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  1. Green Systems UK | Open Energy Information

    Open Energy Info (EERE)

    Systems UK Jump to: navigation, search Name: Green Systems UK Place: Cambridge, United Kingdom Sector: Solar Product: Design and installation of vacuum tube & flat plate solar hot...

  2. Cambridge Structural Database

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Cambridge Structural Database Cambridge Structural Database LANL researchers can access WebCSD from offsite via Remote Access. Question? 667-5809 Email Cambridge Structural Database (CSD) includes bibliographic, chemical, and crystallographic information for organic molecules and metal-organic compounds. The crystal structure data comes from the open literature or direct deposits by researchers. The CSD System incorporations a suite of flexible search and analysis tools. The Research Library

  3. Cambridge Energy Alliance | Open Energy Information

    Open Energy Info (EERE)

    Logo: Cambridge Energy Alliance Name: Cambridge Energy Alliance Address: 1385 Cambridge St Place: Cambridge, Massachusetts Zip: 02139 Region: Greater Boston Area Website:...

  4. Cambridge Enterprise | Open Energy Information

    Open Energy Info (EERE)

    Enterprise Jump to: navigation, search Name: Cambridge Enterprise Place: United Kingdom Sector: Services Product: General Financial & Legal Services ( Subsidiary Division )...

  5. Cambridge Design & Development | Open Energy Information

    Open Energy Info (EERE)

    Design & Development Jump to: navigation, search Name: Cambridge Design & Development Place: Cambridge, MA Information About Partnership with NREL Partnership with NREL Yes...

  6. Cambridge Project Development | Open Energy Information

    Open Energy Info (EERE)

    Project Development Jump to: navigation, search Name: Cambridge Project Development Place: Miami, Florida Product: Florida-based firm that builds wate management and waste to...

  7. Cambridge Energy Research Associates CERA | Open Energy Information

    Open Energy Info (EERE)

    Associates CERA Jump to: navigation, search Name: Cambridge Energy Research Associates (CERA) Place: Cambridge, Massachusetts Zip: 2142 Sector: Services Product: Prominent provider...

  8. Cambridge, Wisconsin: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    Hide Map This article is a stub. You can help OpenEI by expanding it. Cambridge is a village in Dane County and Jefferson County, Wisconsin. It falls under...

  9. Cambridge Funds Investment Co Ltd | Open Energy Information

    Open Energy Info (EERE)

    Funds Investment Co Ltd Jump to: navigation, search Name: Cambridge Funds Investment Co, Ltd. Place: Cambridge, England, United Kingdom Zip: CB3 9LF Product: The company buy and...

  10. Fermilab Today | University of Cambridge Profile

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    era of modern physics. Today we are gearing up for the new discoveries we hope will emerge in the coming decade. FUNDING AGENCY: UK Science and Technology Facilities Council...

  11. Jo Sexton, President, Cambridge Area Chamber of Commerce Panel...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Outliine for QER July 21, 2014 Jo Sexton, President, Cambridge Area Chamber of Commerce Panel 3 Public-Private Partnerships for Economic Growth and Workforce Development How a ...

  12. Cambridge Display Technology Ltd CDT | Open Energy Information

    Open Energy Info (EERE)

    Technology Ltd CDT Jump to: navigation, search Name: Cambridge Display Technology Ltd (CDT) Place: Cambridgeshire, United Kingdom Zip: CB3 6DW Product: A major player in the...

  13. SEMI-ANNUAL REPORTS FOR CE FLNG, LLC (CAMBRIDGE) - DK. NO. 12...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    CE FLNG, LLC (CAMBRIDGE) - DK. NO. 12-123-LNG - ORDER 3193 SEMI-ANNUAL REPORTS FOR CE FLNG, LLC (CAMBRIDGE) - DK. NO. 12-123-LNG - ORDER 3193 PDF icon April 2013 PDF icon October...

  14. A Tour of Plasma Physics in Downtown Cambridge | Princeton Plasma Physics

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Lab A Tour of Plasma Physics in Downtown Cambridge American Fusion News Category: Massachusetts Institute of Technology (MIT) Link: A Tour of Plasma Physics in Downtown Cambridge

  15. Hammerfest UK | Open Energy Information

    Open Energy Info (EERE)

    Hammerfest UK Place: Scotland, United Kingdom Product: ScottishPower and Norwegian technology company Hammerfest Strm set up a new tidal power company Hammerfest UK utilising...

  16. Ebony Solutions UK | Open Energy Information

    Open Energy Info (EERE)

    Ebony Solutions UK Jump to: navigation, search Name: Ebony Solutions UK Place: Northwich, Cheshire, United Kingdom Zip: CW8 2SX Product: A UK biodiesel manufacturer. References:...

  17. Building America Case Study: Boiler Control Replacement for Hydronically Heated Multifamily Buildings, Cambridge, Massachusetts (Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2014-11-01

    The ARIES Collaborative, a U.S. Department of Energy Building America research team, partnered with NeighborWorks America affiliate Homeowners' Rehab Inc. (HRI) of Cambridge, Massachusetts, to study improvements to the central hydronic heating system in one of the nonprofit's housing developments. The heating controls in the three-building, 42-unit Columbia Cambridge Alliance for Spanish Tenants housing development were upgraded. Fuel use in the development was excessive compared to similar properties. A poorly insulated thermal envelope contributed to high energy bills, but adding wall insulation was not cost-effective or practical. The more cost-effective option was improving heating system efficiency. Efficient operation of the heating system faced several obstacles, including inflexible boiler controls and failed thermostatic radiator valves. Boiler controls were replaced with systems that offer temperature setbacks and one that controls heat based on apartment temperature in addition to outdoor temperature. Utility bill analysis shows that post-retrofit weather-normalized heating energy use was reduced by 10%-31% (average of 19%). Indoor temperature cutoff reduced boiler runtime (and therefore heating fuel consumption) by 28% in the one building in which it was implemented. Nearly all savings were obtained during night which had a lower indoor temperature cut off (68 degrees F) than day (73 degrees F). This implies that the outdoor reset curve was appropriately adjusted for this building for daytime operation. Nighttime setback of heating system supply water temperature had no discernable impact on boiler runtime or gas bills.

  18. Technology Solutions Case Study: Boiler Control Replacement for Hydronically Heated Multifamily Buildings, Cambridge, Massachusetts

    SciTech Connect (OSTI)

    2014-11-01

    The ARIES Collaborative, a U.S. Department of Energy Building America research team, partnered with NeighborWorks America affiliate Homeowners' Rehab Inc. (HRI) of Cambridge, Massachusetts, to study improvements to the central hydronic heating system in one of the nonprofit's housing developments. The heating controls in the three-building, 42-unit Columbia Cambridge Alliance for Spanish Tenants housing development were upgraded. Fuel use in the development was excessive compared to similar properties. A poorly insulated thermal envelope contributed to high energy bills, but adding wall insulation was not cost-effective or practical. The more cost-effective option was improving heating system efficiency, which faced several obstacles, including inflexible boiler controls and failed thermostatic radiator valves. Boiler controls were replaced with systems that offer temperature setbacks and one that controls heat based on apartment temperature in addition to outdoor temperature. Utility bill analysis shows that post-retrofit weather-normalized heating energy use was reduced by 10%-31% (average of 19%). Indoor temperature cutoff reduced boiler runtime (and therefore heating fuel consumption) by 28% in the one building in which it was implemented. Nearly all savings were obtained during night which had a lower indoor temperature cut off (68°F) than day (73° F). This implies that the outdoor reset curve was appropriately adjusted for this building for daytime operation. Nighttime setback of heating system supply water temperature had no discernable impact on boiler runtime or gas bills.

  19. Gamesa Energy UK | Open Energy Information

    Open Energy Info (EERE)

    UK Place: Newport, Wales, United Kingdom Zip: NP10 8FY Sector: Wind energy Product: UK arm of wind farm developer and turbine manufacturer Gamesa. References: Gamesa Energy UK1...

  20. Biodiesel Filling Stations UK | Open Energy Information

    Open Energy Info (EERE)

    Filling Stations UK Jump to: navigation, search Name: Biodiesel Filling Stations UK Place: United Kingdom Product: A website providing a list of places in the UK where people can...

  1. FIAMM UK Ltd | Open Energy Information

    Open Energy Info (EERE)

    search Name: FIAMM UK Ltd Place: United Kingdom Product: UK Division of Fiamm, battery manufacturer. References: FIAMM UK Ltd1 This article is a stub. You can help OpenEI...

  2. M Cauldwell UK Ltd | Open Energy Information

    Open Energy Info (EERE)

    Cauldwell UK Ltd Jump to: navigation, search Name: M Cauldwell UK Ltd Place: United Kingdom Sector: Wind energy Product: UK-based private developer, Mark Cauldwell, involved in the...

  3. Solargen Solutions UK | Open Energy Information

    Open Energy Info (EERE)

    Solargen Solutions UK Jump to: navigation, search Name: Solargen Solutions UK Place: United Kingdom Zip: NP 44 3AS Sector: Renewable Energy, Solar Product: String representation...

  4. Ryle Technology Ltd UK | Open Energy Information

    Open Energy Info (EERE)

    Technology Ltd UK Place: United Kingdom Sector: Wind energy Product: Focused on wind blade technology development. References: Ryle Technology Ltd UK1 This article is a stub....

  5. Building America Case Study: Boiler Control Replacement for Hydronically Heated Multifamily Buildings, Cambridge, Massachusetts (Fact Sheet), Technology Solutions for New and Existing Homes, Energy Efficiency & Renewable Energy (EERE)

    Energy Savers [EERE]

    Boiler Control Replacement for Hydronically Heated Multifamily Buildings Cambridge, Massachusetts PROJECT INFORMATION Project Name: Cambridge Alliance for Spanish Tenants Apartments Location: Cambridge, MA Partners: Homeowners Rehab, Inc., homeownersrehab.org Advanced Residential Integrated Solutions Collaborative, levypartnership.com Building Component: HVAC Application: Retrofit, multifamily Year Tested: 2010-2013 Applicable Climate Zone(s): Mixed-Humid and Cold PERFORMANCE DATA Cost of energy

  6. Plasma-Surface Interaction Research At The Cambridge Laboratory Of Accelerator Studies Of Surfaces

    SciTech Connect (OSTI)

    Wright, G. M.; Barnard, H. S.; Hartwig, Z. S.; Stahle, P. W.; Sullivan, R. M.; Woller, K. B.; Whyte, D. G.

    2011-06-01

    The material requirements for plasma-facing components in a nuclear fusion reactor are some of the strictest and most challenging facing us today. These materials are simultaneously exposed to extreme heat loads (20 MW/m{sup 2} steady-state, 1 GW/m{sup 2} in millisecond transients) and particle fluxes (>10{sup 24} m{sup -2} s{sup -1}) while also undergoing high neutron irradiation (10{sup 18} neutrons/m{sup 2} s). At the Cambridge Laboratory of Accelerator Studies of Surfaces (CLASS), many of the most important issues in plasma-surface interaction research, such as plasma-driven material erosion and deposition, material transport and irradiation and hydrogenic retention are investigated with the use of a 1.7 MV tandem ion accelerator. Ion-Beam Analysis (IBA) is used to investigate and quantify changes in materials due to plasma exposure and ion irradiation is used as a proxy for neutron irradiation to investigate plasma-surface interactions for irradiated materials. This report will outline the capabilities and current research activities at CLASS.

  7. Bioflame Mid UK Recycling JV | Open Energy Information

    Open Energy Info (EERE)

    search Name: Bioflame & Mid-UK Recycling JV Place: England, United Kingdom Product: Joint Venture between Bioflame and Mid-UK Recycling References: Bioflame & Mid-UK...

  8. Renewable Energy Systems (RES UK and Ireland) | Open Energy Informatio...

    Open Energy Info (EERE)

    (RES UK and Ireland) Jump to: navigation, search Logo: Renewable Energy Systems (RES UK and Ireland) Name: Renewable Energy Systems (RES UK and Ireland) Address: Beaufort Court Egg...

  9. O Gen UK Ltd | Open Energy Information

    Open Energy Info (EERE)

    Gen UK Ltd Jump to: navigation, search Name: O-Gen UK Ltd Place: Stone, United Kingdom Zip: ST15 8XU Sector: Biomass Product: Power generator from biomass. Coordinates:...

  10. IdaTech UK | Open Energy Information

    Open Energy Info (EERE)

    IdaTech UK Place: United Kingdom Product: Former UK subsidiary of US PEM fuel cell developer, IdaTech LLC, which completed acquisition of the parent company in July 2006....

  11. Novera Energy UK Ltd | Open Energy Information

    Open Energy Info (EERE)

    UK Ltd Place: Warrington, United Kingdom Zip: WA4 6HL Product: Novera was a landfill gas-to-power business in the UK acquired by Primergy in 2002 and folded into Novera...

  12. PNE WIND UK | Open Energy Information

    Open Energy Info (EERE)

    search Name: PNE WIND UK Place: United Kingdom Sector: Wind energy Product: UK-based joint venture between PNE Wind and New Energy Development Ltd for the development of 300MW...

  13. PNE UK Wind | Open Energy Information

    Open Energy Info (EERE)

    search Name: PNE UK Wind Place: United Kingdom Sector: Wind energy Product: UK-based joint venture looking to develop a 300MW portfolio of wind farm projects across England,...

  14. UK Energy Systems Ltd | Open Energy Information

    Open Energy Info (EERE)

    UK subsisidary of US firm. Focused on renewable energy projects and cogeneration power plants. The US arm owns and operates 26 LFG-to-energy plants totalling 60MW. References: UK...

  15. Eneco Wind UK | Open Energy Information

    Open Energy Info (EERE)

    United Kingdom Sector: Wind energy Product: Eneco Wind UK is a subsidiary of Eneco Energie, a Dutch energy supplier. References: Eneco Wind UK1 This article is a stub. You...

  16. UK mining invests, suppliers profit

    SciTech Connect (OSTI)

    2009-04-15

    In the midst of a major economic crisis in the United Kingdom, equipment suppliers have been reporting a number of considerable purchases by British coal mining companies. In December 2008, Liebherr-Great Britain delivered the first two of four Rq350 Litronic hydraulic excavators for use at the Broken Cross opencast coal site in Lanarkshire, Scotland. Ten Terex TR100 rigid haulers were delivered to the site in late 2008. Hatfield Colliery at Stainforth, South Yorkshire, has been reopened by PowerFuel. The main equipment for two longwall faces was supplied by Joy Mining Machinery UK Ltd. 2 photos.

