gaps, that will occur within the engineered barrier and between the engineered barrier and rock mass in setting engineered barrier in the disposal tunnel or pit, is studied. At last, the disposal depth variation is studied to satisfy the temperature constraint in the near field. (author)

Competence in confirming correct placement of nasogastric feeding tubes amongst FY1 doctors

OpenAIRE

Lee, Sindy; Mason, Eleanor

2013-01-01

Foundation year one (FY1) doctors are required to confirm correct placement of nasogastric (NG) feeding tubes on chest radiography on a regular basis. Many FY1s do not receive formal training during medical school or during the FY1 year. Multiple incidents of harm to patients, including death, resulting from incorrect placement of an NG feeding tube have been reported to the National Patient Safety Agency (NPSA) since 2005. Our audit assessed the confidence and knowledge of FY1 doctors in cor...

Current status and future plans of R and D on geological disposal of HLW in Japan

International Nuclear Information System (INIS)

Sasaki, Noriaki

1994-01-01

As to the final disposal of HLW, it is considered highly important to provide a clear distinction between implementation of disposal and the research and development as independent processes, and to increase the transparency of the overall disposal program by defining concrete schedules and the roles and responsibilities of the organizations involved. The Power Reactor and Nuclear Fuel Development Corporation (PNC) has being conducted research and development on the geological disposal of HLW, as the leading organization. The responsibility of PNC is to ensure smooth progress of research and development project and to carry out studies of geological environment. The role of the Japanese government is to take overall responsibilities for appropriate and steady implementations of the program, as well as enacting any laws or policies required. On the other hand, electricity supply utilities are responsible to secure necessary funds for disposal, and in accordance with their role as waste producers, they are expected to cooperate even at the stage of research and development. Fundamental features of research and development of PNC carried out at this stage are as follows; (1) Generic research and development, (2) To establish scientific and technical bases of geological isolation of HLW in Japan, (3) About 15 years program from 1989 with documentation of progress reports, (4) Approach from near-field to far-field. PNC summarized the findings obtained by 1991, and submitted a document (H3 Report) in September 1992 as the first progress report. H3 Report is the first and comprehensive technical report on geological disposal of HLW in Japan, and provides information for the public to find out the current status of the research and development. This paper reviews the conclusions of H3 Report, overall procedures and schedule for implementing geological disposal, and future plans of R and D in PNC. (J.P.N.)

Theoretical Division annual report, FY 1975. [LASL

Energy Technology Data Exchange (ETDEWEB)

Carruthers, P.A.

1976-02-01

This report presents an overview of the activities in the Theoretical Division and a summary of research highlights during FY 1975. It is intended to inform a wide audience about the theoretical work of the LASL and, therefore, contains introductory material which places recent advances in a broader context. The report is organized into two special interest reports: reactor safety research and the Advanced Research Committee, and 11 reports from the T-Division group leaders on the work of their respective groups. Main interests and responsibilities are outlined including the relationship of the group's work to the work of other T-Division groups and other divisions at the Laboratory. The description of research highlights for FY 1975 explains in a fairly simple, straightforward manner the major recent advances and their significance. Each group report is followed by a publication list for FY 1975 (330 references) and a list of talks given outside the Laboratory (140 references). 29 figures. (auth)

Argillite And Crystalline Disposal Research: Accomplishments And Path-Forward.

Energy Technology Data Exchange (ETDEWEB)

McMahon, Kevin A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Jove-Colon, Carlos F. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Wang, Yifeng [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2016-09-01

The intention of this document is to provide a path-forward for research and development (R&D) for two host rock media-specific (argillite and crystalline) disposal research work packages within the Used Fuel Disposition Campaign (UFDC). The two work packages, Argillite Disposal R&D and Crystalline Disposal R&D, support the achievement of the overarching mission and objectives of the Department of Energy Office of Nuclear Energy Fuel Cycle Technologies Program. These two work packages cover many of the fundamental technical issues that will have multiple implications to other disposal research work packages by bridging knowledge gaps to support the development of the safety case. The path-forward begins with the assumption of target dates that are set out in the January 2013 DOE Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste (http://energy.gov/downloads/strategy-management-and-disposal-used-nuclear-fuel-and-high-levelradioactive- waste). The path-forward will be maintained as a living document and will be updated as needed in response to available funding and the progress of multiple R&D tasks in the Used Fuel Disposition Campaign and the Fuel Cycle Technologies Program. This path forward is developed based on the report of “Used Fuel Disposition Campaign Disposal Research and Development Roadmap (FCR&D-USED- 2011-000065 REV0)” (DOE, 2011). This document delineates the goals and objectives of the UFDC R&D program, needs for generic disposal concept design, and summarizes the prioritization of R&D issues.

Hanford Waste Vitrification Plant technology progress

International Nuclear Information System (INIS)

Wolfe, B.A.; Scott, J.L.; Allen, C.R.

1989-10-01

The Hanford Waste Vitrification Plant (HWVP) is currently being designed to safely process and temporarily store immobilized defense liquid high-level wastes from the Hanford Site. These wastes will be immobilized in a borosilicate glass waste form in the HWVP and stored onsite until a qualified geologic waste repository is ready for permanent disposal. Because of the diversity of wastes to be disposed of, specific technical issues are being addressed so that the plant can be designed and operated to produce a waste form that meets the requirements for permanent disposal in a geologic repository. This paper reports the progress to date in addressing these issues. 2 figs., 3 tabs

InterProScan Result: FY741994 [KAIKOcDNA[Archive

Lifescience Database Archive (English)

Full Text Available FY741994 FY741994_2_ORF2 D0306AF64002633E PFAM PF00067 p450 7e-14 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

Consolidation Process for FY 1997 Financial Statements for Other Defense Organizations

National Research Council Canada - National Science Library

1998-01-01

... to prepare consolidated financial statements for FY 1996 and each succeeding year. The DoD Consolidated Financial Statements for FY 1997 include financial statements for a reporting entity entitled "Other Defense Organizations...

Evaluation of gas-phase technetium decontamination and safety related experiments during FY 1994. A report of work in progress

Energy Technology Data Exchange (ETDEWEB)

Simmons, D.W.; Munday, E.B.

1995-05-01

Laboratory activities for FY94 included: evaluation of decontamination of Tc by gas-phase techniques, evaluation of diluted ClF{sub 3} for removing U deposits, evaluation of potential hazard of wet air inlekage into a vessel containing ClF{sub 3}, planning and preparation for experiments to assess hazard of rapid reaction of ClF{sub 3} and hydrated UO{sub 2}F{sub 2} or powdered Al, and preliminary evaluation of compatibility of Tenic valve seat material.

Department of Defense Strategic Sustainability Performance Plan FY 2012

Science.gov (United States)

2012-01-01

interoperability of equipment; and the management and oversight of contingency basing. Improved contingency base sustainability will also enhance mission...with communicating classified information from alternate work locations. In FY 2011, NGA developed and began implementing a telecommuting policy...operating procedures. DLA Disposition Services strengthened its oversight of the electronics demanufacturing process in FY 2011 by tightening

InterProScan Result: FY752086 [KAIKOcDNA[Archive

Lifescience Database Archive (English)

Full Text Available FY752086 FY752086_4_ORF1 883389819CEEC6A6 PFAM PF00067 p450 2.3e-25 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

InterProScan Result: FY748470 [KAIKOcDNA[Archive

Lifescience Database Archive (English)

Full Text Available FY748470 FY748470_1_ORF2 6597395FD817F217 PFAM PF00067 p450 1.3e-05 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

InterProScan Result: FY005565 [KAIKOcDNA[Archive

Lifescience Database Archive (English)

Full Text Available FY005565 FY005565_1_ORF1 21201BC324E6CE7F PFAM PF00067 p450 6.2e-17 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

FY 1989 report on the section meeting of gasification technology of the Coal Gasification Committee; 1989 nendo sekitan gasuka iinkai gasuka gijutsu bukai hokokusho

Energy Technology Data Exchange (ETDEWEB)

NONE

1990-03-01

The paper reported activities of the Coal Gasification Committee in FY 1989. The 1st Coal Gasification Committee Meeting was held on July 21,1989, and report/discussion were made about an outline of the FY 1989 research plan. In the 2nd Meeting, report/discussion were made about activities of each of the section meetings and the progress of the development of coal gasification technology. In FY 1998, as the 4th design/construction of pilot plant, manufacture/installation were conducted of a part (equipment of coal supply system/char recycle system) of the gasification process equipment/facilities. As to recycle gas facilities, manufacture of equipment/facilities was conducted. Concerning a part of the pipe rack/central control panel/electric panel, manufacture/installation of equipment were made. In the support study of a pilot plant (trial development of materials for plant use equipment), refractory was studied in terms of the evaluation of durability of furnace materials against liquefaction residue slag, study of furnace materials responsive to liquefaction residue and gasification of high ash melting point coal, etc. (NEDO)

FY 1999 annual work plan for infrastructure program WBS 6

Energy Technology Data Exchange (ETDEWEB)

Donley, C.D.

1998-08-27

The Fiscal Year (FY) 1999 DynCorp Annual Work Plan (AWP) relates DOE-RL work breakdown structure (WBS) to Cost Accounts and to Organizational Structure. Each Cost Account includes a workscope narrative and justification performance and service standards, goals, and deliverables. Basis of estimates are included within each Cost Account to demonstrate the relationship of budget to defined workscope. The FY 1999 AWP reflects the planning assumptions and initiatives that are included in the PHMC Strategic Plan for Infrastructure Optimization which was established in FY 1998. Development of the FY 1999 AWP was in accordance with a sequential series of events and efforts described in the Infrastructure Annual Work Planning and Budget Cycle which was developed and established in conjunction with the Strategic Plan. The Strategic Plan covers a rolling five year span of time and is updated at the start of each fiscal year as the beginning of the annual work planning and budget cycle for the following fiscal year. Accordingly the planning for the FY 1999 AWP began in January 1998. Also included in the annual work planning and budget cycle, and the basis for the budget in this AWP, is the development of a requirements-based budget.

Post-disposal safety assessment of toxic and radioactive waste: waste types, disposal practices, disposal criteria, assessment methods and post-disposal impacts

International Nuclear Information System (INIS)

Torres, C.; Simon, I.; Little, R.H.; Charles, D.; Grogan, H.A.; Smith, G.M.; Sumerling, T.J.; Watkins, B.M.

1993-01-01

The need for safety assessments of waste disposal stems not only from the implementation of regulations requiring the assessment of environmental effects, but also from the more general need to justify decisions on protection requirements. As waste-disposal methods have become more technologically based, through the application of more highly engineered design concepts and through more rigorous and specific limitations on the types and quantities of the waste disposed, it follows that assessment procedures also must become more sophisticated. It is the overall aim of this study to improve the predictive modelling capacity for post-disposal safety assessments of land-based disposal facilities through the development and testing of a comprehensive, yet practicable, assessment framework. This report records all the work which has been undertaken during Phase 1 of the study. Waste types, disposal practices, disposal criteria and assessment methods for both toxic and radioactive waste are reviewed with the purpose of identifying those features relevant to assessment methodology development. Difference and similarities in waste types, disposal practices, criteria and assessment methods between countries, and between toxic and radioactive wastes are highlighted and discussed. Finally, an approach to identify post-disposal impacts, how they arise and their effects on humans and the environment is described

Decontamination and decommissioning activities photobriefing book FY 1998

International Nuclear Information System (INIS)

1999-01-01

Fiscal Year (FY) 1998 was very successful in terms of Decontamination and Decommissioning (D and D) project completions. This photobriefing book highlights these projects and activities in one ongoing project. Brief descriptions of projects planned for the future are also provided. Two D and D projects funded by the US DOE Office of Environmental Management (EM-40) were completed safely and on schedule in FY 1998: (1) Argonne Thermal Source Reactor (ATSR) was a low-power research reactor that operated from 1950 to 1989; and (2) The Building 594 (a.k.a. 579) Waste Ion-Exchange Facility was an obsolete facility constructed in the 1950s to process waste fluids from a collecting lagoon. Field work at one project was ongoing during FY 1998: (1) Chicago Pile 5 (CP-5) was a 5-megawatt, heavy water-moderated, enriched uranium-fueled reactor used to produce neutrons for scientific research from 1954-79. The reactor was shut down and defueled in 1979. D and D is scheduled to be completed in FY 2000. Project experience has lent itself to developing unique staff capabilities. The D and D group was chosen as lead organization for a project supported with operating funds provided by Argonne's Plant Facilities and Services (PFS) Division. This project was also completed safely and on schedule in FY 1998: (1) The Building 200/205 Pneumatic Transfer Tube was constructed in the late 1960s between Hot Cell M-4 in Building 200 and a glove box in Room F-131, Building 205, and used to transfer irradiated fuel specimens and other samples between the two buildings

Tanks Focus Area Site Needs Assessment - FY 2001

Energy Technology Data Exchange (ETDEWEB)

Allen, Robert W.; Josephson, Gary B.; Westsik, Joseph H.; Nickola, Cheryl L.