  17. Enertrag UK Ltd | Open Energy Information

    Open Energy Info (EERE)

    Ltd Place: United Kingdom Sector: Wind energy Product: Involved throught the SPV Norfolk Offshore Wind in the development of Cromer Offshore Wind Farm. References: Enertrag UK...

  18. Good Energy UK | Open Energy Information

    Open Energy Info (EERE)

    Good Energy UK Place: Wiltshire, United Kingdom Zip: SN15 1ER Sector: Renewable Energy Product: Supplier of renewable electricity to homes and businesses. References: Good Energy...

  19. Safety Basis Report

    SciTech Connect (OSTI)

    R.J. Garrett

    2002-01-14

    As part of the internal Integrated Safety Management Assessment verification process, it was determined that there was a lack of documentation that summarizes the safety basis of the current Yucca Mountain Project (YMP) site characterization activities. It was noted that a safety basis would make it possible to establish a technically justifiable graded approach to the implementation of the requirements identified in the Standards/Requirements Identification Document. The Standards/Requirements Identification Documents commit a facility to compliance with specific requirements and, together with the hazard baseline documentation, provide a technical basis for ensuring that the public and workers are protected. This Safety Basis Report has been developed to establish and document the safety basis of the current site characterization activities, establish and document the hazard baseline, and provide the technical basis for identifying structures, systems, and components (SSCs) that perform functions necessary to protect the public, the worker, and the environment from hazards unique to the YMP site characterization activities. This technical basis for identifying SSCs serves as a grading process for the implementation of programs such as Conduct of Operations (DOE Order 5480.19) and the Suspect/Counterfeit Items Program. In addition, this report provides a consolidated summary of the hazards analyses processes developed to support the design, construction, and operation of the YMP site characterization facilities and, therefore, provides a tool for evaluating the safety impacts of changes to the design and operation of the YMP site characterization activities.

  20. Implementing Agreement - U.S.-UK Collaboration in Fossil Energy...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Implementing Agreement - U.S.-UK Collaboration in Fossil Energy R&D Implementing Agreement - U.S.-UK Collaboration in Fossil Energy R&D PDF icon Implementing Agreement - U.S.-UK ...

  1. Technical Planning Basis

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2007-07-11

    The Guide assists DOE/NNSA field elements and operating contractors in identifying and analyzing hazards at facilities and sites to provide the technical planning basis for emergency management programs. Supersedes DOE G 151.1-1, Volume 2.

  2. E ON Climate Renewables UK formerly Powergen Renewable Energy...

    Open Energy Info (EERE)

    UK formerly Powergen Renewable Energy Holdings Jump to: navigation, search Name: E.ON Climate & Renewables UK (formerly Powergen Renewable Energy Holdings) Place: Coventry,...

  3. UK Centre for Marine Renewable Energy | Open Energy Information

    Open Energy Info (EERE)

    Centre for Marine Renewable Energy Jump to: navigation, search Name: UK Centre for Marine Renewable Energy Place: United Kingdom Sector: Renewable Energy Product: UK Centre for...

  4. Renewable Energy Association UK REA | Open Energy Information

    Open Energy Info (EERE)

    Association UK REA Jump to: navigation, search Name: Renewable Energy Association UK (REA) Place: London, United Kingdom Zip: SW1Y 4AR Sector: Renewable Energy Product: Trade...

  5. EC Power UK Ltd | Open Energy Information

    Open Energy Info (EERE)

    UK Ltd Place: Bristol, England, United Kingdom Zip: BS37 6JL Product: Micro combined heat and power plant manufacturer (<18kWe). Coordinates: 42.55678, -88.050449 Show Map...

  6. Adelan UK Ltd | Open Energy Information

    Open Energy Info (EERE)

    UK Ltd Place: Birmingham, United Kingdom Zip: B15 2SQ Product: A small solid oxide fuel cell (SOFC) which has developed an innovative microtubular fuel cell unit design....

  7. Fuel Cells UK | Open Energy Information

    Open Energy Info (EERE)

    United Kingdom Zip: NN14 3ED Product: An industry association of the UK fuel cell industry whose mission is to foster the development of the industry. References: Fuel...

  8. UK Ministry of Defence | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search Name: UK Ministry of Defence Place: London, Greater London, United Kingdom Zip: SW1A 2HB Product: Government body responsible for defence in the...

  9. Ultracell UK Ltd | Open Energy Information

    Open Energy Info (EERE)

    Ultracell (UK) Ltd Place: Liverpool, United Kingdom Zip: L30 4XL Product: Distributor of rechargeable sealed lead acid batteries. Coordinates: 53.409773, -2.978481 Show Map...

  10. UK FT PDU Facility Draft EA

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    UK's CAER, on a parcel of land within an existing 125-acre ... impacts to the human and natural environment of its ... and acid gas cleanup components of the facility. ...

  11. Confidentiality Agreement between the US Department of Energy, the UK

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Nuclear Decommissioning Authority, and the UK National Nuclear Laboratory Limited, 2015 | Department of Energy Confidentiality Agreement between the US Department of Energy, the UK Nuclear Decommissioning Authority, and the UK National Nuclear Laboratory Limited, 2015 Confidentiality Agreement between the US Department of Energy, the UK Nuclear Decommissioning Authority, and the UK National Nuclear Laboratory Limited, 2015 PDF icon Confidentiality Agreement between the US Department of

  12. Global Commodities UK Ltd defunct | Open Energy Information

    Open Energy Info (EERE)

    7LZ Product: UK-based biodiesel producer and developer of driveECO, a biodegradable diesel. Went into liquidation in 2006. References: Global Commodities UK Ltd (defunct)1...

  13. REG Bio power UK Ltd | Open Energy Information

    Open Energy Info (EERE)

    REG Bio power UK Ltd Jump to: navigation, search Name: REG Bio-power (UK) Ltd Place: United Kingdom Zip: NG1 2AX Product: Norfolk-based REG Bio-Power operates an electricity...

  14. Credit Leona Securities Asia CLSA UK | Open Energy Information

    Open Energy Info (EERE)

    Leona Securities Asia CLSA UK Jump to: navigation, search Name: Credit Leona Securities Asia - CLSA (UK) Place: London, United Kingdom Zip: EC3V 4QH Sector: Services Product: CLSA...

  15. UK Coal Peel Energy JV | Open Energy Information

    Open Energy Info (EERE)

    Coal Peel Energy JV Jump to: navigation, search Name: UK Coal & Peel Energy JV Place: United Kingdom Sector: Wind energy Product: JV to develop wind projects. References: UK Coal &...

  16. Uk'e koley No Footprint

    Energy Savers [EERE]

    Uk'e koley "No Footprint" Chickaloon Village Traditional Council Nay'dini'aa Na' Chickaloon Tribal Overview * Our Tribe has long been devoted to being a good steward to the environment, understanding that it is our responsibility to take care of the land that has been loaned to us for the short time we are here. * Historically harvested resources include salmon, moose, caribou, beluga whale, grizzly and black bear, dall sheep, beaver and numerous other animals and plants for food,

  17. UK Delegation Focuses on EM's Reactor 'Cocooning' Expertise During

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Hanford Site Tour | Department of Energy UK Delegation Focuses on EM's Reactor 'Cocooning' Expertise During Hanford Site Tour UK Delegation Focuses on EM's Reactor 'Cocooning' Expertise During Hanford Site Tour December 29, 2015 - 12:35pm Addthis The UK delegation gathers at the front of the H Reactor core. Left to right: Amanda Anderson, DOE Office of the Chief of Nuclear Safety; Paul Lonsdale, Magnox Ltd.; Steve Kirchhoff, DOE Office of Environment, Health, Safety and Security; Mina

  18. Statement of Intent Spurs Collaboration for EM, UK Nuclear Organizations |

    Energy Savers [EERE]

    Department of Energy Statement of Intent Spurs Collaboration for EM, UK Nuclear Organizations Statement of Intent Spurs Collaboration for EM, UK Nuclear Organizations March 16, 2016 - 12:25pm Addthis The U.K. NDA delegation visited Savannah River Site’s Defense Waste Processing Facility earlier this year. From left to right: John Owens, Savannah River Remediation (SRR); Benjamin Rivera, EM Headquarters International Programs; George Matis, SRR; John Clarke, NDA; Jack Craig, DOE Savannah

  19. UK Department of Trade and Industry Renewables Group | Open Energy...

    Open Energy Info (EERE)

    Trade and Industry Renewables Group Jump to: navigation, search Name: UK Department of Trade and Industry Renewables Group Place: London, United Kingdom Sector: Renewable Energy...

  20. UK Climate Change Projects Office | Open Energy Information

    Open Energy Info (EERE)

    Climate Change Projects Office Jump to: navigation, search Name: UK Climate Change Projects Office Place: London, United Kingdom Zip: SW1W 9SS Product: Government advisory office...

  1. UK Biotechnology and Biological Sciences Research Council | Open...

    Open Energy Info (EERE)

    Biotechnology and Biological Sciences Research Council Jump to: navigation, search Name: UK Biotechnology and Biological Sciences Research Council Place: London, United Kingdom...

  2. Basis

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    operator bispectral analysis D. A. Baver, 1 P. W. Terry, 1 and C. Holland 2 1 Department of Physics, University of Wisconsin, Madison, Wisconsin 53706, USA 2 Center for Energy Research, University of California, San Diego, California 92093, USA ͑Received 11 September 2008; accepted 12 February 2009; published online 30 March 2009͒ A new procedure for calculating model coefficients from fluctuation data for fully developed turbulence is derived. This procedure differs from previous related

  3. Basis

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    that this equation is a difference- equation representation in the temporal domain of a first- order-in-time nonlinear partial differential equation. The co- efficient L k...

  4. CRAD, NNSA- Safety Basis (SB)

    Broader source: Energy.gov [DOE]

    CRAD for Safety Basis (SB). Criteria Review and Approach Documents (CRADs) that can be used to conduct a well-organized and thorough assessment of elements of safety and health programs.

  5. The carbon component of the UK power price

    SciTech Connect (OSTI)

    Kris Voorspools

    2006-08-01

    CO{sub 2} emissions trading is in full swing in Europe and is already having an impact on the price of power in the UK. If EU allowances (EUAs) trade at euro 20/t-CO{sub 2}, the EUA component in the power price is estimated to be slightly < euro 10/MW.h. In the case of UK power for delivery 1 year ahead, this is {approximately} 10% of the market price of power. The introduction of a carbon components into the UK power prices took place along before the 'official' start of ETS in 2005. Analysis of historical data of the price of power, gas, coal and EUAs shows that the first trace of a CO{sub 2} component in UK power dates back to August 2003, shortly after EUAs first started to trade. In April 2004, CO{sub 2} was fully integrated into the UK power price. 4 refs., 5 figs.

  6. The Basis Code Development System

    Energy Science and Technology Software Center (OSTI)

    1994-03-15

    BASIS9.4 is a system for developing interactive computer programs in Fortran, with some support for C and C++ as well. Using BASIS9.4 you can create a program that has a sophisticated programming language as its user interface so that the user can set, calculate with, and plot, all the major variables in the program. The program author writes only the scientific part of the program; BASIS9.4 supplies an environment in which to exercise that scientificmore » programming which includes an interactive language, an interpreter, graphics, terminal logs, error recovery, macros, saving and retrieving variables, formatted I/O, and online documentation.« less

  7. Coastal Conservation

    SciTech Connect (OSTI)

    Diefenderfer, Heida L.

    2014-12-23

    Book review of Coastal Conservation Edited by Brooke Maslo and Julie L. Lockwood Cambridge University Press, Cambridge, UK, 2014, 382 pages ISBN 978-1-107-60674-6,

  8. Safety Basis Information System | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Basis Information System Safety Basis Information System Safety Basis Report (Public Access) Click on the above link to see the current Safety Basis report. This report provides a list of all DOE nuclear facilities with the safety basis status, hazard categorization, and safety basis type. Safety Basis Login Click on the above link to log in to the Safety Basis web interface. "RESTRICTED; access only to DOE and DOE contractors" Safety Basis Account Request Click on the above link to

  9. Authorization basis requirements comparison report

    SciTech Connect (OSTI)

    Brantley, W.M.

    1997-08-18

    The TWRS Authorization Basis (AB) consists of a set of documents identified by TWRS management with the concurrence of DOE-RL. Upon implementation of the TWRS Basis for Interim Operation (BIO) and Technical Safety Requirements (TSRs), the AB list will be revised to include the BIO and TSRs. Some documents that currently form part of the AB will be removed from the list. This SD identifies each - requirement from those documents, and recommends a disposition for each to ensure that necessary requirements are retained when the AB is revised to incorporate the BIO and TSRs. This SD also identifies documents that will remain part of the AB after the BIO and TSRs are implemented. This document does not change the AB, but provides guidance for the preparation of change documentation.

  10. Hanford Generic Interim Safety Basis

    SciTech Connect (OSTI)

    Lavender, J.C.

    1994-09-09

    The purpose of this document is to identify WHC programs and requirements that are an integral part of the authorization basis for nuclear facilities that are generic to all WHC-managed facilities. The purpose of these programs is to implement the DOE Orders, as WHC becomes contractually obligated to implement them. The Hanford Generic ISB focuses on the institutional controls and safety requirements identified in DOE Order 5480.23, Nuclear Safety Analysis Reports.

  11. 2009 UK/US Nuclear Engineering Workshop Report

    SciTech Connect (OSTI)

    Richard Rankin

    2009-04-01

    This report summarizes the 2009 UK/US Nuclear Engineering Workshop held April 20-21, 2010, in Washington, D.C. to discuss opportunities for nuclear engineering collaboration between researchers in the United States and the United Kingdom.

  12. OSR encapsulation basis -- 100-KW

    SciTech Connect (OSTI)

    Meichle, R.H.

    1995-01-27

    The purpose of this report is to provide the basis for a change in the Operations Safety Requirement (OSR) encapsulated fuel storage requirements in the 105 KW fuel storage basin which will permit the handling and storing of encapsulated fuel in canisters which no longer have a water-free space in the top of the canister. The scope of this report is limited to providing the change from the perspective of the safety envelope (bases) of the Safety Analysis Report (SAR) and Operations Safety Requirements (OSR). It does not change the encapsulation process itself.