2001-04-30

The TFA uses a systematic process for developing its annual program that draws from the tanks science and technology development needs expressed by the five DOE tank waste sites. TFA's annual program development process is iterative and involves the following steps: Collection of site needs; Needs analysis; Development of technical responses and initial prioritization; Refinement of the program for the next fiscal year; Formulation of the Corporate Review Budget (CRB); Preparation of Program Execution Guidance (PEG) for the next FY Revision of the Multiyear Program Plan (MYPP). This document describes the outcomes of the first phase of this process, from collection of site needs to the initial prioritization of technical activities. The TFA received site needs in October - December 2000. A total of 170 site needs were received, an increase of 30 over the previous year. The needs were analyzed and integrated, where appropriate. Sixty-six distinct technical responses were drafted and prioritized. In addition, seven strategic tasks were approved to compete for available funding in FY 2002 and FY 2003. Draft technical responses were prepared and provided to the TFA Site Representatives and the TFA User Steering Group (USG) for their review and comment. These responses were discussed at a March 15, 2001, meeting where the TFA Management Team established the priority listing in preparation for input to the DOE Office of Science and Technology (OST) budget process. At the time of publication of this document, the TFA continues to finalize technical responses as directed by the TFA Management Team and clarify the intended work scopes for FY 2002 and FY 2003.

Caffeine's impairment of insulin-mediated glucose disposal cannot be solely attributed to adrenaline in humans

DEFF Research Database (Denmark)

Battram, D S; Graham, T E; Dela, F

2007-01-01

Caffeine (CAF) impedes insulin-mediated glucose disposal (IMGD) and increases plasma adrenaline concentrations ([ADR]; 0.6 nm). While the antagonism of ADR abolishes the CAF effect, infusion of ADR (0.75 nm) has no effect on IMGD. We have now examined CAF and ADR in concert to determine whether...

FY 2008 Public Libraries Survey

Data.gov (United States)

Institute of Museum and Library Services — Dig into FY 2008 data on public library systems (referred to as administrative entities in the Public Libraries Survey) and main libraries, branches, and bookmobiles...

FY 2010 Public Libraries Survey

Data.gov (United States)

Institute of Museum and Library Services — Dig into FY 2010 data on public library systems (referred to as administrative entities in the Public Libraries Survey) and main libraries, branches, and bookmobiles...

FY 2011 Public Libraries Survey

Data.gov (United States)

Institute of Museum and Library Services — Dig into FY 2011 data on public library systems (referred to as administrative entities in the Public Libraries Survey) and main libraries, branches, and bookmobiles...

FY 2009 Public Libraries Survey

Data.gov (United States)

Institute of Museum and Library Services — Dig into FY 2009 data on public library systems (referred to as administrative entities in the Public Libraries Survey) and main libraries, branches, and bookmobiles...

Disposal systems evaluations and tool development : Engineered Barrier System (EBS) evaluation.

Energy Technology Data Exchange (ETDEWEB)

Rutqvist, Jonny (LBNL); Liu, Hui-Hai (LBNL); Steefel, Carl I. (LBNL); Serrano de Caro, M. A. (LLNL); Caporuscio, Florie Andre (LANL); Birkholzer, Jens T. (LBNL); Blink, James A. (LLNL); Sutton, Mark A. (LLNL); Xu, Hongwu (LANL); Buscheck, Thomas A. (LLNL); Levy, Schon S. (LANL); Tsang, Chin-Fu (LBNL); Sonnenthal, Eric (LBNL); Halsey, William G. (LLNL); Jove-Colon, Carlos F.; Wolery, Thomas J. (LLNL)

2011-01-01

Evaluation Framework (DSEF). This report will focus on the multi-barrier concept of EBS and variants of this type which in essence is the most adopted concept by various repository programs. Empasis is given mainly to the evaluation of EBS materials and processes through the analysis of published studies in the scientific literature of past and existing repository research programs. Tool evaluations are also emphasized, particularly on THCM processes and chemical equilibria. Although being an increasingly important aspect of NW disposition, short-term or interim storage of NW will be briefly discussed but not to the extent of the EBS issues relevant to disposal systems in deep geologic environments. Interim storage will be discussed in the report Evaluation of Storage Concepts FY10 Final Report (Weiner et al. 2010).

Disposal systems evaluations and tool development: Engineered Barrier System (EBS) evaluation

International Nuclear Information System (INIS)

Rutqvist, Jonny; Liu, Hui-Hai; Steefel, Carl I.; Serrano de Caro, M.A.; Caporuscio, Florie Andre; Birkholzer, Jens T.; Blink, James A.; Sutton, Mark A.; Xu, Hongwu; Buscheck, Thomas A.; Levy, Schon S.; Tsang, Chin-Fu; Sonnenthal, Eric; Halsey, William G.; Jove-Colon, Carlos F.; Wolery, Thomas J.

2011-01-01

Evaluation Framework (DSEF). This report will focus on the multi-barrier concept of EBS and variants of this type which in essence is the most adopted concept by various repository programs. Empasis is given mainly to the evaluation of EBS materials and processes through the analysis of published studies in the scientific literature of past and existing repository research programs. Tool evaluations are also emphasized, particularly on THCM processes and chemical equilibria. Although being an increasingly important aspect of NW disposition, short-term or interim storage of NW will be briefly discussed but not to the extent of the EBS issues relevant to disposal systems in deep geologic environments. Interim storage will be discussed in the report Evaluation of Storage Concepts FY10 Final Report (Weiner et al. 2010).

Library Systems: FY 1992-2012 Public Libraries Survey Trends (Administrative Entity)

Data.gov (United States)

Institute of Museum and Library Services — Find key information on trends in library systems around the United States from FY 1992 to FY 2012.These data include imputed values for libraries that did not...

New York's response to the national LLRW disposal legislation

International Nuclear Information System (INIS)

Orazio, A.F.; Schwarz, W.F.; Feeney, A.X.

1988-01-01

The Federal Low Level Radioactive Waste Policy Act (LLRWPA) and its amendments brought about a shift from commercial responsibility to state responsibility for low level radioactive waste (LLRW) disposal. This shift required New York to evaluate various policy options for handling its new LLRW disposal responsibility. After passage of the 1980 Federal Act, New York participated in efforts which resulted in a proposed interstate compact in the Northeast. Following a review of the proposed compact, as well as other options, New York decided to assume by itself full responsibility for disposing of its LLRW. In July 1986, New York enacted the New York State LLRW Management Act. This act provides New York with a detailed plan for establishing a LLWR disposal facility by the 1993 federal deadline. This paper consists of two segments. The first describes the major provisions of the State Act assigning responsibilities to the various agencies involved and reports on their progress. The second segment discusses the current activities of those involved in implementing the State Act with an emphasis on the recent and future activities of the Siting Commission

Lead Slowing-Down Spectrometry for Spent Fuel Assay: FY11 Status Report

International Nuclear Information System (INIS)

Warren, Glen A.; Casella, Andrew M.; Haight, R.C.; Anderson, Kevin K.; Danon, Yaron; Hatchett, D.; Becker, Bjorn; Devlin, M.; Imel, G.R.; Beller, D.; Gavron, A.; Kulisek, Jonathan A.; Bowyer, Sonya M.; Gesh, Christopher J.; O'Donnell, J.M.

2011-01-01

Executive Summary Developing a method for the accurate, direct, and independent assay of the fissile isotopes in bulk materials (such as used fuel) from next-generation domestic nuclear fuel cycles is a goal of the Office of Nuclear Energy, Fuel Cycle R and D, Material Protection and Control Technology (MPACT) Campaign. To meet this goal, MPACT supports a multi-institutional collaboration to study the feasibility of Lead Slowing Down Spectroscopy (LSDS). This technique is an active nondestructive assay method that has the potential to provide independent, direct measurement of Pu and U isotopic masses in used fuel with an uncertainty considerably lower than the approximately 10% typical of today's confirmatory assay methods. This document is a progress report for FY2011 collaboration activities. Progress made by the collaboration in FY2011 continues to indicate the promise of LSDS techniques applied to used fuel. PNNL developed an empirical model based on calibration of the LSDS to responses generated from well-characterized used fuel. The empirical model demonstrated the potential for the direct and independent assay of the sum of the masses of 239Pu and 241Pu to within approximately 3% over a wide used fuel parameter space. Similar results were obtained using a perturbation approach developed by LANL. Benchmark measurements have been successfully conducted at LANL and at RPI using their respective LSDS instruments. The ISU and UNLV collaborative effort is focused on the fabrication and testing of prototype fission chambers lined with ultra-depleted 238U and 232Th, and uranium deposition on a stainless steel disc using spiked U3O8 from room temperature ionic liquid was successful, with improving thickness obtained. In FY2012, the collaboration plans a broad array of activities. PNNL will focus on optimizing its empirical model and minimizing its reliance on calibration data, as well continuing efforts on developing an analytical model. Additional measurements are

HLA-DRB1*15:01-DQA1*01:02-DQB1*06:02 Haplotype Protects Autoantibody-Positive Relatives From Type 1 Diabetes Throughout the Stages of Disease Progression.

Science.gov (United States)

Pugliese, Alberto; Boulware, David; Yu, Liping; Babu, Sunanda; Steck, Andrea K; Becker, Dorothy; Rodriguez, Henry; DiMeglio, Linda; Evans-Molina, Carmella; Harrison, Leonard C; Schatz, Desmond; Palmer, Jerry P; Greenbaum, Carla; Eisenbarth, George S; Sosenko, Jay M

2016-04-01

The HLA-DRB1*15:01-DQA1*01:02-DQB1*06:02 haplotype is linked to protection from the development of type 1 diabetes (T1D). However, it is not known at which stages in the natural history of T1D development this haplotype affords protection. We examined a cohort of 3,358 autoantibody-positive relatives of T1D patients in the Pathway to Prevention (PTP) Study of the Type 1 Diabetes TrialNet. The PTP study examines risk factors for T1D and disease progression in relatives. HLA typing revealed that 155 relatives carried this protective haplotype. A comparison with 60 autoantibody-negative relatives suggested protection from autoantibody development. Moreover, the relatives with DRB1*15:01-DQA1*01:02-DQB1*06:02 less frequently expressed autoantibodies associated with higher T1D risk, were less likely to have multiple autoantibodies at baseline, and rarely converted from single to multiple autoantibody positivity on follow-up. These relatives also had lower frequencies of metabolic abnormalities at baseline and exhibited no overall metabolic worsening on follow-up. Ultimately, they had a very low 5-year cumulative incidence of T1D. In conclusion, the protective influence of DRB1*15:01-DQA1*01:02-DQB1*06:02 spans from autoantibody development through all stages of progression, and relatives with this allele only rarely develop T1D. © 2016 by the American Diabetes Association. Readers may use this article as long as the work is properly cited, the use is educational and not for profit, and the work is not altered.

Computational algebraic geometry for statistical modeling FY09Q2 progress.

Energy Technology Data Exchange (ETDEWEB)

Thompson, David C.; Rojas, Joseph Maurice; Pebay, Philippe Pierre

2009-03-01

This is a progress report on polynomial system solving for statistical modeling. This is a progress report on polynomial system solving for statistical modeling. This quarter we have developed our first model of shock response data and an algorithm for identifying the chamber cone containing a polynomial system in n variables with n+k terms within polynomial time - a significant improvement over previous algorithms, all having exponential worst-case complexity. We have implemented and verified the chamber cone algorithm for n+3 and are working to extend the implementation to handle arbitrary k. Later sections of this report explain chamber cones in more detail; the next section provides an overview of the project and how the current progress fits into it.

FY09 recycling opportunity assessment for Sandia National Laboratories/New Mexico.

Energy Technology Data Exchange (ETDEWEB)

McCord, Samuel Adam

2010-07-01

This Recycling Opportunity Assessment (ROA) is a revision and expansion of the FY04 ROA. The original 16 materials are updated through FY08, and then 56 material streams are examined through FY09 with action items for ongoing improvement listed for most. In addition to expanding the list of solid waste materials examined, two new sections have been added to cover hazardous waste materials. Appendices include energy equivalencies of materials recycled, trends and recycle data, and summary tables of high, medium, and low priority action items.

Illinois perspective on low level radioactive waste disposal

International Nuclear Information System (INIS)

Etchison, D.

1984-01-01

Illinois is a big generator of low level radioactive waste. It has had extensive experience with controversial waste disposal and storage facilities. This experience makes it difficult for the public and political leaders in Illinois to support the establishment of new disposal facilities in the state. Yet, with extensive debates and discussions concerning the Low Level Waste Policy Act of 1980 and the proposed Midwest Compact, political leaders and the public are facing up to the fact that they must be responsible for the disposal of the low level radioactive waste generated in the state. The Governor and many political leaders from Illinois support the regional approach and believe it can be an innovative and progressive way for the state to deal with the range of low level waste management and disposal problems. A version of the Midwest Interstate Low Level Waste Compact has become Illinois law, but it has significant differences from the one adopted by five other states. Like other states in the midwest and northeast, Illinois is opposed to Congressional consent of the four pending compacts before the remaining two compacts, the northeast and midwest are sent to Washington and interregional agreements are negotiated between the sited and non-sited regions. A new national system must be established before access to existing commercial disposal becomes restricted

Richland Operations (DOE-RL) Environmental Safety Health (ES and H) FY 2000 and FY 2001 Execution Commitment Summary

Energy Technology Data Exchange (ETDEWEB)

REEP, I.E.

2000-12-01

All sites in the U.S. Department of Energy (DOE) Complex prepare this report annually for the DOE Office of Environment, Safety and Health (EH). The purpose of this report is to provide a summary of the previous and current year's Environment, Safety and Health (ES&H) execution commitments and the Safety and Health (S&H) resources that support these activities. The fiscal year (FY) 2000 and 2001 information and data contained in the Richland Operations Environment, Safefy and Health Fiscal Year 2002 Budget-Risk Management Summary (RL 2000a) were the basis for preparing this report. Fiscal year 2001 activities are based on the President's Amended Congressional Budget Request of $689.6 million for funding Ofice of Environmental Management (EM) $44.0 million for Fast Flux Test Facility standby less $7.0 million in anticipated DOE, Headquarters holdbacks for Office of Nuclear Energy, Science and Technology (NE); and $55.3 million for Safeguards and Security (SAS). Any funding changes as a result of the Congressional appropriation process will be reflected in the Fiscal Year 2003 ES&H Budget-Risk Management Summary to be issued in May 2001. This report provides the end-of-year status of FY 2000 ES&H execution commitments, including actual S&H expenditures, and describes planned FY 2001 ES&H execution commitments and the S&H resources needed to support those activities. This requirement is included in the ES&H guidance contained in the FY 2002 Field Budget Call (DOE 2000).

FY 2001 study report on the evaluation/analysis of the data collected in the field test project on the photovoltaic power generation for public facilities, etc.; 2001 nendo kenkyu seika hokokusho. Kokyo shisetsu you taiyoko hatsuden field test jigyo ni okeru shushu data hyoka kaiseki

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-03-01

As a field test project on the photovoltaic power generation, collection/analysis/evaluation of the operational data were made about photovoltaic power systems installed at 73 places in FY 2001. As to the analysis of deterioration with age and yearly changes of the system, analysis was made of operation hours of the equivalent system, system output coefficient and inverter performance efficiency in FY 1999, FY 2000 and FY 2001, and it was confirmed that there was few deterioration with age. Relating to the evaluation of reliability of the system, evaluation was made for the record of failures of photovoltaic power systems at 73 places, and the results were not very good as follows: average failure cycle: 1.06 y/system; average failure repair period: 14.9 d/system; rough opportunity loss electric energy: 81,548 kWh/y x 73 sites. Concerning the analysis of economical efficiency, the system cost decreased year by year to 1,102,000 yen/kW in FY 1997, and the power generation cost became 91.8 yen/kWh. The fund recovery year was 35.3 years, assuming the following: unit price of selling electricity: 15 yen/kWh, durable years: 20 years, and public subsidiary rate: 1/2. (NEDO)

LLW disposal, 1996 and beyond, an industry perspective

International Nuclear Information System (INIS)

Genoa, P.H.

1996-01-01

In this article the author reviews what has been done in the past 15 years in terms of opening sites for disposal of low-level radioactive wastes, and what seems to be on the horizon. He reviews process timelines, timelines from regional efforts, and timelines for LLW facilities. The author also looks at what types of changes have been made in the generation, control, and volume of LLW. He examines the pressures which have driven these changes, both from society and from cost control economics. The author tries to look at what government, waste generators, and the waste management industry should do to make progress toward adequate solutions to address the LLW disposal problems

Engineering risk assessment for emergency disposal projects of sudden water pollution incidents.

Science.gov (United States)

Shi, Bin; Jiang, Jiping; Liu, Rentao; Khan, Afed Ullah; Wang, Peng

2017-06-01

Without an engineering risk assessment for emergency disposal in response to sudden water pollution incidents, responders are prone to be challenged during emergency decision making. To address this gap, the concept and framework of emergency disposal engineering risks are reported in this paper. The proposed risk index system covers three stages consistent with the progress of an emergency disposal project. Fuzzy fault tree analysis (FFTA), a logical and diagrammatic method, was developed to evaluate the potential failure during the process of emergency disposal. The probability of basic events and their combination, which caused the failure of an emergency disposal project, were calculated based on the case of an emergency disposal project of an aniline pollution incident in the Zhuozhang River, Changzhi, China, in 2014. The critical events that can cause the occurrence of a top event (TE) were identified according to their contribution. Finally, advices on how to take measures using limited resources to prevent the failure of a TE are given according to the quantified results of risk magnitude. The proposed approach could be a potential useful safeguard for the implementation of an emergency disposal project during the process of emergency response.

78 FR 56271 - FY 2014-2020 Draft VA Strategic Plan

Science.gov (United States)

2013-09-12

... DEPARTMENT OF VETERANS AFFAIRS FY 2014-2020 Draft VA Strategic Plan AGENCY: Department of Veterans... Affairs (VA) is announcing the availability of the FY 2014-2020 Draft VA Strategic Plan (Strategic Plan... Act of 2010 (GPRAMA) (Pub. L. 111-352). The Strategic Plan provides the Department's long-term...

A study for the safety evaluation of geological disposal of TRU waste and influence on disposal site design by change of amount of TRU waste (Joint research)

International Nuclear Information System (INIS)

Hasegawa, Makoto; Kondo, Hitoshi; Takahashi, Kuniaki; Funabashi, Hideaki; Kawatsuma, Shinji; Kamei, Gento; Hirano, Fumio; Mihara, Morihiro; Ueda, Hiroyoshi; Ohi, Takao; Hyodo, Hideaki

2011-02-01

In the safety evaluation of the geological disposal of the TRU waste, it is extremely important to share the information with the Research and development organization (JAEA: that is also the waste generator) by the waste disposal entrepreneur (NUMO). In 2009, NUMO and JAEA set up a technical commission to investigate the reasonable TRU waste disposal following a cooperation agreement between these two organizations. In this report, the calculation result of radionuclide transport for a TRU waste geological disposal system was described, by using the Tiger code and the GoldSim code at identical terms. Tiger code is developed to calculate a more realistic performance assessment by JAEA. On the other hand, GoldSim code is the general simulation software that is used for the computation modeling of NUMO TRU disposal site. Comparing the calculation result, a big difference was not seen. Therefore, the reliability of both codes was able to be confirmed. Moreover, the influence on the disposal site design (Capacity: 19,000m 3 ) was examined when 10% of the amount of TRU waste increased. As a result, it was confirmed that the influence of the site design was very little based on the concept of the Second Progress Report on Research and Development for TRU Waste Disposal in Japan. (author)

Tank Vapor Characterization Project: Annual status report for FY 1996

International Nuclear Information System (INIS)

Silvers, K.L.; Fruchter, J.S.; Huckaby, J.L.; Almeida, T.L.; Evans, J.C. Jr.; Pool, K.H.; Simonen, C.A.; Thornton, B.M.

1997-01-01

In Fiscal Year 1996, staff at the Vapor Analytical Laboratory at Pacific Northwest National Laboratory performed work in support of characterizing the vapor composition of the headspaces of radioactive waste tanks at the Hanford Site. Work performed included support for technical issues and sampling methodologies, upgrades for analytical equipment, analytical method development, preparation of unexposed samples, analyses of tank headspaces samples, preparation of data reports, and operation of the tank vapor database. Progress made in FY 1996 included completion and issuance of 50 analytical data reports. A sampling system comparison study was initiated and completed during the fiscal year. The comparison study involved the vapor sampling system (VSS), a truck-based system, and the in situ vapor sampling system (ISVS), a cart-based system. Samples collected during the study were characterized for inorganic, permanent gases, total non-methane organic compounds and organic speciation by SUMMA trademark and TST methods. The study showed comparable sampling results between the systems resulting in the program switching from the VSS to the less expensive ISVS methodology in late May 1996. A temporal study was initiated in January 1996 in order to understand the influences seasonal temperatures changes have on the vapors in the headspace of Hanford waste tanks. A holding time study was initiated in the fourth quarter of FY 1996. Samples were collected from tank S-102 and rushed to the laboratory for time zero analysis. Additional samples will be analyzed at 1, 2, 4, 8, 16, and 32 weeks

Federal Facility Agreement Annual Progress Report for FY 1998

Energy Technology Data Exchange (ETDEWEB)

Palmer, E.

1999-08-04

This FFA Annual Progress Report has been developed to summarize the information for activities performed during the Fiscal Year 1998 (October 1, 1997, to September 30, 1998) and activities planned for Fiscal Year 1999 by U.S. EPA, SCDHEC, and SRS at those units and areas identified for remediation in the Agreement.

Verification study on technology for preliminary investigation for HLW geological disposal. Part 2. Verification of surface geophysical prospecting through establishing site descriptive models

International Nuclear Information System (INIS)

Kondo, Hirofumi; Suzuki, Koichi; Hasegawa, Takuma; Goto, Keiichiro; Yoshimura, Kimitaka; Muramoto, Shigenori

2012-01-01

The Yokosuka demonstration and validation project using Yokosuka CRIEPI site has been conducted since FY 2006 as a cooperative research between NUMO (Nuclear Waste Management Organization of Japan) and CRIEPI. The objectives of this project are to examine and to refine the basic methodology of the investigation and assessment of properties of geological environment in the stage of Preliminary Investigation for HLW geological disposal. Within Preliminary Investigation technologies, surface geophysical prospecting is an important means of obtaining information from deep geological environment for planning borehole surveys. In FY 2010, both seismic prospecting (seismic reflection and vertical seismic profiling methods) for obtaining information about geological structure and electromagnetic prospecting (magneto-telluric and time domain electromagnetic methods) for obtaining information about resistivity structure reflecting the distribution of salt water/fresh water boundary to a depth of over several hundred meters were conducted in the Yokosuka CRIEPI site. Through these surveys, the contribution of geophysical prospecting methods in the surface survey stage to improving the reliability of site descriptive models was confirmed. (author)

Safety regulation of geological disposal of radioactive waste: progress since Cordoba and remaining challenges

International Nuclear Information System (INIS)

Duncan, A.; Pescatore, C.