  13. Pipeline Decommissioning Trial AWE Berkshire UK - 13619

    SciTech Connect (OSTI)

    Agnew, Kieran

    2013-07-01

    This Paper details the implementation of a 'Decommissioning Trial' to assess the feasibility of decommissioning the redundant pipeline operated by AWE located in Berkshire UK. The paper also presents the tool box of decommissioning techniques that were developed during the decommissioning trial. Constructed in the 1950's and operated until 2005, AWE used a pipeline for the authorised discharge of treated effluent. Now redundant, the pipeline is under a care and surveillance regime awaiting decommissioning. The pipeline is some 18.5 km in length and extends from AWE site to the River Thames. Along its route the pipeline passes along and under several major roads, railway lines and rivers as well as travelling through woodland, agricultural land and residential areas. Currently under care and surveillance AWE is considering a number of options for decommissioning the pipeline. One option is to remove the pipeline. In order to assist option evaluation and assess the feasibility of removing the pipeline a decommissioning trial was undertaken and sections of the pipeline were removed within the AWE site. The objectives of the decommissioning trial were to: - Demonstrate to stakeholders that the pipeline can be removed safely, securely and cleanly - Develop a 'tool box' of methods that could be deployed to remove the pipeline - Replicate the conditions and environments encountered along the route of the pipeline The onsite trial was also designed to replicate the physical prevailing conditions and constraints encountered along the remainder of its route i.e. working along a narrow corridor, working in close proximity to roads, working in proximity to above ground and underground services (e.g. Gas, Water, Electricity). By undertaking the decommissioning trial AWE have successfully demonstrated the pipeline can be decommissioned in a safe, secure and clean manor and have developed a tool box of decommissioning techniques. The tool box of includes; - Hot tapping - a method of breaching the pipe while maintaining containment to remove residual liquids, - Crimp and shear - remote crimping, cutting and handling of pipe using the excavator - Pipe jacking - a way of removing pipes avoiding excavations and causing minimal disturbance and disruption. The details of the decommissioning trial design, the techniques employed, their application and effectiveness are discussed and evaluated here in. (authors)

  14. Beyond Design Basis Events | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Beyond Design Basis Events Beyond Design Basis Events Beyond Design Basis Events Following the March 2011 Fukushima Daiichi nuclear plant accident in Japan, DOE embarked upon several initiatives to investigate the safety posture of its nuclear facilities relative to beyond design basis events (BDBEs). These initiatives included issuing Safety Bulletin 2011-01, Events Beyond Design Safety Basis Analysis, and conducting two DOE nuclear safety workshops. DOE also issued two reports documenting the

  15. Internal dosimetry technical basis manual

    SciTech Connect (OSTI)

    Not Available

    1990-12-20

    The internal dosimetry program at the Savannah River Site (SRS) consists of radiation protection programs and activities used to detect and evaluate intakes of radioactive material by radiation workers. Examples of such programs are: air monitoring; surface contamination monitoring; personal contamination surveys; radiobioassay; and dose assessment. The objectives of the internal dosimetry program are to demonstrate that the workplace is under control and that workers are not being exposed to radioactive material, and to detect and assess inadvertent intakes in the workplace. The Savannah River Site Internal Dosimetry Technical Basis Manual (TBM) is intended to provide a technical and philosophical discussion of the radiobioassay and dose assessment aspects of the internal dosimetry program. Detailed information on air, surface, and personal contamination surveillance programs is not given in this manual except for how these programs interface with routine and special bioassay programs.

  16. BASIS Set Exchange (BSE): Chemistry Basis Sets from the William R. Wiley Environmental Molecular Sciences Laboratory (EMSL) Basis Set Library

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Feller, D; Schuchardt, Karen L.; Didier, Brett T.; Elsethagen, Todd; Sun, Lisong; Gurumoorthi, Vidhya; Chase, Jared; Li, Jun

    The Basis Set Exchange (BSE) provides a web-based user interface for downloading and uploading Gaussian-type (GTO) basis sets, including effective core potentials (ECPs), from the EMSL Basis Set Library. It provides an improved user interface and capabilities over its predecessor, the EMSL Basis Set Order Form, for exploring the contents of the EMSL Basis Set Library. The popular Basis Set Order Form and underlying Basis Set Library were originally developed by Dr. David Feller and have been available from the EMSL webpages since 1994. BSE not only allows downloading of the more than 200 Basis sets in various formats; it allows users to annotate existing sets and to upload new sets. (Specialized Interface)

  17. Tank characterization technical sampling basis

    SciTech Connect (OSTI)

    Brown, T.M.

    1998-04-28

    Tank Characterization Technical Sampling Basis (this document) is the first step of an in place working process to plan characterization activities in an optimal manner. This document will be used to develop the revision of the Waste Information Requirements Document (WIRD) (Winkelman et al. 1997) and ultimately, to create sampling schedules. The revised WIRD will define all Characterization Project activities over the course of subsequent fiscal years 1999 through 2002. This document establishes priorities for sampling and characterization activities conducted under the Tank Waste Remediation System (TWRS) Tank Waste Characterization Project. The Tank Waste Characterization Project is designed to provide all TWRS programs with information describing the physical, chemical, and radiological properties of the contents of waste storage tanks at the Hanford Site. These tanks contain radioactive waste generated from the production of nuclear weapons materials at the Hanford Site. The waste composition varies from tank to tank because of the large number of chemical processes that were used when producing nuclear weapons materials over the years and because the wastes were mixed during efforts to better use tank storage space. The Tank Waste Characterization Project mission is to provide information and waste sample material necessary for TWRS to define and maintain safe interim storage and to process waste fractions into stable forms for ultimate disposal. This document integrates the information needed to address safety issues, regulatory requirements, and retrieval, treatment, and immobilization requirements. Characterization sampling to support tank farm operational needs is also discussed.

  18. Advanced Fuel Cycle Cost Basis

    SciTech Connect (OSTI)

    D. E. Shropshire; K. A. Williams; W. B. Boore; J. D. Smith; B. W. Dixon; M. Dunzik-Gougar; R. D. Adams; D. Gombert; E. Schneider

    2009-12-01

    This report, commissioned by the U.S. Department of Energy (DOE), provides a comprehensive set of cost data supporting a cost analysis for the relative economic comparison of options for use in the Advanced Fuel Cycle Initiative (AFCI) Program. The report describes the AFCI cost basis development process, reference information on AFCI cost modules, a procedure for estimating fuel cycle costs, economic evaluation guidelines, and a discussion on the integration of cost data into economic computer models. This report contains reference cost data for 25 cost modules—23 fuel cycle cost modules and 2 reactor modules. The cost modules were developed in the areas of natural uranium mining and milling, conversion, enrichment, depleted uranium disposition, fuel fabrication, interim spent fuel storage, reprocessing, waste conditioning, spent nuclear fuel (SNF) packaging, long-term monitored retrievable storage, near surface disposal of low-level waste (LLW), geologic repository and other disposal concepts, and transportation processes for nuclear fuel, LLW, SNF, transuranic, and high-level waste.

  19. Advanced Fuel Cycle Cost Basis

    SciTech Connect (OSTI)

    D. E. Shropshire; K. A. Williams; W. B. Boore; J. D. Smith; B. W. Dixon; M. Dunzik-Gougar; R. D. Adams; D. Gombert; E. Schneider

    2008-03-01

    This report, commissioned by the U.S. Department of Energy (DOE), provides a comprehensive set of cost data supporting a cost analysis for the relative economic comparison of options for use in the Advanced Fuel Cycle Initiative (AFCI) Program. The report describes the AFCI cost basis development process, reference information on AFCI cost modules, a procedure for estimating fuel cycle costs, economic evaluation guidelines, and a discussion on the integration of cost data into economic computer models. This report contains reference cost data for 25 cost modules—23 fuel cycle cost modules and 2 reactor modules. The cost modules were developed in the areas of natural uranium mining and milling, conversion, enrichment, depleted uranium disposition, fuel fabrication, interim spent fuel storage, reprocessing, waste conditioning, spent nuclear fuel (SNF) packaging, long-term monitored retrievable storage, near surface disposal of low-level waste (LLW), geologic repository and other disposal concepts, and transportation processes for nuclear fuel, LLW, SNF, transuranic, and high-level waste.

  20. Advanced Fuel Cycle Cost Basis

    SciTech Connect (OSTI)

    D. E. Shropshire; K. A. Williams; W. B. Boore; J. D. Smith; B. W. Dixon; M. Dunzik-Gougar; R. D. Adams; D. Gombert

    2007-04-01

    This report, commissioned by the U.S. Department of Energy (DOE), provides a comprehensive set of cost data supporting a cost analysis for the relative economic comparison of options for use in the Advanced Fuel Cycle Initiative (AFCI) Program. The report describes the AFCI cost basis development process, reference information on AFCI cost modules, a procedure for estimating fuel cycle costs, economic evaluation guidelines, and a discussion on the integration of cost data into economic computer models. This report contains reference cost data for 26 cost modules—24 fuel cycle cost modules and 2 reactor modules. The cost modules were developed in the areas of natural uranium mining and milling, conversion, enrichment, depleted uranium disposition, fuel fabrication, interim spent fuel storage, reprocessing, waste conditioning, spent nuclear fuel (SNF) packaging, long-term monitored retrievable storage, near surface disposal of low-level waste (LLW), geologic repository and other disposal concepts, and transportation processes for nuclear fuel, LLW, SNF, and high-level waste.

  1. US/UK Loan Account Project Status PMOD477

    SciTech Connect (OSTI)

    Stevens, Patrice A.

    2012-07-12

    The viewgraphs describe the status of PMOD477 for LANL. The meeting will occur at DOE-HQ with NA-11 and Military Applications personnel in attendance. Serves to repatriate material with a balance to zero by December 2012. Phase 1 -- Establish formality of operations for War Reserve (WR): Complete surrogate taskings to A90 through a Materials Channel and perform US/UK lessons learned; Complete the US/UK agreed Quality Acceptance Plan, Materials Plan, Shipping procedure, and establish the formal UK/US point of contacts. Phase 2 -- Metal Manufacture (WR): Process material and store material as electrorefined metal (ER) rings, with initial assay and isotopic analysis, prior to manufacturing. Material is cast into accepted configuration and appropriate acceptance document for each aliquot will be generated. Phase 3 -- Intermediate Material Manufacture, Packaging and Shipping (WR): Continue processing of the material in accepted configuration with appropriate acceptance documentation for each aliquot. Provide an initial tasking of the material owed to UK including appropriate quality acceptance documentation. Phase 4 -- Complete Tasking (WR). Phase 5 -- Residue Processing (Non-WR): Complete processing of residue material and waste into accepted configuration with appropriate acceptance document for disposal.

  2. Research To Underpin The UK Plutonium Disposition Strategy

    SciTech Connect (OSTI)

    Hanson, B.C.; Scales, C.R.; Worrall, A.; Thomas, M.; Davies, P.; Gilchrist, P.

    2006-07-01

    In April 2005, the UK Nuclear Decommissioning Authority (NDA) took ownership of most of the civil nuclear liabilities and assets in the UK. These include separated civil plutonium stocks, which are expected to rise to over 100 tonnes. Future UK national policy for disposition remains to be finalised. The feasibility of management options needs to be determined in order to allow the NDA to advise government on the ultimate disposition of this material. Nexia Solutions has a contract with NDA to develop and carry out a research project which will result in a recommendation on the technical feasibility of a number of disposition options, focussing on re-use and immobilisation of plutonium as a waste for disposal. Initial work is already underway evaluating re-use with MOX and IMF fuels and immobilisation using ceramics, glasses and MOX for disposal. The programme is expected to result, circa 2010, in a recommendation of a preferred route for immobilisation and a preferred route for re-use for the UK's civil Pu stocks. (authors)

  3. Beyond Design Basis Event Pilot Evaluations

    Broader source: Energy.gov [DOE]

    This document provides Results and Recommendations for Improvements to Enhance Nuclear Safety at Department of Energy Nuclear Facilities based upon Beyond Design Basis Event Pilot Evaluations

  4. Property:ExplorationBasis | Open Energy Information

    Open Energy Info (EERE)

    Text Description Exploration Basis Why was exploration work conducted in this area (e.g., USGS report of a geothermal resource, hot springs with geothemmetry indicating...

  5. design basis threat | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    design basis threat | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the...

  6. Structural basis for Tetrahymena telomerase processivity factor...

    Office of Scientific and Technical Information (OSTI)

    DNA Citation Details In-Document Search Title: Structural basis for Tetrahymena telomerase processivity factor Teb1 binding to single-stranded telomeric-repeat DNA Authors: ...

  7. Structure, defects and thermal stability of delithiated olivine...

    Office of Scientific and Technical Information (OSTI)

    Brookhaven National University; University of California, San Diego; University of Cambridge, UK; Lawrence Berkeley National Laboratory; Massachusetts Institute of Technology;...

  8. Crystal Structure, Physical Properties, and Electrochemistry...

    Office of Scientific and Technical Information (OSTI)

    Brookhaven National University; University of California, San Diego; University of Cambridge, UK; Lawrence Berkeley National Laboratory; Massachusetts Institute of Technology;...

  9. Electrochemically Induced High Capacity Displacement Reaction...

    Office of Scientific and Technical Information (OSTI)

    National Laboratory; Binghamton University; Brookhaven National University; University of California, San Diego; University of Cambridge, UK; Lawrence Berkeley National Laboratory;...

  10. US, UK, France Discuss Stockpile Stewardship, Arms Control and

    National Nuclear Security Administration (NNSA)

    Nonproliferation and Visit the Nevada National Security Site | National Nuclear Security Administration US, UK, France Discuss Stockpile Stewardship, Arms Control and Nonproliferation and Visit the Nevada National Security Site Friday, December 20, 2013 - 10:19am On Dec. 18-19, 2013, the United States hosted a visit by delegations from France and the United Kingdom to see experimental facilities at the Nevada National Security Site (NNSS) related to stockpile stewardship, arms control and

  11. UK Energy Minister to Address World Renewable Energy Congress - News

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Releases | NREL UK Energy Minister to Address World Renewable Energy Congress Conference, Expo to Bring International 'Clean Energy' experts to Denver April 7, 2004 Golden, Colo. - Stephen Timms, energy minister for the United Kingdom will speak to delegates from as many as 100 nations at the opening ceremony of the eighth World Renewable Energy Congress (WREC VIII) in Denver on Aug. 30. Expected to be the world's largest gathering of renewable energy experts, WREC VIII will provide a forum

  12. Offshore UK; Shell starts Galleon field pre-drilling

    SciTech Connect (OSTI)

    Not Available

    1993-01-01

    Shell U.K. Exploration and Production (Shell), acting as operator for a consortium of companies, has described plans for the two-phase development of Galleon gas field, located 50 miles from the Shell/Esso gas processing plant at Bacton, Norfolk, in 82 ft of water. The field has estimated reserves of 1.4 Tcf. Phase 1 development will cost [Brit pounds]300 million ($500 million); and first production is expected in late 1994. British Gas has agreed to purchase at least Phase 1 gas. Shell will be the operator for the development. A preliminary costsharing arrangement has been agreed to by the co-venturers to bridge the period until equities are determined. The consortium comprises Shell and Esso, with 40% each, and Conoco (U.K.) Ltd. and Oryx U.K. Energy Co., each with 10%. The field is located in Shell/Esso Blocks 48/14, 19a and 20a, and Conoco/Oryx Block 48/15a. Galleon will be the sixth gas field to be developed in the Southern North Sea by Shell, the operator for Shell and Esso. It will be the third field in the Sole Pit area, where total reserves found by Shell/Esso are about 3.0 Tcf.

  13. Safety Basis Information System | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Request Click on the above link to access the form to request access to the Safety Basis web interface. If you need assistance logging in, please AU UserSupport. Contact Nimi Rao...

  14. SRS FTF Section 3116 Basis for Determination

    Broader source: Energy.gov [DOE]

    Basis for Section 3116 Determination for Closure of F-Tank Farm at the Savannah River Site. In accordance with NDAA Section 3116, certain waste from reprocessing of spent nuclear fuel is not high...

  15. Basis for UCNI | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    UCNI Basis for UCNI What documents contain the legal and policy foundations for the UCNI program? Section 148 of the Atomic Energy Act of 1954, as amended (42 U.S.C. 2011 et seq.), is the statutory basis for the UCNI program. 10 CFR Part 1017, Identification and Protection of Unclassified Controlled Nuclear Information specifies many detailed policies and requirements concerning the UCNI program. DOE O 471.1B, Identification and Protection of Unclassified Controlled Nuclear Information,

  16. A comparative assessment of waste incinerators in the UK

    SciTech Connect (OSTI)

    Nixon, J.D.; Wright, D.G.; Dey, P.K.; Ghosh, S.K.; Davies, P.A.

    2013-11-15

    Highlights: We evaluate operational municipal solid waste incinerators in the UK. The supply chain of four case study plants are examined and compared in detail. Technical, financial and operational data has been gathered for the four plants. We suggest the best business practices for waste incinerators. Appropriate strategy choices are the major difficulties for waste to energy plants. - Abstract: The uptake in Europe of Energy from Waste (EfW) incinerator plants has increased rapidly in recent years. In the UK, 25 municipal waste incinerators with energy recovery are now in operation; however, their waste supply chains and business practices vary significantly. With over a hundred more plant developments being considered it is important to establish best business practices for ensuring efficient environmental and operational performance. By reviewing the 25 plants we identify four suitable case study plants to compare technologies (moving grate, fluidised bed and rotary kiln), plant economics and operations. Using data collected from annual reports and through interviews and site visits we provide recommendations for improving the supply chain for waste incinerators and highlight the current issues and challenges faced by the industry. We find that plants using moving grate have a high availability of 8792%. However, compared to the fluidised bed and rotary kiln, quantities of bottom ash and emissions of hydrogen chloride and carbon monoxide are high. The uptake of integrated recycling practices, combined heat and power, and post incineration non-ferrous metal collections needs to be increased among EfW incinerators in the UK. We conclude that one of the major difficulties encountered by waste facilities is the appropriate selection of technology, capacity, site, waste suppliers and heat consumers. This study will be of particular value to EfW plant developers, government authorities and researchers working within the sector of waste management.

  17. Nanoplasmonics simulations at the basis set limit through completeness-optimized, local numerical basis sets

    SciTech Connect (OSTI)

    Rossi, Tuomas P. Sakko, Arto; Puska, Martti J.; Lehtola, Susi; Nieminen, Risto M.

    2015-03-07

    We present an approach for generating local numerical basis sets of improving accuracy for first-principles nanoplasmonics simulations within time-dependent density functional theory. The method is demonstrated for copper, silver, and gold nanoparticles that are of experimental interest but computationally demanding due to the semi-core d-electrons that affect their plasmonic response. The basis sets are constructed by augmenting numerical atomic orbital basis sets by truncated Gaussian-type orbitals generated by the completeness-optimization scheme, which is applied to the photoabsorption spectra of homoatomic metal atom dimers. We obtain basis sets of improving accuracy up to the complete basis set limit and demonstrate that the performance of the basis sets transfers to simulations of larger nanoparticles and nanoalloys as well as to calculations with various exchange-correlation functionals. This work promotes the use of the local basis set approach of controllable accuracy in first-principles nanoplasmonics simulations and beyond.

  18. A Quarterly Update on Joint UK NDA/US DOE Activities and Initiatives

    Energy Savers [EERE]

    Quarterly Update on Joint UK NDA/US DOE Activities and Initiatives Issue 9: Winter 2014 The third Plutonium Management Infor- mation Exchange Workshop was held in Sellafield on October 1 & 2. Attendees included staff from UK NDA, UK Na- tional Nuclear Laboratory, Sellafield Ltd, Los Alamos National Laboratory, Savan- nah River National Laboratory and the University of Manchester although atten- dance from DOE HQ was precluded by the US Government shutdown. The meet- ing covered a wide range

  19. Statement of Intent between the US Department of Energy and UK...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Communication & Engagement International Programs Statement of Intent between the US Department of Energy and UK Nuclear Decommissioning Authority Statement of Intent between ...

  20. MHK Projects/Hammerfest Strom UK Tidal Stream | Open Energy Informatio...

    Open Energy Info (EERE)

    Hammerfest Strom UK Tidal Stream < MHK Projects Jump to: navigation, search << Return to the MHK database homepage Loading map... "minzoom":false,"mappingservice":"googlemaps3","t...

  1. Statement of Intent between the US Department of Energy and UK Nuclear Decommissioning Authority

    Broader source: Energy.gov [DOE]

    Statement of Intent between the US Department of Energy and UK Nuclear Decommissioning Authority for exchange of information concerning management of radioactive waste.

  2. Structural Basis for Activation of Cholera Toxin

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Structural Basis for Activation of Cholera Toxin Structural Basis for Activation of Cholera Toxin Print Wednesday, 30 November 2005 00:00 Cholera is a serious disease that claims thousands of victims each year in third-world, war-torn, and disaster-stricken nations. The culprit is the bacterium Vibrio cholerae, which can be ingested through contaminated food or water and colonizes the mucous membrane of the human small intestine. There, it secretes cholera toxin (CT), a protein whose A1 subunit

  3. TWRS authorization basis configuration control summary

    SciTech Connect (OSTI)

    Mendoza, D.P.

    1997-12-26

    This document was developed to define the Authorization Basis management functional requirements for configuration control, to evaluate the management control systems currently in place, and identify any additional controls that may be required until the TWRS [Tank Waste Remediation System] Configuration Management system is fully in place.

  4. CRAD, Facility Safety- Nuclear Facility Safety Basis

    Office of Energy Efficiency and Renewable Energy (EERE)

    A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) that can be used for assessment of a contractor's Nuclear Facility Safety Basis.

  5. Review and Approval of Nuclear Facility Safety Basis and Safety Design Basis Documents

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2014-12-19

    This Standard describes a framework and the criteria to be used for approval of (1) safety basis documents, as required by 10 Code of Federal Regulation (C.F.R.) 830, Nuclear Safety Management, and (2) safety design basis documents, as required by Department of Energy (DOE) Standard (STD)-1189-2008, Integration of Safety into the Design Process.

  6. Radioactive Waste Management BasisApril 2006

    SciTech Connect (OSTI)

    Perkins, B K

    2011-08-31

    This Radioactive Waste Management Basis (RWMB) documents radioactive waste management practices adopted at Lawrence Livermore National Laboratory (LLNL) pursuant to Department of Energy (DOE) Order 435.1, Radioactive Waste Management. The purpose of this Radioactive Waste Management Basis is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE Manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

  7. TECHNICAL BASIS DOCUMENT FOR NATURAL EVENT HAZARDS

    SciTech Connect (OSTI)

    KRIPPS, L.J.

    2006-07-31

    This technical basis document was developed to support the documented safety analysis (DSA) and describes the risk binning process and the technical basis for assigning risk bins for natural event hazard (NEH)-initiated accidents. The purpose of the risk binning process is to determine the need for safety-significant structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls for a given representative accident or represented hazardous conditions based on an evaluation of the frequency and consequence. Note that the risk binning process is not applied to facility workers, because all facility worker hazardous conditions are considered for safety-significant SSCs and/or TSR-level controls.

  8. Structural Basis for Activation of Cholera Toxin

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Structural Basis for Activation of Cholera Toxin Print Cholera is a serious disease that claims thousands of victims each year in third-world, war-torn, and disaster-stricken nations. The culprit is the bacterium Vibrio cholerae, which can be ingested through contaminated food or water and colonizes the mucous membrane of the human small intestine. There, it secretes cholera toxin (CT), a protein whose A1 subunit (CTA1) triggers a series of events culminating in the massive efflux of

  9. Structural Basis for Activation of Cholera Toxin

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Structural Basis for Activation of Cholera Toxin Print Cholera is a serious disease that claims thousands of victims each year in third-world, war-torn, and disaster-stricken nations. The culprit is the bacterium Vibrio cholerae, which can be ingested through contaminated food or water and colonizes the mucous membrane of the human small intestine. There, it secretes cholera toxin (CT), a protein whose A1 subunit (CTA1) triggers a series of events culminating in the massive efflux of

  10. Structural Basis for Activation of Cholera Toxin

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Structural Basis for Activation of Cholera Toxin Print Cholera is a serious disease that claims thousands of victims each year in third-world, war-torn, and disaster-stricken nations. The culprit is the bacterium Vibrio cholerae, which can be ingested through contaminated food or water and colonizes the mucous membrane of the human small intestine. There, it secretes cholera toxin (CT), a protein whose A1 subunit (CTA1) triggers a series of events culminating in the massive efflux of

  11. Design Basis Threat | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Design Basis Threat NNSA has taken aggressive action to improve the security of its nuclear weapons material (often referred to as special nuclear material, or SNM) and nuclear weapons in its custody. NNSA has taken aggressive action to improve the security of its nuclear weapons material (often referred to as special nuclear material, or SNM) and nuclear weapons in its custody. NNSA has taken aggressive action to improve the security of its nuclear weapons material (often referred to as special

  12. Structural Basis for Activation of Cholera Toxin

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Structural Basis for Activation of Cholera Toxin Print Cholera is a serious disease that claims thousands of victims each year in third-world, war-torn, and disaster-stricken nations. The culprit is the bacterium Vibrio cholerae, which can be ingested through contaminated food or water and colonizes the mucous membrane of the human small intestine. There, it secretes cholera toxin (CT), a protein whose A1 subunit (CTA1) triggers a series of events culminating in the massive efflux of

  13. Review and Approval of Nuclear Facility Safety Basis and Safety...

    Office of Environmental Management (EM)

    DOE STANDARD REVIEW AND APPROVAL OF NUCLEAR FACILITY SAFETY BASIS AND SAFETY DESIGN BASIS ... Neither a reviewer nor the preparer has veto power over ultimate resolution or ...

  14. ORISE: The Medical Basis for Radiation-Accident Preparedness...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    The Medical Basis for Radiation-Accident Preparedness: Medical Management Proceedings of the Fifth International REACTS Symposium on the Medical Basis for Radiation-Accident ...

  15. Structural Basis for the Interaction between Pyk2-FAT Domain...

    Office of Scientific and Technical Information (OSTI)

    Structural Basis for the Interaction between Pyk2-FAT Domain and Leupaxin LD Repeats Citation Details In-Document Search Title: Structural Basis for the Interaction between ...

  16. Nuclear Safety Basis Program Review Overview and Management Oversight...

    Office of Environmental Management (EM)

    Nuclear Safety Basis Program Review Overview and Management Oversight Standard Review Plan Nuclear Safety Basis Program Review Overview and Management Oversight Standard Review ...

  17. Structural basis for substrate specificity in the Escherichia...

    Office of Scientific and Technical Information (OSTI)

    Structural basis for substrate specificity in the Escherichia coli maltose transport system Citation Details In-Document Search Title: Structural basis for substrate specificity in ...

  18. Los Alamos National Laboratory fission basis (Conference) | SciTech...

    Office of Scientific and Technical Information (OSTI)

    Los Alamos National Laboratory fission basis Citation Details In-Document Search Title: Los Alamos National Laboratory fission basis You are accessing a document from the ...

  19. Technical Cost Modeling - Life Cycle Analysis Basis for Program...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    More Documents & Publications Technical Cost Modeling - Life Cycle Analysis Basis for Program Focus Technical Cost Modeling - Life Cycle Analysis Basis for Program Focus Polymer ...

  20. Technical Cost Modeling - Life Cycle Analysis Basis for Program...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    More Documents & Publications Technical Cost Modeling - Life Cycle Analysis Basis for Program Focus Technical Cost Modeling - Life Cycle Analysis Basis for Program Focus Life Cycle ...

  1. Technical Cost Modeling - Life Cycle Analysis Basis for Program...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    More Documents & Publications Technical Cost Modeling - Life Cycle Analysis Basis for Program Focus Technical Cost Modeling - Life Cycle Analysis Basis for Program Focus ...

  2. Heavy quarkonium in a holographic basis (Journal Article) | DOE...

    Office of Scientific and Technical Information (OSTI)

    Heavy quarkonium in a holographic basis Title: Heavy quarkonium in a holographic basis Authors: Li, Yang Search DOE PAGES for author "Li, Yang" Search DOE PAGES for ORCID ...

  3. A molecular basis for advanced materials in water treatment....

    Office of Scientific and Technical Information (OSTI)

    A molecular basis for advanced materials in water treatment. Citation Details In-Document Search Title: A molecular basis for advanced materials in water treatment. Authors: Rempe, ...