2010-01-01

Claudio Pescatore, Deputy Division Head (NEA) presented a paper, the purpose of which was to recall where we stood at the time of the Cordoba Workshop (1997) on the regulation of disposal of long-lived radioactive waste, to review developments since then, to present the key existing issues, and reflect on the remaining challenges and possible responses. The overview study on progress in regulation for geological disposal since the Cordoba workshop [NEA/RWMC/RF(2008)6], provides a good list of references regarding the first two issues. The presentation of the existing issues takes advantage of the synthesis of the responses to a questionnaire completed by the regulatory organisations in preparation for this workshop. It warns regulators and implementers that international work to date seems to have created an expectation in the mind of the public and in some organisations that nothing less than a guarantee by the regulator is needed of maintaining current levels of protection of both individuals and populations practically forever, regardless of the impracticality of this. This expectation needs to be replaced with a carefully and clearly explained understanding of the choices involved in dealing with long-lived radioactive waste against a background of our responsibilities to both current and future generations and our practical capacity to deliver them. Concerning the current major challenges faced in regulation, the paper comes back to the issue of the 'guarantee' by the regulator and it observes that there is no doubt that there is a willingness to do the best to comply with the principle of protection and that we are broadly convinced that current concepts for geological disposal, supported by multiple lines of reasoning and application of best available techniques (BAT) will meet that principle. However, we do not have the capacity to prove or guarantee this, nor do we believe that it is possible in practice. Although we are advised that it is neither

Fiscal Year (FY) 2017 Activities for the Spent Fuel Nondestructive Assay Project

Energy Technology Data Exchange (ETDEWEB)

Trellue, Holly Renee [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Trahan, Alexis Chanel [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); McMath, Garrett Earl [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Swinhoe, Martyn Thomas [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Hu, Jianwei [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Worrall, Andrew [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Ilas, Germina [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Grogan, Brandon [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2017-09-11

The main focus of research in the NA-241 spent fuel nondestructive assay (NDA) project in FY17 has been completing the fabrication and testing of two prototype instruments for upcoming spent fuel measurements at the Clab interim storage facility in Sweden. One is a passive instrument: Differential Die-away Self Interrogation-Passive Neutron Albedo Reactivity (DDSI), and one is an active instrument: Differential Die-Away-Californium Interrogation with Prompt Neutron (DDA). DDSI was fabricated and tested with fresh fuel at Los Alamos National Laboratory in FY15 and FY16, then shipped to Sweden at the beginning of FY17. Research was performed in FY17 to simplify results from the data acquisition system, which is complex because signals from 56 different 3He detectors must be processed using list mode data. The DDA instrument was fabricated at the end of FY16. New high count rate electronics better suited for a spent fuel environment (i.e., KM-200 preamplifiers) were built specifically for this instrument in FY17, and new Tygon tubing to house electrical cables was purchased and installed. Fresh fuel tests using the DDA instrument with numerous configurations of fuel rods containing depleted uranium (DU), low enriched uranium (LEU), and LEU with burnable poisons (Gd) were successfully performed and compared to simulations.1 Additionally, members of the spent fuel NDA project team travelled to Sweden for a “spent fuel characterization and decay heat” workshop involving simulations of spent fuel and analysis of uncertainties in decay heat calculations.

Westinghouse Hanford Company FY 1995 Materials Management Plan (MMP)

International Nuclear Information System (INIS)

Higginson, M.C.

1994-10-01

The safe and sound operation of facilities and storage of nuclear material are top priorities within Hanford's environmental management, site restoration mission. The projected materials estimates, based on the Materials Management Plan (MMP) assumptions outlined below, were prepared for Department of Energy (DOE) use in long-range planning. The Hanford MMP covers the period FY 1995 through FY 2005, as directed by DOE. All DOE Richland Operations (RL) Office facilities are essentially funded by the Office of Transition and Facilities Management, Environmental Restoration and Waste Management (EM). These facilities include PUREX, the UO 3 plant, N-Reactor, T-Plant, K-Basins, FFTF, PFP and the 300 Area Fuel Fabrication facilities. Currently DP provides partial funding for the latter two facilities. Beginning in FY 1996 (in accordance with DOE-HQ MMP assumptions), EM will fund expenses related to the storage, monitoring, and safeguarding of all Special Nuclear Material (SNM) in the PFP. Ownership and costs related to movement and/or stabilization of that material will belong to EM programs (excluding NE material). It is also assumed that IAEA will take over inventory validation and surveillance of EM owned SNM at this time (FY 1996)

NREL Photovoltaic Program FY 1996 Annual Report

Energy Technology Data Exchange (ETDEWEB)

1997-08-01

This report summarizes the in-house and subcontract research and development (R&D) activities under the National Renewable Energy Laboratory (NREL) Photovoltaics (PV) Program from October 1, 1995 through September 30, 1996 (fiscal year [FY] 1996). The NREL PV Program is part of the U.S. Department of Energy's (DOE) National Photovoltaics Program, as described in the DOE Photovoltaics Program Plan, FY 1991 - FY 1995. The mission of the DOE National Photovoltaics Program is to: "Work in partnership with U.S. industry to develop and deploy photovoltaic technology for generating economically competitive electric power, making photovoltaics an important contributor to the nation's and the world's energy use and environmental improvement. The two primary goals of the national program are to (1) maintain the U.S. PV industry's world leadership in research and technology development and (2) help the U.S. industry remain a major, profitable force in the world market. The NREL PV Program provides leadership and support to the national program toward achieving its mission and goals.

Control of radioactive waste disposal into the marine environment

International Nuclear Information System (INIS)

1983-01-01

The body of this publication is intended to provide adequate information on the broad aspects of radioactive waste disposal into the sea. The introduction of radionuclides into the sea from uncontrollable sources, such as weapons test explosions, is outside the scope of this publication, as are releases of radionuclides from nuclear-powered vessels. It should be stressed that agreements on practices for the marine disposal of wastes are being developed and the understanding of oceanographic processes is rapidly progressing; therefore, the conclusions presented here should always be considered in the context of changes in both knowledge and practice that occur subsequent to the completion of this text

AR and TD Fossil Energy Materials Program. Quarterly progress report for the period ending December 31, 1981

Energy Technology Data Exchange (ETDEWEB)

1982-04-01

The ORNL Fossil Energy Materials Program Office compiles and issues this combined quarterly progress report from camera-ready copies submitted by each of the participating subcontractor organizations. This report of activities on the program is organized in accordance with a work breakdown structure defined in the AR and TD Fossil Energy Materials Program Plan for FY 1982-1986 in which projects are organized according to fossil energy technologies. This report is divided into parts and chapters with each part describing projects related to a particular fossil energy technology. Chapters within a part provide details of the various projects associated with that technology. We hope this series of AR and TD Fossil Energy Materials Program quarterly progress reports will aid in the dissemination of information developed on the program. Plans for the program will be issued annually. A draft of the program plan for FY 1982 to 1986 has been prepared and is in the review process. The implementation of these plans will be reflected by these quarterly progress reports, and this dissemination of information will bw augmented by topical or final reports as appropriate.

Flammable gas safety program. Analytical methods development: FY 1993 progress report

Energy Technology Data Exchange (ETDEWEB)

Campbell, J.A.; Clauss, S.; Grant, K.; Hoopes, V.; Lerner, B.; Lucke, R.; Mong, G.; Rau, J.; Steele, R.

1994-01-01

This report describes the status of developing analytical methods to account for the organic constituents in Hanford waste tanks, with particular emphasis on those tanks that have been assigned to the Flammable Gas Watch List. Six samples of core segments from Tank 101-SY, obtained during the window E core sampling, have been analyzed for organic constituents. Four of the samples were from the upper region, or convective layer, of the tank and two were from the lower, nonconvective layer. The samples were analyzed for chelators, chelator fragments, and several carboxylic acids by derivatization gas chromatography/mass spectrometry (GC/MS). The major components detected were ethylenediaminetetraacetic acid (EDTA), nitroso-iminodiacetic acid (NIDA), nitrilotriacetic acid (NTA), citric acid (CA), succinic acid (SA), and ethylenediaminetriacetic acid (ED3A). The chelator of highest concentration was EDTA in all six samples analyzed. Liquid chromatography (LC) was used to quantitate low molecular weight acids (LMWA) including oxalic, formic, glycolic, and acetic acids, which are present in the waste as acid salts. From 23 to 61% of the total organic carbon (TOC) in the samples analyzed was accounted for by these acids. Oxalate constituted approximately 40% of the TOC in the nonconvective layer samples. Oxalate was found to be approximately 3 to 4 times higher in concentration in the nonconvective layer than in the convective layer. During FY 1993, LC methods for analyzing LWMA, and two chelators N-(2-hydroxyethyl) ethylenediaminetriacetic acid and EDTA, were transferred to personnel in the Analytical Chemistry Laboratory and the 222-S laboratory.

FY01 Supplemental Science and Performance Analysis: Volume 1, Scientific Bases and Analyses

International Nuclear Information System (INIS)

Bodvarsson, G.S.; Dobson, David

2001-01-01

The U.S. Department of Energy (DOE) is considering the possible recommendation of a site at Yucca Mountain, Nevada, for development as a geologic repository for the disposal of high-level radioactive waste and spent nuclear fuel. To facilitate public review and comment, in May 2001 the DOE released the Yucca Mountain Science and Engineering Report (S and ER) (DOE 2001 [DIRS 153849]), which presents technical information supporting the consideration of the possible site recommendation. The report summarizes the results of more than 20 years of scientific and engineering studies. A decision to recommend the site has not been made: the DOE has provided the S and ER and its supporting documents as an aid to the public in formulating comments on the possible recommendation. When the S and ER (DOE 2001 [DIRS 153849]) was released, the DOE acknowledged that technical and scientific analyses of the site were ongoing. Therefore, the DOE noted in the Federal Register Notice accompanying the report (66 FR 23013 [DIRS 155009], p. 2) that additional technical information would be released before the dates, locations, and times for public hearings on the possible recommendation were announced. This information includes: (1) the results of additional technical studies of a potential repository at Yucca Mountain, contained in this FY01 Supplemental Science and Performance Analyses: Vol. 1, Scientific Bases and Analyses; and FY01 Supplemental Science and Performance Analyses: Vol. 2, Performance Analyses (McNeish 2001 [DIRS 155023]) (collectively referred to as the SSPA) and (2) a preliminary evaluation of the Yucca Mountain site's preclosure and postclosure performance against the DOE's proposed site suitability guidelines (10 CFR Part 963 [64 FR 67054 [DIRS 124754

FY01 Supplemental Science and Performance Analysis: Volume 1,Scientific Bases and Analyses

Energy Technology Data Exchange (ETDEWEB)

Bodvarsson, G.S.; Dobson, David

2001-05-30

The U.S. Department of Energy (DOE) is considering the possible recommendation of a site at Yucca Mountain, Nevada, for development as a geologic repository for the disposal of high-level radioactive waste and spent nuclear fuel. To facilitate public review and comment, in May 2001 the DOE released the Yucca Mountain Science and Engineering Report (S&ER) (DOE 2001 [DIRS 153849]), which presents technical information supporting the consideration of the possible site recommendation. The report summarizes the results of more than 20 years of scientific and engineering studies. A decision to recommend the site has not been made: the DOE has provided the S&ER and its supporting documents as an aid to the public in formulating comments on the possible recommendation. When the S&ER (DOE 2001 [DIRS 153849]) was released, the DOE acknowledged that technical and scientific analyses of the site were ongoing. Therefore, the DOE noted in the Federal Register Notice accompanying the report (66 FR 23013 [DIRS 155009], p. 2) that additional technical information would be released before the dates, locations, and times for public hearings on the possible recommendation were announced. This information includes: (1) the results of additional technical studies of a potential repository at Yucca Mountain, contained in this FY01 Supplemental Science and Performance Analyses: Vol. 1, Scientific Bases and Analyses; and FY01 Supplemental Science and Performance Analyses: Vol. 2, Performance Analyses (McNeish 2001 [DIRS 155023]) (collectively referred to as the SSPA) and (2) a preliminary evaluation of the Yucca Mountain site's preclosure and postclosure performance against the DOE's proposed site suitability guidelines (10 CFR Part 963 [64 FR 67054 [DIRS 124754

2007 Joint Service Power Expo Held in San Diego, California on April 24-26, 2007. Volume 4: Thursday Presentations

Science.gov (United States)

2007-04-26

Ammonia Borane Core Attributes • Pellet Based Ammonia Borane • 12-14% Hydrogen Well Demonstrated • System Packaging Under Development Jadoo Power Systems...FY07 FY08 Pacing Technologies: Burner control/Heat- driven cooling Meso-components LW Blk III PM-MEP STEP Power...technology to the warfighter quicker” FY05 FY06 FY07 FY08 Pacing Technologies: Burner

1989 Annual report on low-level radioactive waste management progress

International Nuclear Information System (INIS)

1990-10-01

This report summarizes the progress during 1989 of states and compacts in establishing new low-level radioactive waste disposal facilities. It also provides summary information on the volume of low-level waste received for disposal in 1989 by commercially operated low-level waste disposal facilities. This report is in response to Section 7(b) of Title I of Public Law 99--240, the Low-Level Radioactive Waste Policy Amendments Act of 1985. 2 figs., 5 tabs

Transrapid 06 test vehicle and its drive system

Energy Technology Data Exchange (ETDEWEB)

Eitlhuber, E

1984-06-01

To prove the practicability of a high-speed maglev transport system, a large-scale test facility is now under construction in Emsland with the backing of the Federal Ministry of Research and Technology. The TRANSRAPID 06 test vehicle is designed to carry 192 seated passengers at a maximum speed of 400 km/h. With running tests now in progress, the project has entered a decisive phase. The article describes the objectives, concept and design of the Tr 06 vehicle and its drive system. Upon conclusion of the main operational preparations by the construction consortium, the facility will be taken over and operated by the MVP, a joint subsidiary of the DB, Lufthansa German Airlines and the IABG. Following a successful changeover, the aim will be to ensure feedback of operating experience to the industry.