  4. Technical Basis for PNNL Beryllium Inventory

    SciTech Connect (OSTI)

    Johnson, Michelle Lynn

    2014-07-09

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

  5. EM Continues Progress in U.S.- U.K. Collaboration

    Broader source: Energy.gov [DOE]

    Officials from EM and the U.K. Nuclear Decommissioning Authority recently held the joint 10th Standing Committee Meeting to discuss progress on the Statement of Intent (SOI) for the information exchange concerning radioactive waste management.

  6. Hammerfest Strom UK co owned by StatoilHydro | Open Energy Information

    Open Energy Info (EERE)

    navigation, search Name: Hammerfest Strom UK co owned by StatoilHydro Address: The Innovation Centre 1 Ainslie Road Hillington Business Park Place: Glasgow Zip: G52 4RU Region:...

  7. US and UK discuss efforts to improve technical verification of nuclear

    National Nuclear Security Administration (NNSA)

    disarmament | National Nuclear Security Administration US and UK discuss efforts to improve technical verification of nuclear disarmament Tuesday, May 6, 2014 - 5:06pm Reaching President Obama's goal of a world without nuclear weapons requires overcoming technical challenges in verifying disarmament. For more than a decade, the U.S. and U.K. have worked together to improve technical verification-an endeavor that balances the need to protect classified and sensitive information with the need

  8. U.S. Department of Energy and UK Department of Trade and Industry Conclude

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Contract Negotiations Associated with BNFL Inc's Work on the Advanced Mixed Waste Treatment Project in Idaho and East Tennessee Technology Park Cleanup Project in Tennessee | Department of Energy UK Department of Trade and Industry Conclude Contract Negotiations Associated with BNFL Inc's Work on the Advanced Mixed Waste Treatment Project in Idaho and East Tennessee Technology Park Cleanup Project in Tennessee U.S. Department of Energy and UK Department of Trade and Industry Conclude

  9. DOE Statement on UK Government's "Road to 2010" Report on Nuclear Security

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    | Department of Energy Statement on UK Government's "Road to 2010" Report on Nuclear Security DOE Statement on UK Government's "Road to 2010" Report on Nuclear Security July 17, 2009 - 12:00am Addthis WASHINGTON, DC - Thomas P. D'Agostino, the Department of Energy's Under Secretary for Nuclear Security and Administrator of the National Nuclear Security Administration, today applauded the British government's new report on advancing the global nuclear security agenda.

  10. NNSA Co-Hosts Nuclear Security Summit Workshop on Maritime Security with UK

    National Nuclear Security Administration (NNSA)

    | National Nuclear Security Administration Co-Hosts Nuclear Security Summit Workshop on Maritime Security with UK November 19, 2015 WASHINGTON - This week, the Department of Energy's National Nuclear Security Administration (DOE/NNSA) and the U.K. Department of Energy and Climate Change concluded a workshop at Wilton Park, United Kingdom, on the growing challenge of securing the global maritime supply chain. In total, 55 participants from 15 countries and 9 international organizations

  11. Review and Approval of Nuclear Facility Safety Basis and Safety Design Basis Documents

    Energy Savers [EERE]

    SENSITIVE DOE-STD-1104-2009 May 2009 Superseding DOE-STD-1104-96 DOE STANDARD REVIEW AND APPROVAL OF NUCLEAR FACILITY SAFETY BASIS AND SAFETY DESIGN BASIS DOCUMENTS U.S. Department of Energy AREA SAFT Washington, DC 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1104-2009 ii Available on the Department of Energy Technical Standards web page at http://www.hss.energy.gov/nuclearsafety/ns/techstds/ DOE-STD-1104-2009 iii CONTENTS FOREWORD

  12. Green Energy Options Ltd | Open Energy Information

    Open Energy Info (EERE)

    Ltd Jump to: navigation, search Name: Green Energy Options Ltd Place: Cambridge, England, United Kingdom Zip: CB23 7QS Product: Cambridge, UK-based developer of in-home displays...

  13. A radial basis function Galerkin method for inhomogeneous nonlocal diffusion

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Lehoucq, Richard B.; Rowe, Stephen T.

    2016-02-01

    We introduce a discretization for a nonlocal diffusion problem using a localized basis of radial basis functions. The stiffness matrix entries are assembled by a special quadrature routine unique to the localized basis. Combining the quadrature method with the localized basis produces a well-conditioned, sparse, symmetric positive definite stiffness matrix. We demonstrate that both the continuum and discrete problems are well-posed and present numerical results for the convergence behavior of the radial basis function method. As a result, we explore approximating the solution to anisotropic differential equations by solving anisotropic nonlocal integral equations using the radial basis function method.

  14. Interim Basis for PCB Sampling and Analyses

    SciTech Connect (OSTI)

    BANNING, D.L.

    2001-03-20

    This document was developed as an interim basis for sampling and analysis of polychlorinated biphenyls (PCBs) and will be used until a formal data quality objective (DQO) document is prepared and approved. On August 31, 2000, the Framework Agreement for Management of Polychlorinated Biphenyls (PCBs) in Hanford Tank Waste was signed by the U.S. Department of Energy (DOE), the Environmental Protection Agency (EPA), and the Washington State Department of Ecology (Ecology) (Ecology et al. 2000). This agreement outlines the management of double shell tank (DST) waste as Toxic Substance Control Act (TSCA) PCB remediation waste based on a risk-based disposal approval option per Title 40 of the Code of Federal Regulations 761.61 (c). The agreement calls for ''Quantification of PCBs in DSTs, single shell tanks (SSTs), and incoming waste to ensure that the vitrification plant and other ancillary facilities PCB waste acceptance limits and the requirements of the anticipated risk-based disposal approval are met.'' Waste samples will be analyzed for PCBs to satisfy this requirement. This document describes the DQO process undertaken to assure appropriate data will be collected to support management of PCBs and is presented in a DQO format. The DQO process was implemented in accordance with the U.S. Environmental Protection Agency EPA QA/G4, Guidance for the Data Quality Objectives Process (EPA 1994) and the Data Quality Objectives for Sampling and Analyses, HNF-IP-0842, Rev. 1A, Vol. IV, Section 4.16 (Banning 1999).

  15. Interim Basis for PCB Sampling and Analyses

    SciTech Connect (OSTI)

    BANNING, D.L.

    2001-01-18

    This document was developed as an interim basis for sampling and analysis of polychlorinated biphenyls (PCBs) and will be used until a formal data quality objective (DQO) document is prepared and approved. On August 31, 2000, the Framework Agreement for Management of Polychlorinated Biphenyls (PCBs) in Hanford Tank Waste was signed by the US. Department of Energy (DOE), the Environmental Protection Agency (EPA), and the Washington State Department of Ecology (Ecology) (Ecology et al. 2000). This agreement outlines the management of double shell tank (DST) waste as Toxic Substance Control Act (TSCA) PCB remediation waste based on a risk-based disposal approval option per Title 40 of the Code of Federal Regulations 761.61 (c). The agreement calls for ''Quantification of PCBs in DSTs, single shell tanks (SSTs), and incoming waste to ensure that the vitrification plant and other ancillary facilities PCB waste acceptance limits and the requirements of the anticipated risk-based disposal approval are met.'' Waste samples will be analyzed for PCBs to satisfy this requirement. This document describes the DQO process undertaken to assure appropriate data will be collected to support management of PCBs and is presented in a DQO format. The DQO process was implemented in accordance with the U.S. Environmental Protection Agency EPA QAlG4, Guidance for the Data Quality Objectives Process (EPA 1994) and the Data Quality Objectives for Sampling and Analyses, HNF-IP-0842, Rev. 1 A, Vol. IV, Section 4.16 (Banning 1999).

  16. Cambridge, Massachusetts: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    Worldwide Greentech Media Harvard - The Clean Energy Project MIT - Center for Advanced Nuclear Energy Systems MIT- Center for 21st Century Energy MIT- Center for Transportation...

  17. Cambridge, Massachusetts: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    Energy Systems MIT- Center for 21st Century Energy MIT- Center for Transportation and Logistics MIT- Deshpande Center for Technological Innovation MIT- Earth Resources Laboratory...

  18. Office of Nuclear Safety Basis and Facility Design

    Broader source: Energy.gov [DOE]

    The Office of Nuclear Safety Basis & Facility Design establishes safety basis and facility design requirements and expectations related to analysis and design of nuclear facilities to ensure protection of workers and the public from the hazards associated with nuclear operations.

  19. Enterprise Assessments Targeted Review of the Safety Basis at...

    Office of Environmental Management (EM)

    Basis at the Savannah River Site F-Area Central Laboratory Facility - January 2016 Enterprise Assessments Targeted Review of the Safety Basis at the Savannah River Site F-Area ...

  20. Authorization basis status report (miscellaneous TWRS facilities, tanks and components)

    SciTech Connect (OSTI)

    Stickney, R.G.

    1998-04-29

    This report presents the results of a systematic evaluation conducted to identify miscellaneous TWRS facilities, tanks and components with potential needed authorization basis upgrades. It provides the Authorization Basis upgrade plan for those miscellaneous TWRS facilities, tanks and components identified.

  1. Review and Approval of Nuclear Facility Safety Basis and Safety...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    104-2014, Review and Approval of Nuclear Facility Safety Basis and Safety Design Basis Documents by Website Administrator This Standard describes a framework and the criteria to be...

  2. CRAD, Integrated Safety Basis and Engineering Design Review ...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Integrated Safety Basis and Engineering Design Review - August 20, 2014 (EA CRAD 31-4, Rev. 0) CRAD, Integrated Safety Basis and Engineering Design Review - August 20, 2014 (EA...

  3. PARFUME Theory and Model basis Report

    SciTech Connect (OSTI)

    Darrell L. Knudson; Gregory K Miller; G.K. Miller; D.A. Petti; J.T. Maki; D.L. Knudson

    2009-09-01

    The success of gas reactors depends upon the safety and quality of the coated particle fuel. The fuel performance modeling code PARFUME simulates the mechanical, thermal and physico-chemical behavior of fuel particles during irradiation. This report documents the theory and material properties behind vari¬ous capabilities of the code, which include: 1) various options for calculating CO production and fission product gas release, 2) an analytical solution for stresses in the coating layers that accounts for irradiation-induced creep and swelling of the pyrocarbon layers, 3) a thermal model that calculates a time-dependent temperature profile through a pebble bed sphere or a prismatic block core, as well as through the layers of each analyzed particle, 4) simulation of multi-dimensional particle behavior associated with cracking in the IPyC layer, partial debonding of the IPyC from the SiC, particle asphericity, and kernel migration (or amoeba effect), 5) two independent methods for determining particle failure probabilities, 6) a model for calculating release-to-birth (R/B) ratios of gaseous fission products that accounts for particle failures and uranium contamination in the fuel matrix, and 7) the evaluation of an accident condition, where a particle experiences a sudden change in temperature following a period of normal irradiation. The accident condi¬tion entails diffusion of fission products through the particle coating layers and through the fuel matrix to the coolant boundary. This document represents the initial version of the PARFUME Theory and Model Basis Report. More detailed descriptions will be provided in future revisions.

  4. CRAD, Engineering Design and Safety Basis- December 22, 2009

    Broader source: Energy.gov [DOE]

    Engineering Design and Safety Basis Inspection Criteria, Inspection Activities, and Lines of Inquiry (HSS CRAD 64-19, Rev. 0)

  5. Early Regulatory Engagement for Successful Site Remediation: the UK Experience - 13173

    SciTech Connect (OSTI)

    Maitland, R.P.; Senior, D.

    2013-07-01

    The Office for Nuclear Regulation (ONR) is an independent safety, security and transport regulator of the UK nuclear industry. ONR regulates all civil nuclear reactor power stations, fuel manufacture, enrichment, spent fuel reprocessing, most defence sites and installations that store and process legacy spent fuel and radioactive waste. The responsibility for funding and strategic direction of decommissioning and radioactive waste management of state owned legacy sites has rested solely with the Nuclear Decommissioning Authority (NDA) since 2005. A key component of NDA's mandate was to encourage new strategic approaches and innovation to dealing with the UK's waste legacy and which deliver value-for-money to the UK taxpayer. ONR, as an agency of the Health and Safety Executive, is entirely independent of NDA and regulates all prescribed activities on NDA's sites. NDA's competition of site management and closure contracts has attracted significant international interest and the formation of consortia comprised of major British, US, French and Swedish organizations bidding for those contracts. The prominence of US organizations in each of those consortia reflects the scale and breadth of existing waste management and D and D projects in the US. This paper will articulate, in broad terms, the challenges faced by international organizations seeking to employ 'off-the-shelf' technology and D and D techniques, successfully employed elsewhere, into the UK regulatory context. The predominantly 'goal-setting' regulatory framework in the UK does not generally prescribe a minimum standard to which a licensee must adhere. The legal onus on licensees in the UK is to demonstrate, whatever technology is selected, that in its applications, risks are reduced 'So Far As Is Reasonably Practicable' or 'SFAIRP'. By the nature of its role, ONR adopts a conservative approach to regulation; however ONR also recognises that in the decommissioning (and ultimately the site closure) domain, it is often necessary to consider and support novel approaches to achieve the nationally desired end-state. Crucial to successful and compliant operation in this regulatory environment is early and sustained engagement of the contractor with the regulator. There must be a 'no-surprises' culture to engender regulatory confidence early in a project. The paper considers some of the challenges facing international prime and lower tier contractors when undertaking D and D contracts in the UK, and emphasizes the importance of constructive and transparent dialogue with all regulators to sustain confidence at all stages of a major decommissioning project. The paper will also articulate ONR's strategy to increase collaboration with the US Department of Energy in light of increasing UK-US synergy in the area of waste management and to benchmark respective regulatory approaches. (authors)

  6. Simulation of the Winfrith SGHWR X-trip blowdown experiment using RELAP-UK Mk IV and RETRAN-UK. Final report

    SciTech Connect (OSTI)

    Richards, C.G.

    1981-11-01

    The paper describes calculations with the thermal hydraulics codes RELAP-UK Mk IV and RETRAN to model the behavior of the Winfrith Steam Generating Heavy Water Reactor (WSGHWR) during a controlled depressurization experiment. The results of the simulations are compared with each other and with the experimental data. In the X-trip experiment a reactor trip was initiated from a steady operating condition of 90% of full power and the reactor allowed to depressurize via steam dump lines from the steam drums. During the transient data from a variety of instruments measuring coolant parameters, such as pressures, flows and temperatures, and plant state such as valve positions, were recorded. The version of RETRAN employed in the calculations was a development version of RETRAN-UK with the addition of a number of features from RELAP-UK, including Bryce slip and the Holmes drift flux model. The first 100 seconds of the X-trip transient in one of the two reactor loops has been simulated, during which time the system pressure falls from 940 to 170 psia.

  7. Enterprise Assessments Review of the Delegation of Safety Basis Approval

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Authority for Hazard Category 1, 2, and 3 Nuclear Facilities - April 2016 | Department of Energy Delegation of Safety Basis Approval Authority for Hazard Category 1, 2, and 3 Nuclear Facilities - April 2016 Enterprise Assessments Review of the Delegation of Safety Basis Approval Authority for Hazard Category 1, 2, and 3 Nuclear Facilities - April 2016 April 2016 Enterprise Assessments Review of the Delegation of Safety Basis Approval Authority for Hazard Category 1, 2, and 3 Nuclear

  8. Protocol for Enhanced Evaluations of Beyond Design Basis Events Supporting

    Energy Savers [EERE]

    Implementation of Operating Experience Report 2013-01 | Department of Energy Protocol for Enhanced Evaluations of Beyond Design Basis Events Supporting Implementation of Operating Experience Report 2013-01 Protocol for Enhanced Evaluations of Beyond Design Basis Events Supporting Implementation of Operating Experience Report 2013-01 April, 2013 Protocol for Enhanced Evaluations of Beyond Design Basis Events Supporting Implementation of Operating Experience Report 2013-01 To support the

  9. ORISE: The Medical Basis for Radiation-Accident Preparedness: Medical

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Management (Published by REAC/TS) The Medical Basis for Radiation-Accident Preparedness: Medical Management Proceedings of the Fifth International REAC/TS Symposium on the Medical Basis for Radiation-Accident Preparedness and the Biodosimetry Workshop As part of its mission to provide continuing education for personnel responsible for treating radiation injuries, REAC/TS hosted the Fifth International REAC/TS Symposium on the Medical Basis for Radiation-Accident Preparedness symposium and

  10. Technical Planning Basis - DOE Directives, Delegations, and Requiremen...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    2, Technical Planning Basis by David Freshwater Functional areas: Defense Nuclear Facility Safety and Health Requirement, Safety and Security, The Guide assists DOENNSA field...

  11. Protocol for Enhanced Evaluations of Beyond Design Basis Events...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Protocol for Enhanced Evaluations of Beyond Design Basis Events Supporting Implementation of Operating Experience Report 2013-01 Protocol for Enhanced Evaluations of Beyond Design...

  12. CRAD, Review of Safety Basis Development- January 31, 2013

    Broader source: Energy.gov [DOE]

    Review of Safety Basis Development for the Savannah River Site Salt Waste Processing Facility - Inspection Criteria, Approach, and Lines of Inquiry (HSS CRAD 45-57, Rev. 0)

  13. Assessing Beyond Design Basis Seismic Events and Implications...

    Office of Environmental Management (EM)

    Defense Nuclear Facilities Safety Board Topics Covered: Department of Energy Approach to Natural Phenomena Hazards Analysis and Design (Seismic) Design Basis and Beyond Design...

  14. Structural and Functional Basis for Broad-spectrum Neutralization...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Structural and Functional Basis for Broad-spectrum Neutralization of Avian and Human ... unsuccessful. figure 2 Fig 2A. Broad spectrum neutralizing antibody F10 in complex ...

  15. U.K. Officials Visit DOE Headquarters to Collaborate on Nuclear Cleanup Issues

    Broader source: Energy.gov [DOE]

    WASHINGTON, D.C. – A U.K. senior-level delegation recently met with headquarters officials from DOE’s offices of EM and Nuclear Energy to expand collaboration under the government-to-government Statement of Intent signed by the Department and U.K.’s Nuclear Decommissioning Authority (NDA) and National Nuclear Laboratory (NNL).

  16. Fuel price changes and the adoption of cogeneration in the U.K. and Netherlands

    SciTech Connect (OSTI)

    Bonilla, David

    2007-08-15

    Whenever industrial plants consume power and heat, there is a need to consider energy efficiency investment in a cogeneration plant. The author tests an empirical model employing application of cross-sectional time series to analyze the economic incentives influencing the adoption of energy-saving technology in the U.K. and Dutch manufacturing sectors. (author)

  17. Leadership | Center for Gas SeparationsRelevant to Clean Energy...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Council (TAC) Dr. Abhoyjit Bhown (EPRI) Prof. Anthony Cheetham (University of Cambridge, UK) Dr. Edward W. Corcoran (ExxonMobil Corporation) Prof. Susumu Kitagawa (Kyoto...

  18. Polysolar Ltd | Open Energy Information

    Open Energy Info (EERE)

    navigation, search Name: Polysolar Ltd. Place: United Kingdom Sector: Solar Product: Cambridge, UK-based start up developing new solar cell architectures with industrial partners...

  19. Dr.James J.Spivey

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Books: cat Catalysis , volumes 12-21, published by the Royal Society of Chemistry (Cambridge, UK). nat Natural Gas Conversion VI, Studies in Surface Science and Catalysis , vol....

  20. Users' Executive Committee

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    of Cambridge, UK David Shuh (2013-2015) Chemical Sciences Division, Berkeley Lab Tyler Troy (2014-2016) Chemical Sciences Division, Berkeley Lab 2015 ALS UEC members (from...

  1. Structural basis for the antibody neutralization of Herpes simplex virus

    Office of Scientific and Technical Information (OSTI)

    (Journal Article) | SciTech Connect Structural basis for the antibody neutralization of Herpes simplex virus Citation Details In-Document Search Title: Structural basis for the antibody neutralization of Herpes simplex virus The gD-E317-Fab complex crystal revealed the conformational epitope of human mAb E317 on HSV gD, providing a molecular basis for understanding the viral neutralization mechanism. Glycoprotein D (gD) of Herpes simplex virus (HSV) binds to a host cell surface receptor,

  2. Structural basis for ubiquitin-mediated antiviral signal activation...

    Office of Scientific and Technical Information (OSTI)

    Title: Structural basis for ubiquitin-mediated antiviral signal activation by RIG-I Authors: Peisley, Alys ; Wu, Bin ; Xu, Hui ; Chen, Zhijian J. ; Hur , Sun 1 ; HHMI) 2 ; ...

  3. The Three-Dimensional Structural Basis of Type II Hyperprolinemia...

    Office of Scientific and Technical Information (OSTI)

    Journal Article: The Three-Dimensional Structural Basis of Type II Hyperprolinemia Citation Details In-Document Search ... Here, we report the first structure of human P5CDH (HsP5CDH) ...

  4. CRAD, Review of Safety Basis Development- October 11, 2012

    Broader source: Energy.gov [DOE]

    Review of Safety Basis Development for the Y-12 National Security Complex Uranium Processing Facility Inspection Criteria, Approach, and Lines of Inquiry (HSS CRAD 45-55, Rev. 0)

  5. Enterprise Assessments Targeted Review of the Safety Basis at...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    ... in SAR 3.3.2.3.1 does not address the effect of an earthquake followed by a fire. ... Although the accident analysis is generally sound, the analysis of the design basis ...

  6. Structural basis for the antibody neutralization of Herpes simplex...

    Office of Scientific and Technical Information (OSTI)

    of Herpes simplex virus Citation Details In-Document Search Title: Structural basis for the antibody neutralization of Herpes simplex virus The gD-E317-Fab complex ...

  7. General Engineer/Physical Scientist (Safety Basis Engineer/Scientist)

    Broader source: Energy.gov [DOE]

    A successful candidate in this position will serve as an authority in the safety basis functional area. The incumbent is responsible for managing, coordinating, and authorizing work in the context...

  8. Advanced Test Reactor Design Basis Reconstitution Project Issue Resolution Process

    SciTech Connect (OSTI)

    Steven D. Winter; Gregg L. Sharp; William E. Kohn; Richard T. McCracken

    2007-05-01

    The Advanced Test Reactor (ATR) Design Basis Reconstitution Program (DBRP) is a structured assessment and reconstitution of the design basis for the ATR. The DBRP is designed to establish and document the ties between the Document Safety Analysis (DSA), design basis, and actual system configurations. Where the DBRP assessment team cannot establish a link between these three major elements, a gap is identified. Resolutions to identified gaps represent configuration management and design basis recovery actions. The proposed paper discusses the process being applied to define, evaluate, report, and address gaps that are identified through the ATR DBRP. Design basis verification may be performed or required for a nuclear facility safety basis on various levels. The process is applicable to large-scale design basis reconstitution efforts, such as the ATR DBRP, or may be scaled for application on smaller projects. The concepts are applicable to long-term maintenance of a nuclear facility safety basis and recovery of degraded safety basis components. The ATR DBRP assessment team has observed numerous examples where a clear and accurate link between the DSA, design basis, and actual system configuration was not immediately identifiable in supporting documentation. As a result, a systematic approach to effectively document, prioritize, and evaluate each observation is required. The DBRP issue resolution process provides direction for consistent identification, documentation, categorization, and evaluation, and where applicable, entry into the determination process for a potential inadequacy in the safety analysis (PISA). The issue resolution process is a key element for execution of the DBRP. Application of the process facilitates collection, assessment, and reporting of issues identified by the DBRP team. Application of the process results in an organized database of safety basis gaps and prioritized corrective action planning and resolution. The DBRP team follows the ATR DBRP issue resolution process which provides a method for the team to promptly sort and prioritize questions and issues between those that can be addressed as a normal part of the reconstitution project and those that are to be handle as PISAs. Presentation of the DBRP issue resolution process provides an example for similar activities that may be required at other facilities within the Department of Energy complex.

  9. Structural and Functional Basis for Inhibition of Erythrocyte Invasion by

    Office of Scientific and Technical Information (OSTI)

    Antibodies that Target Plasmodium falciparum EBA-175 (Journal Article) | SciTech Connect Journal Article: Structural and Functional Basis for Inhibition of Erythrocyte Invasion by Antibodies that Target Plasmodium falciparum EBA-175 Citation Details In-Document Search Title: Structural and Functional Basis for Inhibition of Erythrocyte Invasion by Antibodies that Target Plasmodium falciparum EBA-175 Authors: Chen, Edwin ; Paing, May M. ; Salinas, Nichole ; Sim, B. Kim Lee ; Tolia, Niraj H.

  10. Structural basis for biomolecular recognition in overlapping binding sites

    Office of Scientific and Technical Information (OSTI)

    in a diiron enzyme system (Journal Article) | SciTech Connect Structural basis for biomolecular recognition in overlapping binding sites in a diiron enzyme system Citation Details In-Document Search Title: Structural basis for biomolecular recognition in overlapping binding sites in a diiron enzyme system Authors: Acheson, Justin F. ; Bailey, Lucas J. ; Elsen, Nathaniel L. ; Fox, Brian G. [1] + Show Author Affiliations UW Publication Date: 2016-01-22 OSTI Identifier: 1229904 Resource Type:

  11. Structural basis of JAZ repression of MYC transcription factors in

    Office of Scientific and Technical Information (OSTI)

    jasmonate signalling (Journal Article) | SciTech Connect Journal Article: Structural basis of JAZ repression of MYC transcription factors in jasmonate signalling Citation Details In-Document Search Title: Structural basis of JAZ repression of MYC transcription factors in jasmonate signalling Authors: Zhang, Feng ; Yao, Jian ; Ke, Jiyuan ; Zhang, Li ; Lam, Vinh Q. ; Xin, Xiu-Fang ; Zhou, X. Edward ; Chen, Jian ; Brunzelle, Joseph ; Griffin, Patrick R. ; Zhou, Mingguo ; Xu, H. Eric ; Melcher,

  12. Structural basis for Tetrahymena telomerase processivity factor Teb1

    Office of Scientific and Technical Information (OSTI)

    binding to single-stranded telomeric-repeat DNA (Journal Article) | SciTech Connect Journal Article: Structural basis for Tetrahymena telomerase processivity factor Teb1 binding to single-stranded telomeric-repeat DNA Citation Details In-Document Search Title: Structural basis for Tetrahymena telomerase processivity factor Teb1 binding to single-stranded telomeric-repeat DNA Authors: Zeng, Zhixiong ; Min, Bosun ; Huang, Jing ; Hong, Kyungah ; Yang, Yuting ; Collins, Kathleen ; Lei, Ming [1]

  13. Structural basis for substrate specificity in the Escherichia coli maltose

    Office of Scientific and Technical Information (OSTI)

    transport system (Journal Article) | SciTech Connect Structural basis for substrate specificity in the Escherichia coli maltose transport system Citation Details In-Document Search Title: Structural basis for substrate specificity in the Escherichia coli maltose transport system Authors: Oldham, Michael L. ; Chen, Shanshuang ; Chen, Jue [1] ; HHMI) [2] + Show Author Affiliations (Purdue) [Purdue ( Publication Date: 2013-11-11 OSTI Identifier: 1105053 Resource Type: Journal Article Resource

  14. Atomic substitution reveals the structural basis for substrate adenine

    Office of Scientific and Technical Information (OSTI)

    recognition and removal by adenine DNA glycosylase (Journal Article) | SciTech Connect Atomic substitution reveals the structural basis for substrate adenine recognition and removal by adenine DNA glycosylase Citation Details In-Document Search Title: Atomic substitution reveals the structural basis for substrate adenine recognition and removal by adenine DNA glycosylase Adenine DNA glycosylase catalyzes the glycolytic removal of adenine from the promutagenic A {center_dot} oxoG base pair in

  15. Optimisation of the Management of Higher Activity Waste in the UK - 13537

    SciTech Connect (OSTI)

    Walsh, Ciara; Buckley, Matthew

    2013-07-01

    The Upstream Optioneering project was created in the Nuclear Decommissioning Authority (UK) to support the development and implementation of significant opportunities to optimise activities across all the phases of the Higher Activity Waste management life cycle (i.e. retrieval, characterisation, conditioning, packaging, storage, transport and disposal). The objective of the Upstream Optioneering project is to work in conjunction with other functions within NDA and the waste producers to identify and deliver solutions to optimise the management of higher activity waste. Historically, optimisation may have occurred on aspects of the waste life cycle (considered here to include retrieval, conditioning, treatment, packaging, interim storage, transport to final end state, which may be geological disposal). By considering the waste life cycle as a whole, critical analysis of assumed constraints may lead to cost savings for the UK Tax Payer. For example, it may be possible to challenge the requirements for packaging wastes for disposal to deliver an optimised waste life cycle. It is likely that the challenges faced in the UK are shared in other countries. It is therefore likely that the opportunities identified may also apply elsewhere, with the potential for sharing information to enable value to be shared. (authors)

  16. The adoption of a decentralized energy technology: The case of UK engine cogeneration

    SciTech Connect (OSTI)

    Strachan, N.D.; Dowlatabadi, H.