KURRI progress report 1996. April 1996 - March 1997

International Nuclear Information System (INIS)

1997-11-01

This report describes the activities of the Research Reactor Institute, Kyoto University (KURRI) during the fiscal year (FY) of 1996. A total of 1506 researchers visited the KURRI to perform 106 experimental applications or to attend 17 symposia and 3 workshops. At the end of a three-year period, the scientific achievements of two research projects, 'Residual Stress and Strip Investigations of Metallic Materials by Neutron Scattering' and 'Radiation Protection to the Manageable Ionizing Radiation in the KUR facilities' were reviewed during the annual Scientific Meeting of the KURRI, held on Jan 21-23, 1997. The five-year modernization Program of the KUR and its related facirities was in progress since the reorganization for a Center of Excellence on April 1, 1995. In the FY, 1996 the maintenance and close inspections of the heavy water facility and the graphite thermal column were carried out during the reactor shutdown from Feb 24, 1997 to May 9, 1997. A total of 174 reports of project and general researches in 1996 were outlined. (M.N.)

KURRI progress report 1996. April 1996 - March 1997

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-11-01

This report describes the activities of the Research Reactor Institute, Kyoto University (KURRI) during the fiscal year (FY) of 1996. A total of 1506 researchers visited the KURRI to perform 106 experimental applications or to attend 17 symposia and 3 workshops. At the end of a three-year period, the scientific achievements of two research projects, `Residual Stress and Strip Investigations of Metallic Materials by Neutron Scattering` and `Radiation Protection to the Manageable Ionizing Radiation in the KUR facilities` were reviewed during the annual Scientific Meeting of the KURRI, held on Jan 21-23, 1997. The five-year modernization Program of the KUR and its related facirities was in progress since the reorganization for a Center of Excellence on April 1, 1995. In the FY, 1996 the maintenance and close inspections of the heavy water facility and the graphite thermal column were carried out during the reactor shutdown from Feb 24, 1997 to May 9, 1997. A total of 174 reports of project and general researches in 1996 were outlined. (M.N.)

FY16 Strategic Themes White Paper.

Energy Technology Data Exchange (ETDEWEB)

Leland, Robert W. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2017-03-01

The Science and Technology (S&T) Division 1000 Strategic Plan includes the Themes, Goals, and Actions for FY16. S&T will continue to support the Labs Strategic plan, Mission Areas and Program Management Units by focusing on four strategic themes that align with the targeted needs of the Labs. The themes presented in this plan are Mission Engagement, Bold Outcomes, Collaborative Environment, and the Safety Imperative. Collectively they emphasize diverse, collaborative teams and a self-reliant culture of safety that will deliver on our promise of exceptional service in the national interest like never before. Mission Engagement focuses on increasing collaboration at all levels but with emphasis at the strategic level with mission efforts across the labs. Bold Outcomes seeks to increase the ability to take thoughtful risks with the goal of achieving transformative breakthroughs more frequently. Collaborative environment strives for a self-aware, collaborative working environment that bridges the many cultures of Sandia. Finally, Safety Imperative aims to minimize the risk of serious injury and to continuously strengthen the safety culture. Each of these themes is accompanied by a brief vision statement, several goals, and planned actions to support those goals throughout FY16 and leading into FY17.

Horonobe Underground Research Laboratory project. Synthesis of phase 1 investigation 2001-2005, Volume 'geological disposal research'

International Nuclear Information System (INIS)

Fujita, Tomoo; Taniguchi, Naoki; Maekawa, Keisuke; Sawada, Atsushi; Makino, Hitoshi; Sasamoto, Hiroshi; Yoshikawa, Hideki; Shibata, Masahiro; Ota, Kunio; Miyahara, Kaname; Naito, Morimasa; Yui, Mikazu; Matsui, Hiroya; Hama, Katsuhiro; Kunimaru, Takanori; Takeuchi, Ryuji; Tanai, Kenji; Kurikami, Hiroshi; Wakasugi, Keiichiro; Ishii, Eiichi

2011-03-01

This report summarizes the progress of research and development on geological disposal during the surface-based investigation phase (2001-2005) in the Horonobe Underground Research Laboratory project, of which aims are to apply the design methods of geological disposal and mass transport analysis to actual geological conditions obtained from the project as an example of actual geological environment. For the first aim, the design methods for the geological disposal facility proposed in 'H12 report (the second progress report)' was reviewed and then improved based on the recent knowledge. The applicability of design for engineered barrier system, backfill of disposal tunnel, underground facility was illustrated. For the second aim, the conceptual structure from site investigation and evaluation to mass transport analysis was developed as a work flow at first. Then following this work flow a series of procedures for mass transport analysis was applied to the actual geological conditions to illustrate the practical workability of the work flow and the applicability of this methodology. Consequently, based on the results, future subjects were derived. (author)

Horonobe Underground Research Laboratory project synthesis of phase I investigation 2001-2005. Volume 'Geological disposal research'

International Nuclear Information System (INIS)

Fujita, Tomoo; Taniguchi, Naoki; Tanai, Kenji; Nishimura, Mayuka; Kobayashi, Yasushi; Hiramoto, Masayuki; Maekawa, Keisuke; Sawada, Atsushi; Makino, Hitoshi; Sasamoto, Hiroshi; Yoshikawa, Hideki; Shibata, Masahiro; Wakasugi, Keiichiro; Nakano, Katsushi; Seo, Toshihiro; Miyahara, Kaname; Naito, Morimasa; Yui, Mikazu; Matsui, Hiroya; Kurikami, Hiroshi; Kunimaru, Takanori; Ishii, Eiichi; Ota, Kunio; Hama, Katsuhiro; Takeuchi, Ryuji

2007-03-01

This report summarizes the progress of research and development on geological disposal during the surface-based investigation phase (2001-2005) in the Horonobe Underground Research Laboratory project (HOR), of which aims are to apply the design methods of geological disposal and mass transport analysis to actual geological conditions obtained from the surface-based investigations in HOR as an example of actual geological environment. For the first aim, the design methods for the geological disposal facility proposed in 'H12 report (the second progress report)' was reviewed and then improved based on the recent knowledge. The applicability of design for engineered barrier system, backfill of disposal tunnel, underground facility was illustrated. For the second aim, the conceptual structure from site investigation and evaluation to mass transport analysis was developed as a work flow at first. Then following this work flow a series of procedures for mass transport analysis was applied to the actual geological conditions to illustrate the practical workability of the work flow and the applicability of this methodology. Consequently, based on the results, future subjects were derived. (author)

KEK Engineering Department -activity report FY 2003

International Nuclear Information System (INIS)

2005-03-01

This report includes all kinds of activities of the Engineering Department of KEK from 2002 to 2003 FY. There are fourteen chapters, which contain KEK Prize for engineering, KEK meeting of engineering technologies, Engineering Seminar, COACK (Component Oriented Advanced Control Kernel) for cooperation R and D project, Forum on engineering technologies from 1998 to 2003 FY, Engineering Department Symposium, service trainings, Engineering Department research study, English training, training for professional worker, training for technical expert, report on joint training for technical expert, training for middle school students, and the Engineering Department system and the main events from 1971 to 2003. (S.Y. )

Assessment and Correction of on-Orbit Radiometric Calibration for FY-3 VIRR Thermal Infrared Channels

Directory of Open Access Journals (Sweden)

Na Xu

2014-03-01

Full Text Available FengYun-3 (FY-3 Visible Infrared Radiometer (VIRR, along with its predecessor, Multispectral Visible Infrared Scanning Radiometer (MVISR, onboard FY-1C&D have had continuous global observation more than 14 years. This data record is valuable for weather prediction, climate monitoring, and environment research. Data quality is vital for satellite data assimilations in Numerical Weather Prediction (NWP and quantitative remote sensing applications. In this paper, the accuracies of radiometric calibration for VIRR onboard FY-3A and FY-3B, in thermal infrared (TIR channels, are evaluated using the Low Earth Orbit (LEO-LEO simultaneous nadir overpass intercalibration method. Hyperspectral and high-quality observations from Infrared Atmosphere Sounding Instrument (IASI onboard METOP-A are used as reference. The biases of VIRR measurements with respect to IASI over one-and-a-half years indicate that the TIR calibration accuracy of FY-3B VIRR is better than that of FY-3A VIRR. The brightness temperature (BT measured by FY-3A/VIRR is cooler than that measured by IASI with monthly mean biases ranging from −2 K to −1 K for channel 4 and −1 K to 0.2 K for channel 5. Measurements from FY-3B/VIRR are more consistent with that from IASI, and the annual mean biases are 0.84 ± 0.16 K and −0.66 ± 0.18 K for channels 4 and 5, respectively. The BT biases of FY-3A/VIRR show scene temperature-dependence and seasonal variation, which are not found from FY-3B/VIRR BT biases. The temperature-dependent biases are shown to be attributed to the nonlinearity of detectors. New nonlinear correction coefficients of FY-3A/VIRR TIR channels are reevaluated using various collocation samples. Verification results indicate that the use of the new nonlinear correction can greatly correct the scene temperature-dependent and systematic biases.

FY2015 Lightweight Materials R&D Annual Progress Report

Energy Technology Data Exchange (ETDEWEB)

None, None

2016-09-30

The Lightweight Materials research and development (R&D) area within the DOE Vehicle Technologies Office (VTO) provides support and guidance for many cutting-edge automotive technologies under development. Research focuses on addressing critical barriers to commercializing lightweight materials for passenger and commercial vehicles. This report describes the progress made on the research and development projects funded by the Lightweight Materials area.

10 CFR 61.52 - Land disposal facility operation and disposal site closure.

Science.gov (United States)

2010-01-01

... DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.52 Land disposal... wastes by placing in disposal units which are sufficiently separated from disposal units for the other... between any buried waste and the disposal site boundary and beneath the disposed waste. The buffer zone...

Experience of NS disposal at the Enterprise ''Zvezdochka'', in Severodvinsk. Problems of ecological safety

International Nuclear Information System (INIS)

Kozlov, Yuri

1999-01-01

According to this presentation, decommissioning and disposal of nuclear submarines is a problem of great concern in Russia. So far more than 150 nuclear submarines have been removed from the Fleet and will be disposed of. Future disposals were not taken into consideration when the shipyards were constructed. Nuclear vessels with loaded cores stay afloat waiting for their turn to be disposed of, often with damaged safety assurance systems and a potential for causing major ecological catastrophes. The presentation deals briefly with some international programmes in progress at Nerpa in Murmansk, Zvezda in Primorye and Zvezdochka in Arkhangelsk and then discusses in more detail the experience of disposal at the Zvezdochka, which under the Start-2 agreement is defined as one of the enterprises dealing with the disposal of strategic nuclear submarines. There they have the qualified staff and the equipment needed. Spent nuclear fuel unloading and removal is the most acute problem

Differences in alarm events between disposable and reusable electrocardiography lead wires.

Science.gov (United States)

Albert, Nancy M; Murray, Terri; Bena, James F; Slifcak, Ellen; Roach, Joel D; Spence, Jackie; Burkle, Alicia

2015-01-01

Disposable electrocardiographic lead wires (ECG-LWs) may not be as durable as reusable ones. To examine differences in alarm events between disposable and reusable ECG-LWs. Two cardiac telemetry units were randomized to reusable ECG-LWs, and 2 units alternated between disposable and reusable ECG-LWs for 4 months. A remote monitoring team, blinded to ECG-LW type, assessed frequency and type of alarm events by using total counts and rates per 100 patient days. Event rates were compared by using generalized linear mixed-effect models for differences and noninferiority between wire types. In 1611 patients and 9385.5 patient days of ECG monitoring, patient characteristics were similar between groups. Rates of alarms for no telemetry, leads fail, or leads off were lower in disposable ECG-LWs (adjusted relative risk [95% CI], 0.71 [0.53-0.96]; noninferiority P < .001; superiority P = .03) and monitoring (artifact) alarms were significantly noninferior (adjusted relative risk [95% CI]: 0.88, [0.62-1.24], P = .02; superiority P = .44). No between-group differences existed in false or true crisis alarms. Disposable ECG-LWs were noninferior to reusable ECG-LWs for all false-alarm events (N [rate per 100 patient days], disposable 2029 [79.1] vs reusable 6673 [97.9]; adjusted relative risk [95% CI]: 0.81 [0.63-1.06], P = .002; superiority P = .12.) Disposable ECG-LWs with patented push-button design had superior performance in reducing alarms created by no telemetry, leads fail, or leads off and significant noninferiority in all false-alarm rates compared with reusable ECG-LWs. Fewer ECG alarms may save nurses time, decrease alarm fatigue, and improve patient safety. ©2015 American Association of Critical-Care Nurses.

Preliminary disposal limits, plume interaction factors, and final disposal limits

Energy Technology Data Exchange (ETDEWEB)

Flach, G. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2018-01-11

In the 2008 E-Area Performance Assessment (PA), each final disposal limit was constructed as the product of a preliminary disposal limit and a plume interaction factor. The following mathematical development demonstrates that performance objectives are generally expected to be satisfied with high confidence under practical PA scenarios using this method. However, radionuclides that experience significant decay between a disposal unit and the 100-meter boundary, such as H-3 and Sr-90, can challenge performance objectives, depending on the disposed-of waste composition, facility geometry, and the significance of the plume interaction factor. Pros and cons of analyzing single disposal units or multiple disposal units as a group in the preliminary disposal limits analysis are also identified.

Conceptual design study of Fusion Experimental Reactor (FY87FER)

International Nuclear Information System (INIS)

1988-05-01

The design study of Fusion Experimental Reactor(FER) which has been proposed to be the next step fusion device has been conducted by JAERI Reactor System Laboratory since 1982 and by FER design team since 1984. This is the final report of the FER design team program and describes the results obtained in FY1987 (partially in FY1986) activities. The contents of this report consist of the reference design which is based on the guideline in FY1986 by the Subcomitees set up in Nuclear Fusion Council of Atomic Energy Commission of Japan, the Low-Physics-Risk reactor design for achieving physics mission more reliably and the system study of FER design candidates including above two designs. (author)

U.S. Geological Survey research in radioactive waste disposal - Fiscal years 1986-1990

Science.gov (United States)

Trask, N.J.; Stevens, P.R.

1991-01-01

The report summarizes progress on geologic and hydrologic research related to the disposal of radioactive wastes. The research efforts are categorized according to whether they are related most directly to: (1) high-level wastes, (2) transuranic wastes, (3) low-level and mixed low-level and hazardous wastes, or (4) uranium mill tailings. Included is research applicable to the identification and geohydrologic characterization of waste-disposal sites, to investigations of specific sites where wastes have been stored, to development of techniques and methods for characterizing disposal sites, and to studies of geologic and hydrologic processes related to the transport and/or retention of waste radionuclides.

77 FR 5614 - Department of State FY11 Service Contract Inventory

Science.gov (United States)

2012-02-03

... DEPARTMENT OF STATE [Public Notice 7785] Department of State FY11 Service Contract Inventory... Contract Inventory. SUMMARY: The Department of State has publically released its Service Contract Inventory.../ . Section 743 of Division C of the FY 2010 Consolidated Appropriations Act, Public Law 111-117, requires...

The progress and results of a demonstration test of a cavern-type disposal facility

International Nuclear Information System (INIS)

Akiyama, Yoshihiro; Terada, Kenji; Oda, Nobuaki; Yada, Tsutomu; Nakajima, Takahiro

2011-01-01

The cavern-type disposal facilities for low-level waste (LLW) with relatively high radioactivity levels mainly generated from power reactor decommissioning and for part of transuranic (TRU) waste mainly from spent fuel reprocessing are designed to be constructed in a cavern 50 to 100 meters below ground, and to employ an engineered barrier system (EBS) of a combination of bentonite and cement materials in Japan. In order to advance the feasibility study for these disposal, a government-commissioned research project named Demonstration Test of Cavern-Type Disposal Facility started in fiscal 2005, and since fiscal 2007 a full-scale mock-up test facility has been constructed under actual subsurface environment. The main objective of the test is to establish construction methodology and procedures which ensure the required quality of the EBS on-site. By fiscal 2009 some parts of the facility have been constructed, and the test has demonstrated both practicability of the construction and achievement of the quality. They are respectively taken as low-permeability of less than 5x10 13 m/s and low-diffusivity of less than 1x10 -12 m 2 /s at the time of completion of construction. This paper covers the project outline and the test results obtained by the construction of some parts of a bentonite and cement materials. (author)

Oak Ridge TNS Program: summary of FY 1978 activities

International Nuclear Information System (INIS)

Steiner, D.; Becraft, W.R.; Brown, T.G.

1979-07-01

The Next Step (TNS) represents the stage of fusion energy development in which the major emphasis is on engineering testing and demonstration. In this document, the activities of the Oak Ridge TNS Program for FY 1978 are described and summarized. The Reference Design that has evolved from these activities is described, its operating characteristics are examined, and project planning issues are considered. Major conclusions from the FY 1978 effort are stated

Rodent movements, densities and radionuclide concentrations at a liquid radioactive waste disposal area

International Nuclear Information System (INIS)

Halford, D.K.

1983-01-01

Movements and densities of rodents at a liquid radioactive waste disposal area were studied from June to September 1981 using trap line and assessment line techniques. The average distance between points of successive capture was 42 +- 25 (SD) m for deer mice (Peromyscus maniculatus) and 37 +- 21 m for kangaroo rats (Dipodomys ordii). Densities of deer mice averaged 10.2/ha with a population estimate of 57 within the area of rodent captures. The population estimate of 4 species of small mammals at the waste pond complex was 93. Radionuclide concentrations averaged 133 +- 97 pCi/g for rodents captured inside the disposal area boundary, 18 +- 22 pCi/g for those captured outside of the dispoal area fence and 0.50 +- 0.6 pCi/g for control animals. Species captured outside of the waste area boundary had significantly lower (P 137 Cs, 134 Cs, 60 Co and 65 Zn) in rodents at the liquid waste disposal area was estimated to be about 162 nCi

FY 93 thermal loading systems study final report: Volume 1. Revision 1

International Nuclear Information System (INIS)

Saterlie, S.F.; Thomson, B.H.

1994-01-01

The ability to meet the overall performance requirements for the proposed Mined Geology Disposal System at Yucca Mountain, Nevada requires the two major subsystem (natural barriers and engineered barriers) to positively contribute to containment and radionuclide isolation. In addition to the postclosure performance the proposed repository must meet preclosure requirements of safety, retrievability, and operability. Cost and schedule were also considered. The thermal loading strategy chosen may significantly affect both the postclosure and preclosure performance of the proposed repository. Although the current Site Characterization Plan reference case is 57 kilowatts (kW)/acre, other thermal loading strategies (different areal mass loadings) have been proposed which possess both advantages and disadvantages. The objectives of the FY 1993 Thermal Loading Study were to (1) place bounds on the thermal loading which would establish the loading regime that is ''too hot'' and the loading regime that is ''too cold'', to (2) ''grade'' or evaluate the performance, as a function of thermal loading, of the repository to contain high level wastes against performance criteria and to (3) evaluate the performance of the various options with respect to cost, safety, and operability. Additionally, the effort was to (4) identify important uncertainties that need to be resolved by tests and/or analyses in order to complete a performance assessment on the effects of thermal loading. The FY 1993 Thermal Loading Study was conducted from December 1, 1992 to December 30, 1993 and this final report provides the findings of the study. Volume 1 contains the Introduction; Performance requirements; Input and assumptions; Near-field thermal analysis; Far-field thermal analysis; Cost analysis; Other considerations; System analysis; Additional thermal analysis; and Conclusions and recommendations. 71 refs., 54 figs

Nevada Test Site-Directed Research and Development, FY 2007 Report

International Nuclear Information System (INIS)

Wil Lewis, editor

2008-01-01

The Nevada Test Site-Directed Research and Development (SDRD) program completed a very successful year of research and development activities in FY 2007. Twenty-nine new projects were selected for funding this year, and eight projects started in FY 2006 were brought to conclusion. The total funds expended by the SDRD program were $5.67 million, for an average per-project cost of $153 thousand. An external audit conducted in September 2007 verified that appropriate accounting practices were applied to the SDRD program. Highlights for the year included: programmatic adoption of 8 SDRD-developed technologies; the filing of 9 invention disclosures for innovation evolving from SDRD projects; participation in the tri-Lab Laboratory Directed Research and Development (LDRD) and SDRD Symposium that was broadly attended by Nevada Test Site (NTS), National Nuclear Security Administration (NNSA), LDRD, U.S. Department of Homeland Security (DHS), and U.S. Department of Defense (DoD) representatives; peer reviews of all FY 2007 projects; and the successful completion of 37 R and D projects, as presented in this report. In response to a company-wide call, authors throughout the NTS complex submitted 182 proposals for FY 2007 SDRD projects. The SDRD program has seen a dramatic increase in the yearly total of submitted proposals--from 69 in FY 2002 to 182 this year--while the number of projects funded has actually decreased from a program high of 57 in FY 2004. The overall effect of this trend has helped ensure an increasingly competitive program that benefited from a broader set of innovative ideas, making project selection both challenging and rewarding. Proposals were evaluated for technical merit, including such factors as innovation, probability of success, potential benefit, and mission applicability. Authors and reviewers benefited from the use of a shortfalls list entitled the 'NTS Technology Needs Assessment' that was compiled from NTS, National Weapons Laboratory (NWL

Nevada Test Site-Directed Research and Development, FY 2007 Report

Energy Technology Data Exchange (ETDEWEB)

Wil Lewis, editor

2008-02-20

The Nevada Test Site-Directed Research and Development (SDRD) program completed a very successful year of research and development activities in FY 2007. Twenty-nine new projects were selected for funding this year, and eight projects started in FY 2006 were brought to conclusion. The total funds expended by the SDRD program were $5.67 million, for an average per-project cost of $153 thousand. An external audit conducted in September 2007 verified that appropriate accounting practices were applied to the SDRD program. Highlights for the year included: programmatic adoption of 8 SDRD-developed technologies; the filing of 9 invention disclosures for innovation evolving from SDRD projects; participation in the tri-Lab Laboratory Directed Research and Development (LDRD) and SDRD Symposium that was broadly attended by Nevada Test Site (NTS), National Nuclear Security Administration (NNSA), LDRD, U.S. Department of Homeland Security (DHS), and U.S. Department of Defense (DoD) representatives; peer reviews of all FY 2007 projects; and the successful completion of 37 R&D projects, as presented in this report. In response to a company-wide call, authors throughout the NTS complex submitted 182 proposals for FY 2007 SDRD projects. The SDRD program has seen a dramatic increase in the yearly total of submitted proposals--from 69 in FY 2002 to 182 this year--while the number of projects funded has actually decreased from a program high of 57 in FY 2004. The overall effect of this trend has helped ensure an increasingly competitive program that benefited from a broader set of innovative ideas, making project selection both challenging and rewarding. Proposals were evaluated for technical merit, including such factors as innovation, probability of success, potential benefit, and mission applicability. Authors and reviewers benefited from the use of a shortfalls list entitled the 'NTS Technology Needs Assessment' that was compiled from NTS, National Weapons Laboratory

Deep Borehole Disposal as an Alternative Concept to Deep Geological Disposal

Energy Technology Data Exchange (ETDEWEB)

Lee, Jongyoul; Lee, Minsoo; Choi, Heuijoo; Kim, Kyungsu [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-10-15

In this paper, the general concept and key technologies for deep borehole disposal of spent fuels or HLW, as an alternative method to the mined geological disposal method, were reviewed. After then an analysis on the distance between boreholes for the disposal of HLW was carried out. Based on the results, a disposal area were calculated approximately and compared with that of mined geological disposal. These results will be used as an input for the analyses of applicability for DBD in Korea. The disposal safety of this system has been demonstrated with underground research laboratory and some advanced countries such as Finland and Sweden are implementing their disposal project on commercial stage. However, if the spent fuels or the high-level radioactive wastes can be disposed of in the depth of 3-5 km and more stable rock formation, it has several advantages. Therefore, as an alternative disposal concept to the mined deep geological disposal concept (DGD), very deep borehole disposal (DBD) technology is under consideration in number of countries in terms of its outstanding safety and cost effectiveness. In this paper, the general concept of deep borehole disposal for spent fuels or high level radioactive wastes was reviewed. And the key technologies, such as drilling technology of large diameter borehole, packaging and emplacement technology, sealing technology and performance/safety analyses technologies, and their challenges in development of deep borehole disposal system were analyzed. Also, very preliminary deep borehole disposal concept including disposal canister concept was developed according to the nuclear environment in Korea.