    1999-07-01

    Adoption of decentralized energy technologies will be crucial in the evolving structure of energy markets and the magnitude of future greenhouse gas emissions. This detailed analysis of the adoption of engine cogeneration gives insights into organizational decision making regarding the diffusion of a cost effective decentralized energy technology. Detailed site information on over 600 UK cogeneration installations was collected and analyzed for the six year period during which UK energy markets were in the process of deregulation. A detailed examination using standard investment criteria of the cogeneration schemes indicated that over 70% of investments were of questionable economic value to adopters. This was because these installations were below the calculated minimum economic size threshold. A key determinant of this size threshold was found to be the fixed costs of maintenance. Analysis of the financing of installations revealed that the largest fraction of poor investments occurred in energy services agreements between suppliers and adopters. The policy implications for decentralized energy technologies of a minimum size threshold and poor investment decisions by early adopters are discussed. Further research aims to explore postulated explanations for the observed decline in early adoption of UK engine cogeneration.

  17. CRAD, Safety Basis- Idaho MF-628 Drum Treatment Facility

    Broader source: Energy.gov [DOE]

    A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a May 2007 readiness assessment of the Safety Basis at the Advanced Mixed Waste Treatment Project.

  18. CRAD, Safety Basis- Idaho Accelerated Retrieval Project Phase II

    Broader source: Energy.gov [DOE]

    A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2006 Commencement of Operations assessment of the Safety Basis at the Idaho Accelerated Retrieval Project Phase II.

  19. Cold Vacuum Drying (CVD) Facility Design Basis Accident Analysis Documentation

    SciTech Connect (OSTI)

    PIEPHO, M.G.

    1999-10-20

    This document provides the detailed accident analysis to support HNF-3553, Annex B, Spent Nuclear Fuel Project Final Safety Analysis Report, ''Cold Vacuum Drying Facility Final Safety Analysis Report (FSAR).'' All assumptions, parameters and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the FSAR.

  20. Canister Storage Building (CSB) Design Basis Accident Analysis Documentation

    SciTech Connect (OSTI)

    CROWE, R.D.; PIEPHO, M.G.

    2000-03-23

    This document provided the detailed accident analysis to support HNF-3553, Spent Nuclear Fuel Project Final Safety Analysis Report, Annex A, ''Canister Storage Building Final Safety Analysis Report''. All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the Canister Storage Building Final Safety Analysis Report.

  1. Canister storage building design basis accident analysis documentation

    SciTech Connect (OSTI)

    KOPELIC, S.D.

    1999-02-25

    This document provides the detailed accident analysis to support HNF-3553, Spent Nuclear Fuel Project Final Safety Analysis Report, Annex A, ''Canister Storage Building Final Safety Analysis Report.'' All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the Canister Storage Building Final Safety Analysis Report.

  2. Solar Power Tower Design Basis Document, Revision 0

    SciTech Connect (OSTI)

    ZAVOICO,ALEXIS B.

    2001-07-01

    This report contains the design basis for a generic molten-salt solar power tower. A solar power tower uses a field of tracking mirrors (heliostats) that redirect sunlight on to a centrally located receiver mounted on top a tower, which absorbs the concentrated sunlight. Molten nitrate salt, pumped from a tank at ground level, absorbs the sunlight, heating it up to 565 C. The heated salt flows back to ground level into another tank where it is stored, then pumped through a steam generator to produce steam and make electricity. This report establishes a set of criteria upon which the next generation of solar power towers will be designed. The report contains detailed criteria for each of the major systems: Collector System, Receiver System, Thermal Storage System, Steam Generator System, Master Control System, and Electric Heat Tracing System. The Electric Power Generation System and Balance of Plant discussions are limited to interface requirements. This design basis builds on the extensive experience gained from the Solar Two project and includes potential design innovations that will improve reliability and lower technical risk. This design basis document is a living document and contains several areas that require trade-studies and design analysis to fully complete the design basis. Project- and site-specific conditions and requirements will also resolve open To Be Determined issues.

  3. Canister Storage Building (CSB) Design Basis Accident Analysis Documentation

    SciTech Connect (OSTI)

    CROWE, R.D.

    1999-09-09

    This document provides the detailed accident analysis to support ''HNF-3553, Spent Nuclear Fuel Project Final Safety, Analysis Report, Annex A,'' ''Canister Storage Building Final Safety Analysis Report.'' All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the Canister Storage Building Final Safety Analysis Report.

  4. Basis for NGNP Reactor Design Down-Selection

    SciTech Connect (OSTI)

    L.E. Demick

    2011-11-01

    The purpose of this paper is to identify the extent of technology development, design and licensing maturity anticipated to be required to credibly identify differences that could make a technical choice practical between the prismatic and pebble bed reactor designs. This paper does not address a business decision based on the economics, business model and resulting business case since these will vary based on the reactor application. The selection of the type of reactor, the module ratings, the number of modules, the configuration of the balance of plant and other design selections will be made on the basis of optimizing the Business Case for the application. These are not decisions that can be made on a generic basis.

  5. Resilient Control Systems Practical Metrics Basis for Defining Mission Impact

    SciTech Connect (OSTI)

    Craig G. Rieger

    2014-08-01

    "Resilience” describes how systems operate at an acceptable level of normalcy despite disturbances or threats. In this paper we first consider the cognitive, cyber-physical interdependencies inherent in critical infrastructure systems and how resilience differs from reliability to mitigate these risks. Terminology and metrics basis are provided to integrate the cognitive, cyber-physical aspects that should be considered when defining solutions for resilience. A practical approach is taken to roll this metrics basis up to system integrity and business case metrics that establish “proper operation” and “impact.” A notional chemical processing plant is the use case for demonstrating how the system integrity metrics can be applied to establish performance, and

  6. Design-Load Basis for LANL Structures, Systems, and Components

    SciTech Connect (OSTI)

    I. Cuesta

    2004-09-01

    This document supports the recommendations in the Los Alamos National Laboratory (LANL) Engineering Standard Manual (ESM), Chapter 5--Structural providing the basis for the loads, analysis procedures, and codes to be used in the ESM. It also provides the justification for eliminating the loads to be considered in design, and evidence that the design basis loads are appropriate and consistent with the graded approach required by the Department of Energy (DOE) Code of Federal Regulation Nuclear Safety Management, 10, Part 830. This document focuses on (1) the primary and secondary natural phenomena hazards listed in DOE-G-420.1-2, Appendix C, (2) additional loads not related to natural phenomena hazards, and (3) the design loads on structures during construction.

  7. Basis functions for electronic structure calculations on spheres

    SciTech Connect (OSTI)

    Gill, Peter M. W. Loos, Pierre-François Agboola, Davids

    2014-12-28

    We introduce a new basis function (the spherical Gaussian) for electronic structure calculations on spheres of any dimension D. We find general expressions for the one- and two-electron integrals and propose an efficient computational algorithm incorporating the Cauchy-Schwarz bound. Using numerical calculations for the D = 2 case, we show that spherical Gaussians are more efficient than spherical harmonics when the electrons are strongly localized.

  8. Online Monitoring Technical Basis and Analysis Framework for Emergency

    Energy Savers [EERE]

    Diesel Generators-Interim Report for FY 2013 | Department of Energy for Emergency Diesel Generators-Interim Report for FY 2013 Online Monitoring Technical Basis and Analysis Framework for Emergency Diesel Generators-Interim Report for FY 2013 The Light Water Reactor Sustainability Program is a research, development, and deployment program sponsored by the U.S. Department of Energy Office of Nuclear Energy. The program is operated in collaboration with the Electric Power Research Institute's

  9. Online Monitoring Technical Basis and Analysis Framework for Large Power

    Energy Savers [EERE]

    Transformers; Interim Report for FY 2012 | Department of Energy for Large Power Transformers; Interim Report for FY 2012 Online Monitoring Technical Basis and Analysis Framework for Large Power Transformers; Interim Report for FY 2012 The Light Water Reactor Sustainability Program is a research, development, and deployment program sponsored by the U.S. Department of Energy Office of Nuclear Energy. The program is operated in collaboration with the Electric Power Research Institute's (EPRI's)

  10. Interim Safety Basis for Fuel Supply Shutdown Facility

    SciTech Connect (OSTI)

    BENECKE, M.W.

    2000-09-07

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

  11. 5th International REAC/TS Symposium: The Medical Basis for Radiation...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    The Medical Basis for Radiation Accident Preparedness Skip site navigation and ... The Medical Basis for Radiation Accident Preparedness Sept. 27-29, 2011 | Miami, ...

  12. CRAD, Safety Basis Upgrade Review (DOE-STD-3009-2014) - May 15...

    Office of Environmental Management (EM)

    1) provides objectives, criteria, and approaches for establishing and maintaining the safety basis at nuclear facilities. CRAD, Safety Basis Upgrade Review (DOE-STD-3009-2014)...

  13. The use of commercial and industrial waste in energy recovery systems - A UK preliminary study

    SciTech Connect (OSTI)

    Lupa, Christopher J.; Ricketts, Lois J.; Sweetman, Andy; Herbert, Ben M.J.

    2011-08-15

    Highlights: > Commercial and industrial waste samples collected. > Samples analysed for calorific value, moisture, ash and elemental composition. > Values similar to those of municipal solid waste and refuse derived fuel. > Sampled waste could be used in current energy recovery systems with minimal retrofitting. > Sampled waste could account 6.5% towards the UK's 2020 renewable electricity target if all qualifying waste is used. - Abstract: With 2020 energy targets set out by the EU fast approaching, the UK is trying to source a higher proportion of its energy from renewable resources. Coupled with this, a growing population and increasing trends in consumer demand have resulted in national waste loads increasing. A possible solution to both issues is energy-from-waste (EfW) technologies. Many studies have focused on municipal solid waste (MSW) as a potential feedstock, but appear to overlook the potential benefits of commercial and industrial waste (C and IW). In this study, samples of C and IW were collected from three North West waste management companies and Lancaster University campus. The samples were tested for their gross and net calorific value, moisture content, ash content, volatile matter, and also elemental composition to determine their suitability in EfW systems. Intra-sample analysis showed there to be little variation between samples with the exception two samples, from waste management site 3, which showed extensive variation with regards to net calorific value, ash content, and elemental analysis. Comparisons with known fuel types revealed similarities between the sampled C and IW, MSW, and refuse derived fuel (RDF) thereby justifying its potential for use in EfW systems. Mean net calorific value (NCV) was calculated as 9.47 MJ/kg and concentrations of sulphur, nitrogen, and chlorine were found to be below 2%. Potential electrical output was calculated using the NCV of the sampled C and IW coupled with four differing energy generation technologies. Using a conventional incinerator with steam cycle, total electrical output was calculated as 24.9 GWh, based on a plant operating at 100,000 tpa. This value rose to 27.0 GWh when using an integrated gasification combined cycle. A final aspect of this study was to deduce the potential total national electrical output if all suitable C and IW were to be used in EfW systems. Using incineration coupled with a steam turbine, this was determined to be 6 TWh, 1.9% of the national demand thereby contributing 6.5% towards the UK's 2020 renewable electricity target.

  14. The benefits of a fast reactor closed fuel cycle in the UK

    SciTech Connect (OSTI)

    Gregg, R.; Hesketh, K.

    2013-07-01

    The work has shown that starting a fast reactor closed fuel cycle in the UK, requires virtually all of Britain's existing and future PWR spent fuel to be reprocessed, in order to obtain the plutonium needed. The existing UK Pu stockpile is sufficient to initially support only a modest SFR 'closed' fleet assuming spent fuel can be reprocessed shortly after discharge (i.e. after two years cooling). For a substantial fast reactor fleet, most Pu will have to originate from reprocessing future spent PWR fuel. Therefore, the maximum fast reactor fleet size will be limited by the preceding PWR fleet size, so scenarios involving fast reactors still require significant quantities of uranium ore indirectly. However, once a fast reactor fuel cycle has been established, the very substantial quantities of uranium tails in the UK would ensure there is sufficient material for several centuries. Both the short and long term impacts on a repository have been considered in this work. Over the short term, the decay heat emanating from the HLW and spent fuel will limit the density of waste within a repository. For scenarios involving fast reactors, the only significant heat bearing actinide content will be present in the final cores, resulting in a 50% overall reduction in decay energy deposited within the repository when compared with an equivalent open fuel cycle. Over the longer term, radiological dose becomes more important. Total radiotoxicity (normalised by electricity generated) is lower for scenarios with Pu recycle after 2000 years. Scenarios involving fast reactors have the lowest radiotoxicity since the quantities of certain actinides (Np, Pu and Am) eventually stabilise. However, total radiotoxicity as a measure of radiological risk does not account for differences in radionuclide mobility once in repository. Radiological dose is dominated by a small number of fission products so is therefore not affected significantly by reactor type or recycling strategy (since the fission product will primarily be a function of nuclear energy generated). However, by reprocessing spent fuel, it is possible to immobilise the fission product in a more suitable waste form that has far more superior in-repository performance. (authors)

  15. RELEASE OF DRIED RADIOACTIVE WASTE MATERIALS TECHNICAL BASIS DOCUMENT

    SciTech Connect (OSTI)

    KOZLOWSKI, S.D.