Deep Borehole Disposal as an Alternative Concept to Deep Geological Disposal

International Nuclear Information System (INIS)

Lee, Jongyoul; Lee, Minsoo; Choi, Heuijoo; Kim, Kyungsu

2016-01-01

In this paper, the general concept and key technologies for deep borehole disposal of spent fuels or HLW, as an alternative method to the mined geological disposal method, were reviewed. After then an analysis on the distance between boreholes for the disposal of HLW was carried out. Based on the results, a disposal area were calculated approximately and compared with that of mined geological disposal. These results will be used as an input for the analyses of applicability for DBD in Korea. The disposal safety of this system has been demonstrated with underground research laboratory and some advanced countries such as Finland and Sweden are implementing their disposal project on commercial stage. However, if the spent fuels or the high-level radioactive wastes can be disposed of in the depth of 3-5 km and more stable rock formation, it has several advantages. Therefore, as an alternative disposal concept to the mined deep geological disposal concept (DGD), very deep borehole disposal (DBD) technology is under consideration in number of countries in terms of its outstanding safety and cost effectiveness. In this paper, the general concept of deep borehole disposal for spent fuels or high level radioactive wastes was reviewed. And the key technologies, such as drilling technology of large diameter borehole, packaging and emplacement technology, sealing technology and performance/safety analyses technologies, and their challenges in development of deep borehole disposal system were analyzed. Also, very preliminary deep borehole disposal concept including disposal canister concept was developed according to the nuclear environment in Korea

The effect of young children's faeces disposal practices on child growth: evidence from 34 countries.

Science.gov (United States)

Bauza, Valerie; Guest, Jeremy S

2017-10-01

To characterize the relationship between child faeces disposal and child growth in low- and middle-income countries. We analysed caregiver responses and anthropometric data from Demographic and Health Surveys (2005-2014) for 202 614 children under five and 82 949 children under two to examine the association between child faeces disposal and child growth. Child faeces disposal in an improved toilet was associated with reduced stunting for children under five [adjusted prevalence ratio (aPR) = 0.90, 95% confidence interval (CI) 0.89-0.92] and a 0.12 increase in height-for-age z-score (HAZ; 95% CI: 0.10-0.15) among all households. Among households with improved sanitation access, practicing improved child faeces disposal was still associated with a decrease in stunting (aPR = 0.94, 95% CI: 0.91-0.96) and a 0.09 increase in HAZ (95% CI: 0.06-0.13). Improved child faeces disposal was also associated with reductions in underweight and wasting, and an increase in weight-for-age z-score (WAZ), but not an increase in weight-for-height z-score (WHZ). Community coverage level of improved child faeces disposal was also associated with stunting, with 75-100% coverage associated with the greatest reduction in stunting. Child faeces disposal in an unimproved toilet was associated with reductions in underweight and wasting, but not stunting. Improved child faeces disposal practices could achieve greater reductions in child undernutrition than improving toilet access alone. Additionally, the common classification of child faeces disposal as 'safe' regardless of the type of toilet used for disposal may underestimate the benefits of disposal in an improved toilet and overestimate the benefits of disposal in an unimproved toilet. © 2017 John Wiley & Sons Ltd.

Disposal and re-use of TENORM - legal limitations and obstacles

International Nuclear Information System (INIS)

Weiss, D.; Ettenhuber, E.

2004-01-01

While implementing EURATOM guideline 96/29 in the German legislation, in June of 2001 an essential pre-condition was created for re-use or disposal of TENORM. An essential progress has been achieved allowing to re-use TENORM or to dump it together with other residues and waste, if the specific activity does not exceed the limits defined in the radiation protection ordinance (StrlSchV). Otherwise, if the specified limits in terms of concentration or radiation dose are exceeded, than these materials must remain under radiological protection. A practical application of the new German regulation turns out to be difficult especially for disposal together with other waste and for re-use as backfilling material in mines taking into account problems arising from adaptation of the respective legislation on radiation protection, soil protection, waste management and shipment of dangerous goods. The report tackles obstacles for re-use and disposal of TENORM together with garbage and toxic waste arising from the new legislation. Otherwise, proposals will be given how obstacles of selected options for re-use and disposal can be overcome. (orig.)

2005 dossier. ANDRA's researches on the geological disposal of high-level and long-lived radioactive wastes. Results and perspectives

International Nuclear Information System (INIS)

2005-06-01

This document makes a status of the researches carried out by the French national agency of radioactive wastes (ANDRA) about the geologic disposal of high-level and long-lived radioactive wastes in deep geologic formations (argilites and granites). Content: 1 - Research on deep disposal of radioactive waste: general interest task: Legislative framework, ANDRA scientific objectives, Inspections and assessments; 2 - Designing a safe and reversible disposal system: Repository safety, Reversibility: an essential requirement; 3 - Clay Research on a repository in a clay formation, A long research programme, Dossier 2005 Argile; 4 - Meuse/Haute-Marne site clay: Expected properties of the rock formation, Choice of argillite, Meuse/Haute-Marne site, Conclusions from 10 years of research at the Meuse/Haute-Marne site; 5 - Repository installations: Safe and reversible architecture, Disposal of B waste, Disposal of C waste, Possible disposal of spent fuel (CU); 6 - The disposal facility in operation: From waste packages reception to their disposal in cells, Stages of the progressive closure of engineered structures; 7 - Reversible management: Freedom of choice for future generations, Various closure stages; 8 - Long-term evolution of the repository: Apprehending the repository complexity Main evolutions expected, Slow and limited release of radioactive substances; 9 - Repository safety and impact on man: Several evolution scenarios, Normal evolution, Altered evolution; 10 - Granite Research on a repository in a granite formation: A global approach, Scientific co-operations, Dossier 2005 Granite; 11 - Characteristics of French granite formations: What properties are required for a repository?, Different types of granite formations; 12 - Repository installations: Repository design adapted to granite fractures, Clay seals to prevent water flows, Waste disposal packages ensuring long-term leak-tightness, Physical and chemical environment favourable for waste packages, Architecture

Progress report for 1985/86 from the Waste Treatment and Disposal Working Party covering joint funded work

International Nuclear Information System (INIS)

Claxton, D.G.S.A.

1986-01-01

The Waste Treatment and Disposal Working Party (WTDWP) covered the areas of: ILW Product Evaluation, ILW and HLW Disposal Studies and ILW and HLW Quality Checking. The objectives of the programme were to evaluate potential waste products arising from the treatment of ILW, and to develop appropriate techniques which could be used to check the quality of the finished waste product. (author)

Corrective Action Plan for Corrective Action Unit 139: Waste Disposal Sites, Nevada Test Site, Nevada

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Restoration

2007-07-01

Corrective Action Unit (CAU) 139, Waste Disposal Sites, is listed in the Federal Facility Agreement and Consent Order (FFACO) of 1996 (FFACO, 1996). CAU 139 consists of seven Corrective Action Sites (CASs) located in Areas 3, 4, 6, and 9 of the Nevada Test Site (NTS), which is located approximately 65 miles (mi) northwest of Las Vegas, Nevada (Figure 1). CAU 139 consists of the following CASs: CAS 03-35-01, Burn Pit; CAS 04-08-02, Waste Disposal Site; CAS 04-99-01, Contaminated Surface Debris; CAS 06-19-02, Waste Disposal Site/Burn Pit; CAS 06-19-03, Waste Disposal Trenches; CAS 09-23-01, Area 9 Gravel Gertie; and CAS 09-34-01, Underground Detection Station. Details of the site history and site characterization results for CAU 139 are provided in the approved Corrective Action Investigation Plan (CAIP) (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2006) and in the approved Corrective Action Decision Document (CADD) (NNSA/NSO, 2007). The purpose of this Corrective Action Plan (CAP) is to present the detailed scope of work required to implement the recommended corrective actions as specified in Section 4.0 of the approved CADD (NNSA/NSO, 2007). The approved closure activities for CAU 139 include removal of soil and debris contaminated with plutonium (Pu)-239, excavation of geophysical anomalies, removal of surface debris, construction of an engineered soil cover, and implementation of use restrictions (URs). Table 1 presents a summary of CAS-specific closure activities and contaminants of concern (COCs). Specific details of the corrective actions to be performed at each CAS are presented in Section 2.0 of this report.

Corrective Action Plan for Corrective Action Unit 139: Waste Disposal Sites, Nevada Test Site, Nevada

International Nuclear Information System (INIS)

NSTec Environmental Restoration

2007-01-01

Corrective Action Unit (CAU) 139, Waste Disposal Sites, is listed in the Federal Facility Agreement and Consent Order (FFACO) of 1996 (FFACO, 1996). CAU 139 consists of seven Corrective Action Sites (CASs) located in Areas 3, 4, 6, and 9 of the Nevada Test Site (NTS), which is located approximately 65 miles (mi) northwest of Las Vegas, Nevada (Figure 1). CAU 139 consists of the following CASs: CAS 03-35-01, Burn Pit; CAS 04-08-02, Waste Disposal Site; CAS 04-99-01, Contaminated Surface Debris; CAS 06-19-02, Waste Disposal Site/Burn Pit; CAS 06-19-03, Waste Disposal Trenches; CAS 09-23-01, Area 9 Gravel Gertie; and CAS 09-34-01, Underground Detection Station. Details of the site history and site characterization results for CAU 139 are provided in the approved Corrective Action Investigation Plan (CAIP) (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2006) and in the approved Corrective Action Decision Document (CADD) (NNSA/NSO, 2007). The purpose of this Corrective Action Plan (CAP) is to present the detailed scope of work required to implement the recommended corrective actions as specified in Section 4.0 of the approved CADD (NNSA/NSO, 2007). The approved closure activities for CAU 139 include removal of soil and debris contaminated with plutonium (Pu)-239, excavation of geophysical anomalies, removal of surface debris, construction of an engineered soil cover, and implementation of use restrictions (URs). Table 1 presents a summary of CAS-specific closure activities and contaminants of concern (COCs). Specific details of the corrective actions to be performed at each CAS are presented in Section 2.0 of this report

Quarterly report on program cost and schedule: Fourth quarter FY 1988

International Nuclear Information System (INIS)

1988-01-01

Major program milestones completed in the fourth quarter of FY 1988 include completed preliminary draft NWPAA Section 175 Impacts Report, completed Title I ESF design, completed site reclamation in Texas, distributed review draft of the Dry Cask Storage Study, completed draft and final FY 1990 OMB budget, issued FY 1987 Annual Report to Congress, issued four draft Environmental Field Activity Plans, issued draft Environmental Program Overview, and made grant payments to local governments under Section 116 of NWPA, as amended. Major accomplishments during the fourth quarter of FY 1988 are listed. The Water Appropriation Permit Application was filed with the Nevada State Engineer on July 21, 1988. Installation and checkout of the Prototype Engineered Barrier Test equipment in G-tunnel is continuing with an expected early September test initiation data. The Configuration Management Plan was sent to DOE/HQ for approval. The prototype facility for testing the horizontal waste package emplacement configuration was completed in the G-tunnel

U.S. Geological Survey research in radioactive waste disposal - Fiscal years 1983, 1984, and 1985

Science.gov (United States)

Dinwiddie, G.A.; Trask, N.J.

1986-01-01

The report summarizes progress on geologic and hydrologic research related to the disposal of radioactive wastes. The research is described according to whether it is related most directly to: (1) high-level and transuranic wastes, (2) low-level wastes, or (3) uranium mill tailings. Included is research applicable to the identification and geohydrologic characterization of waste-disposal sites, to investigations of specific sites where wastes have been stored, and to studies of regions or environments where waste-disposal sites might be located. A significant part of the activity is concerned with techniques and methods for characterizing disposal sites and studies of geologic and hydrologic processes related to the transport and (or) retention of waste radionuclides.

Studies on engineering technologies in the Mizunami Underground Research Laboratory. FY 2007 (Contract research)

International Nuclear Information System (INIS)

Noda, Masaru; Suyama, Yasuhiro; Nobuto, Jun; Ijiri, Yuji; Mikake, Shinichiro; Matsui, Hiroya

2009-07-01

The Mizunami Underground Research Laboratory (MIU) of the Japan Atomic Energy Agency is a major site for geoscientific research to advance the scientific and technological basis for geological disposal of high-level radioactive waste in crystalline rock. Studies on relevant engineering technologies in the MIU consist of a) research on design and construction technology for very deep underground applications, and b) research on engineering technology as a basis of geological disposal. In the Second Phase of the MIU project (the construction phase), engineering studies have focused on research into design and construction technologies for deep underground. The main subjects in the study of very deep underground structures consist of the following: 'Demonstration of the design methodology', 'Demonstration of existing and supplementary excavation methods', 'Demonstration of countermeasures during excavation' and 'Demonstration of safe construction'. In the FY 2007 studies, identification and evaluation of the subjects for study of engineering technologies in the construction phase were carried out to optimize future research work. Specific studies included: validation of the existing design methodology based on data obtained during construction; validation of existing and supplementary rock excavation methods for very deep shafts; estimation of rock stability under high differential water pressures, methodology on long-term maintenance of underground excavations and risk management systems for construction of underground structures have been performed. Based on these studies, future research focused on the four subject areas, which are 'Demonstration of the design methodology', 'Demonstration of existing and supplementary excavation methods', 'Demonstration of countermeasures during excavation' and 'Demonstration of safe construction', has been identified. The design methodology in the first phase of the MIU Project (surface-based investigation phase) was verified to

Summary report on safety and licensing strategy support for the ABR prototype

International Nuclear Information System (INIS)

Cahalan, J. E.; Nuclear Engineering Division

2007-01-01

Argonne National Laboratory is providing support to the US Department of Energy in the Global Nuclear Energy Partnership (GNEP) in certification of an advanced, sodium-cooled fast reactor. The reactor is to be constructed as a prototype for future commercial power reactors that will produce electricity while consuming actinides recovered from light water reactor spent fuel. This prototype reactor has been called the Advanced Burner Reactor, or ABR, and is now often referred to as the advanced recycle reactor. As part of its activities, Argonne is providing technical services to assist definition of a safety and licensing strategy for the ABR prototype, and to further implementation of the strategy. In FY06, an organizational meeting was held for DOE and its laboratory contractors to discuss licensing alternatives and review previous licensing experience for the Fast Flux Test Facility (FFTF) and the Clinch River Breeder Reactor Plant (CRBRP). Near the end of FY06, a report summarizing the discussions and conclusions was written. One of the top-level conclusions recorded in the report was a recommendation to follow a licensing strategy that included the US Nuclear Regulatory Commission (NRC) as the regulatory review and licensing authority. In FY07, activities ar Argonne to support safety and licensing progress have continued. These activities have focused on further evaluation of licensing alternatives; assessment of design, analysis, and documentation implications of licensing paths; and initial technical interactions with the Nuclear Regulatory Commission. This report summarizes FY07 activities

Fusion Reactor Safety Research program. Annual report, FY-80

International Nuclear Information System (INIS)

Crocker, J.G.; Cohen, S.

1981-06-01

The report is in three sections. Outside contracts includes a report of newly-started study at the General Atomic Company to consider safety implications of low-activation materials, portions of two papers from ongoing work at PNL and ANL, reports of the lithium spill work at HEDL, the LITFIRE code development at MIT, and risk assessment at MIT, all of which are an expansion of FY-79 outside contracts. EG and G Activities includes adaptations of four papers of ongoing work in transient code development, tritium system risk assessment, heat transfer and fluid flow analysis, and fusion safety data base. Program Plan Development includes the Executive Summary of the Plan, which was completed in FY-80, and is accompanied by a list of publications and a brief outline of proposed FY-81 activities to be based on the Program Plan

Cementitious Barriers Partnership - FY2015 End-Year Report

International Nuclear Information System (INIS)

Burns, H. H.; Flach, G. P.; Langton, C. A.; Smith, F. G.; Kosson, D. S.; Meeussen, J. C. L.; Seignette, Paul; Van der Sloot, H. A.

2015-01-01

The DOE-EM Office of Tank Waste Management Cementitious Barriers Partnership (CBP) is chartered with providing the technical basis for implementing cement-based waste forms and radioactive waste containment structures for long-term disposal. Therefore, the CBP ultimate purpose is to support progress in final treatment and disposal of legacy waste and closure of High-Level Waste (HLW) tanks in the DOE complex. This status report highlights the CBP 2015 Software and Experimental Program efforts and accomplishments that support DOE needs in environmental cleanup and waste disposal. DOE needs in this area include: Long-term performance predictions to provide credibility (i.e., a defensible technical basis) for regulator and DOE review and approvals, Facility flow sheet development/enhancements, and Conceptual designs for new disposal facilities. In 2015, the CBP developed a beta release of the CBP Software Toolbox - ''Version 3.0'', which includes new STADIUM carbonation and damage models, a new SRNL module for estimating hydraulic properties and flow in fractured and intact cementitious materials, and a new LeachXS/ORCHESTRA (LXO) oxidation module. In addition, the STADIUM sulfate attack and chloride models have been improved as well as the LXO modules for sulfate attack, carbonation, constituent leaching, and percolation with radial diffusion (for leaching and transport in cracked cementitious materials). These STADIUM and LXO models are applicable to and can be used by both DOE and the Nuclear Regulatory Commission (NRC) end-users for service life prediction and long-term leaching evaluations of radioactive waste containment structures across the DOE complex.

Cementitious Barriers Partnership - FY2015 End-Year Report

Energy Technology Data Exchange (ETDEWEB)

Burns, H. H. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Flach, G. P. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Langton, C. A. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Smith, F. G. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Kosson, D. S. [Vanderbilt Univ., Nashville, TN (United States). School of Engineering; Brown, K. G. [Vanderbilt Univ., Nashville, TN (United States). School of Engineering; Samson, E. [SIMCO Technologies, Inc., QC (Canada); Meeussen, J. C. L. [Nuclear Research and Consultancy Group (NRG); Seignette, Paul [Energy Research Center of the Netherlands; van der Sloot, H. A. [Hans van der Sloot Consultancy

2015-09-17

The DOE-EM Office of Tank Waste Management Cementitious Barriers Partnership (CBP) is chartered with providing the technical basis for implementing cement-based waste forms and radioactive waste containment structures for long-term disposal. Therefore, the CBP ultimate purpose is to support progress in final treatment and disposal of legacy waste and closure of High-Level Waste (HLW) tanks in the DOE complex. This status report highlights the CBP 2015 Software and Experimental Program efforts and accomplishments that support DOE needs in environmental cleanup and waste disposal. DOE needs in this area include: Long-term performance predictions to provide credibility (i.e., a defensible technical basis) for regulator and DOE review and approvals, Facility flow sheet development/enhancements, and Conceptual designs for new disposal facilities. In 2015, the CBP developed a beta release of the CBP Software Toolbox – “Version 3.0”, which includes new STADIUM carbonation and damage models, a new SRNL module for estimating hydraulic properties and flow in fractured and intact cementitious materials, and a new LeachXS/ORCHESTRA (LXO) oxidation module. In addition, the STADIUM sulfate attack and chloride models have been improved as well as the LXO modules for sulfate attack, carbonation, constituent leaching, and percolation with radial diffusion (for leaching and transport in cracked cementitious materials). These STADIUM and LXO models are applicable to and can be used by both DOE and the Nuclear Regulatory Commission (NRC) end-users for service life prediction and long-term leaching evaluations of radioactive waste containment structures across the DOE complex.

Seabed disposal program: a first-year report, December 1974

International Nuclear Information System (INIS)

Bishop, W.P.

1975-03-01

A summary is given of the progress made by a study group, composed of persons from many disciplines and organizations, which was formed to examine certain areas of the world's oceans to determine whether it is feasible to use such areas, or the ocean floor beneath them, as permanent disposal sites for high-level nuclear wastes. (U.S.)

The development and status of performance assessment in radioactive waste disposal

International Nuclear Information System (INIS)

McCombie, C.; Papp, T.; Coplan, S.

1990-01-01

The development of formal performance assessment in radioactive waste disposal has been in progress for around 10-15 years now. The time is particularly opportune for a review of the state-of-the-art because of current changes in the status of repository planning and implementation worldwide. Several major feasibility-type studies have been completed, the first full site-specific safety analyses are being performed for engineered underground disposal facilities for L/ILW, and - for HLW - the die are now being cast by implementers and regulatory determining how the safety analyses for licensing are to be performed and assessed. The article reviews the development of performance assessment and attempts to identify some key issues occupying safety analysts and regulatory reviewers involved in waste disposal today. (author) 7 figs

Supply and demand outlook for Japan's economic and energy up to FY2018

International Nuclear Information System (INIS)

Aoshima, Momoko; Yorita, Yasuo; Tsunoda, Miyuki

2017-01-01

Japan's economy has gradually expanded, with real GDP in the first quarter of 2017 becoming positive growth for five consecutive quarters for the first time since 2005 to 2006. Although the uncertain factors are increasing both in terms of politics and economy, the world economy is also growing moderately. As the main premises in the standard scenario, the following are supposed: (1) world economy grows moderately, with worldwide growth rate reaching 3.0% in FY2017 and 3.3% in FY2018, (2) exchange rate is about ¥115/$ in both FY2017 and FY2018 average, (3) as for nuclear power generation, cumulative restarted unit number reaches 10 basis until the end of FY2018, with average months of operation in FY2018 reaching 9 months, and with power generation amount reaching 65.6 billion kWh (7% of the power supply composition ratio), and (4) as for the supply and demand for power, the supply reserve ratio of 3% necessary for stable electric power supply can be secured nationwide. Thus, the supply and demand outlook for Japan's economic and energy up to FY2018 was made. The following various evaluation analyses were carried out: (1) macro economy, (2) production activities, (3) primary energy domestic supply, (4) final energy consumption, (5) electricity sales volume and power supply composition (electric power companies), (6) city gas sales volume (gas companies), fuel oil and LPG sales volume and crude oil throughput, and (7) in-depth analysis; demand trend of light oil, renewable energy power generation, and effects of restart of nuclear power plants. (A.O.)

State, Foreign Operations, and Related Programs: FY2008 Appropriations

Science.gov (United States)

2007-12-14

and social reforms. The President initially pledged $5 billion annually by FY2006, although funds requested and appropriated have never reached this...to Cuba. The BBG is planning to eliminate several VOA services including Uzbek, Greek, and Cantonese as well as the RFE/RL Macedonia service. BBG also...increased to $230.0 million. The increase of $195 million is entirely for social services to Iraqi refugees. FY2007 Supplemental Request. On April 25

Nuclear fuel waste disposal. Canada's consultative approach

International Nuclear Information System (INIS)

Hillier, J.A.R.; Dixon, R.S.

1993-01-01

Over the past two decades, society has increasingly demanded more public participation and public input into decision-making by governments. Development of the Canadian concept for deep geological disposal of used nuclear fuel has proceeded in a manner that has taken account of the requirements for social acceptability as well as technical excellence. As the agency responsible for development of the disposal concept, Atomic Energy of Canada Limited (AECL) has devoted considerable effort to consultation with the various publics that have an interest in the concept. This evolutionary interactive and consultative process, which has been underway for some 14 years, has attempted to keep the public informed of the technical development of the concept and to invite feedback. This paper describes the major elements of this evolutionary process, which will continue throughout the concept assessment and review process currently in progress. (author)

Nuclear fuel waste disposal. Canada's consultative approach

Energy Technology Data Exchange (ETDEWEB)

Hillier, J A.R.; Dixon, R S [AECL (Canada)

1993-07-01

Over the past two decades, society has increasingly demanded more public participation and public input into decision-making by governments. Development of the Canadian concept for deep geological disposal of used nuclear fuel has proceeded in a manner that has taken account of the requirements for social acceptability as well as technical excellence. As the agency responsible for development of the disposal concept, Atomic Energy of Canada Limited (AECL) has devoted considerable effort to consultation with the various publics that have an interest in the concept. This evolutionary interactive and consultative process, which has been underway for some 14 years, has attempted to keep the public informed of the technical development of the concept and to invite feedback. This paper describes the major elements of this evolutionary process, which will continue throughout the concept assessment and review process currently in progress. (author)