    2007-05-30

    This technical basis document was developed to support RPP-23429, Preliminary Documented Safety Analysis for the Demonstration Bulk Vitrification System (PDSA) and RPP-23479, Preliminary Documented Safety Analysis for the Contact-Handled Transuranic Mixed (CH-TRUM) Waste Facility. The main document describes the risk binning process and the technical basis for assigning risk bins to the representative accidents involving the release of dried radioactive waste materials from the Demonstration Bulk Vitrification System (DBVS) and to the associated represented hazardous conditions. Appendices D through F provide the technical basis for assigning risk bins to the representative dried waste release accident and associated represented hazardous conditions for the Contact-Handled Transuranic Mixed (CH-TRUM) Waste Packaging Unit (WPU). The risk binning process uses an evaluation of the frequency and consequence of a given representative accident or represented hazardous condition to determine the need for safety structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls. A representative accident or a represented hazardous condition is assigned to a risk bin based on the potential radiological and toxicological consequences to the public and the collocated worker. Note that the risk binning process is not applied to facility workers because credible hazardous conditions with the potential for significant facility worker consequences are considered for safety-significant SSCs and/or TSR-level controls regardless of their estimated frequency. The controls for protection of the facility workers are described in RPP-23429 and RPP-23479. Determination of the need for safety-class SSCs was performed in accordance with DOE-STD-3009-94, Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses, as described below.

  16. Guidance For Preparatioon of Basis For Interim Operation (BIO) Documents

    Energy Savers [EERE]

    3011-2002 December 2002 Superceding DOE-STD-3011-94 November 1994 DOE STANDARD GUIDANCE FOR PREPARATION OF BASIS FOR INTERIM OPERATION (BIO) DOCUMENTS U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE DOE-STD-3011-2002 ii This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S.

  17. The Bender-Dunne basis operators as Hilbert space operators

    SciTech Connect (OSTI)

    Bunao, Joseph; Galapon, Eric A. E-mail: eric.galapon@upd.edu.ph

    2014-02-15

    The Bender-Dunne basis operators, T{sub ?m,n}=2{sup ?n}?{sub k=0}{sup n}(n/k )q{sup k}p{sup ?m}q{sup n?k} where q and p are the position and momentum operators, respectively, are formal integral operators in position representation in the entire real line R for positive integers n and m. We show, by explicit construction of a dense domain, that the operators T{sub ?m,n}'s are densely defined operators in the Hilbert space L{sup 2}(R)

  18. Session 31B - Panel: Opportunities in the UK with the Nuclear Decommissioning Authority (NDA)

    SciTech Connect (OSTI)

    Benda, Gary; Hayes, David; Gorham, Ron; Wareing, Mark; Simper, Adrian; Selby, Terry

    2006-07-01

    The NDA participated in a panel session 31B on Wednesday afternoon starting at 3:15. The NDA is a non-departmental public body, set up in April 2005 under the Energy Act 2004 to take strategic responsibility for the UK's nuclear legacy. Details of their organization and history are located on their web site at www.nda.gov.uk. Also copies of their Power Point presentations made at WM'06 are available on their web site. Their core objective is to ensure that the 20 civil public sector nuclear sites under our ownership are decommissioned and cleaned up safely, securely, cost effectively and in ways that protect the environment for this and future generations. They lead the development of a unified and coherent decommissioning strategy, working in partnership with regulators and site licensees to achieve best value, optimum impact on local communities, and the highest environmental standards. The NDA's main task is the decommissioning and clean up of civil nuclear sites. If the Government decides it is necessary, however, the Energy Act 2004 allows the NDA to take responsibility for sites currently operated by, or on behalf of, the Ministry of Defence (MoD). Resources will then be transferred from the MoD to meet the costs of clean up. The NDA made a number of presentations to allow conference delegates the opportunity to understand some of the major aspects of their work and to interact with NDA staff. These included the following topics and gave opportunity for audience discussion: - A brief presentation to update on progress by the NDA; - Outline of low level waste management and the prioritisation process; - Discussion of the competition schedule related to low level waste management and the Drigg site. The following presentations and handout were delivered in various sessions of the conference as noted below and are available on their web page including the WM'06 Plenary Session presentation by Sir Anthony Cleaver, Chairman of the NDA. During Session 31B, the following Power Point presentations were made. NDA Overview by David Hayes, Director of Special Projects National M and O Contractor Work Prioritisation Process by Mark Wareing, including topics on: - Need for prioritisation; - Development of the process; - Using the process as a measure of progress. Competition by Ron Gorham, Head of Procurement, including topics on: - The current model; - What NDA are actually competing; - The acquisition process; - NDA aspirations for competition; - NDA aspirations from the market. Low Level Waste Contracting in the UK by Adrian Simper, Expenditure and Programme Strategy Manager, including topics on: - Low Level Waste: NDA responsibilities, Definitions, Arisings; - Proposed NDA Procurement for LLW Management: Scope, Contracting approach, Timetable. The NDA responded to questions from the audience and also announced that the NDA will be holding a special Industry Day for potential contractors interested in the first NDA competition - the Low Level Waste Repository near Drigg in Cumbria. The event is scheduled on the 25-26 April 2006 with more details on their web site at www.nda.gov.uk. (authors)

  19. The impact of coal chlorine on the fireside corrosion behavior of boiler tubing: A UK perspective

    SciTech Connect (OSTI)

    James, P.J.; Pinder, L.W.

    1997-08-01

    Boiler tube failures are the principal cause of loss of power plant availability worldwide. A significant proportion of the failures in the furnace wall and pendant/platen superheater and reheater stages are the result, either directly or indirectly, of excessive metal loss by fireside corrosion. Despite fundamental differences in the corrosion mechanisms active on furnace walls (gaseous) and superheater/reheater stages (molten salt), much of the worsening fireside corrosion problems experienced in both sections on UK plant in the 1960`s and 1970`s was attributed to fuel chemistry, in particular the coal chlorine content. This paper explores the more recent history of fireside corrosion in CEGB and PowerGen Stations and details the current view of the impact of coal chlorine on the wastage mechanisms concerned in each boiler stage.

  20. Cold Vacuum Drying facility design basis accident analysis documentation

    SciTech Connect (OSTI)

    CROWE, R.D.

    2000-08-08

    This document provides the detailed accident analysis to support HNF-3553, Annex B, Spent Nuclear Fuel Project Final Safety Analysis Report (FSAR), ''Cold Vacuum Drying Facility Final Safety Analysis Report.'' All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the FSAR. The calculations in this document address the design basis accidents (DBAs) selected for analysis in HNF-3553, ''Spent Nuclear Fuel Project Final Safety Analysis Report'', Annex B, ''Cold Vacuum Drying Facility Final Safety Analysis Report.'' The objective is to determine the quantity of radioactive particulate available for release at any point during processing at the Cold Vacuum Drying Facility (CVDF) and to use that quantity to determine the amount of radioactive material released during the DBAs. The radioactive material released is used to determine dose consequences to receptors at four locations, and the dose consequences are compared with the appropriate evaluation guidelines and release limits to ascertain the need for preventive and mitigative controls.

  1. Hanford External Dosimetry Technical Basis Manual PNL-MA-842

    SciTech Connect (OSTI)

    Rathbone, Bruce A.

    2005-02-25

    The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNL’s Hanford External Dosimetry Program which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. Rev. 0 marks the first revision to be released through PNNL’s Electronic Records & Information Capture Architecture (ERICA) database.

  2. Electronic structure basis for the extraordinary magnetoresistance in WTe2

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Pletikosić, I.; Ali, Mazhar N.; Fedorov, A. V.; Cava, R. J.; Valla, T.

    2014-11-19

    The electronic structure basis of the extremely large magnetoresistance in layered non-magnetic tungsten ditelluride has been investigated by angle-resolved photoelectron spectroscopy. Hole and electron pockets of approximately the same size were found at the Fermi level, suggesting that carrier compensation should be considered the primary source of the effect. The material exhibits a highly anisotropic, quasi one-dimensional Fermi surface from which the pronounced anisotropy of the magnetoresistance follows. As a result, a change in the Fermi surface with temperature was found and a high-density-of-states band that may take over conduction at higher temperatures and cause the observed turn-on behavior ofmore » the magnetoresistance in WTe₂ was identified.« less

  3. Electronic structure basis for the titanic magnetoresistance in WTe?

    SciTech Connect (OSTI)

    Pletikosic, I.; Ali, Mazhar N.; Fedorov, A. V.; Cava, R. J.; Valla, T.

    2014-11-19

    The electronic structure basis of the extremely large magnetoresistance in layered non-magnetic tungsten ditelluride has been investigated by angle-resolved photoelectron spectroscopy. Hole and electron pockets of approximately the same size were found at the Fermi level, suggesting that carrier compensation should be considered the primary source of the effect. The material exhibits a highly anisotropic, quasi one-dimensional Fermi surface from which the pronounced anisotropy of the magnetoresistance follows. A change in the Fermi surface with temperature was found and a high-density-of-states band that may take over conduction at higher temperatures and cause the observed turn-on behavior of the magnetoresistance in WTe? was identified.

  4. Electronic structure basis for the titanic magnetoresistance in WTe?

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Pletikosic, I.; Ali, Mazhar N.; Fedorov, A. V.; Cava, R. J.; Valla, T.

    2014-11-19

    The electronic structure basis of the extremely large magnetoresistance in layered non-magnetic tungsten ditelluride has been investigated by angle-resolved photoelectron spectroscopy. Hole and electron pockets of approximately the same size were found at the Fermi level, suggesting that carrier compensation should be considered the primary source of the effect. The material exhibits a highly anisotropic, quasi one-dimensional Fermi surface from which the pronounced anisotropy of the magnetoresistance follows. A change in the Fermi surface with temperature was found and a high-density-of-states band that may take over conduction at higher temperatures and cause the observed turn-on behavior of the magnetoresistance inmoreWTe? was identified.less

  5. Draft Geologic Disposal Requirements Basis for STAD Specification

    SciTech Connect (OSTI)

    Ilgen, Anastasia G.; Bryan, Charles R.; Hardin, Ernest

    2015-03-25

    This document provides the basis for requirements in the current version of Performance Specification for Standardized Transportation, Aging, and Disposal Canister Systems, (FCRD-NFST-2014-0000579) that are driven by storage and geologic disposal considerations. Performance requirements for the Standardized Transportation, Aging, and Disposal (STAD) canister are given in Section 3.1 of that report. Here, the requirements are reviewed and the rationale for each provided. Note that, while FCRD-NFST-2014-0000579 provides performance specifications for other components of the STAD storage system (e.g. storage overpack, transfer and transportation casks, and others), these have no impact on the canister performance during disposal, and are not discussed here.

  6. Hanford External Dosimetry Technical Basis Manual PNL-MA-842

    SciTech Connect (OSTI)

    Rathbone, Bruce A.

    2009-08-28

    The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNL’s Hanford External Dosimetry Program (HEDP) which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee (HPDAC) which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. The first revision to be released through PNNL’s Electronic Records & Information Capture Architecture (ERICA) database was designated Revision 0. Revision numbers that are whole numbers reflect major revisions typically involving changes to all chapters in the document. Revision numbers that include a decimal fraction reflect minor revisions, usually restricted to selected chapters or selected pages in the document.

  7. CONTROL TESTING OF THE UK NATIONAL NUCLEAR LABORATORY'S RADBALL TECHNOLOGY AT SAVANNAH RIVER NATIONAL LABORATORY

    SciTech Connect (OSTI)

    Farfan, E.

    2009-11-23

    The UK National Nuclear Laboratory (NNL) has developed a remote, non-electrical, radiation-mapping device known as RadBall (patent pending), which offers a means to locate and quantify radiation hazards and sources within contaminated areas of the nuclear industry. To date, the RadBall has been deployed in a number of technology trials in nuclear waste reprocessing plants at Sellafield in the UK. The trials have demonstrated the successful ability of the RadBall technology to be deployed and retrieved from active areas. The positive results from these initial deployment trials and the anticipated future potential of RadBall have led to the NNL partnering with the Savannah River National Laboratory (SRNL) to further underpin and strengthen the technical performance of the technology. RadBall consists of a colander-like outer shell that houses a radiation-sensitive polymer sphere. It has no power requirements and can be positioned in tight or hard-to reach places. The outer shell works to collimate radiation sources and those areas of the polymer sphere that are exposed react, becoming increasingly less transparent, in proportion to the absorbed dose. The polymer sphere is imaged in an optical-CT scanner which produces a high resolution 3D map of optical attenuation coefficients. Subsequent analysis of the optical attenuation maps provides information on the spatial distribution and strength of the sources in a given area forming a 3D characterization of the area of interest. This study completed at SRNL addresses key aspects of the testing of the RadBall technology. The first set of tests was performed at Savannah River Nuclear Solutions Health Physics Instrument Calibration Laboratory (HPICL) using various gamma-ray sources and an x-ray machine with known radiological characteristics. The objective of these preliminary tests was to identify the optimal dose and collimator thickness. The second set of tests involved a highly contaminated hot cell. The objective of this part of the testing was to characterize a hot cell with unknown radiation sources. The RadBall calibration experiments and hot cell deployment completed at SRNL were successful in that for each trial, the technology was able to locate the radiation sources. The NNL believe that the ability of RadBall to be remotely deployed with no electrical supplies into difficult to access areas of plant and locate and quantify radiation hazards is a unique radiation mapping service. The NNL consider there to be significant business potential associated with this innovative technology.

  8. Hanford External Dosimetry Technical Basis Manual PNL-MA-842

    SciTech Connect (OSTI)

    Rathbone, Bruce A.

    2011-04-04

    The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at the U.S. Department of Energy (DOE) Hanford site. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with requirements of 10 CFR 835, the DOE Laboratory Accreditation Program, the DOE Richland Operations Office, DOE Office of River Protection, DOE Pacific Northwest Office of Science, and Hanford’s DOE contractors. The dosimetry system is operated by the Pacific Northwest National Laboratory (PNNL) Hanford External Dosimetry Program which provides dosimetry services to PNNL and all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since its inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. The first revision to be released through PNNL’s Electronic Records & Information Capture Architecture database was designated Revision 0. Revision numbers that are whole numbers reflect major revisions typically involving significant changes to all chapters in the document. Revision numbers that include a decimal fraction reflect minor revisions, usually restricted to selected chapters or selected pages in the document. Maintenance and distribution of controlled hard copies of the manual by PNNL was discontinued beginning with Revision 0.2.

  9. Hanford External Dosimetry Technical Basis Manual PNL-MA-842

    SciTech Connect (OSTI)

    Rathbone, Bruce A.

    2007-03-12

    The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNL’s Hanford External Dosimetry Program (HEDP) which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee (HPDAC) which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. Rev. 0 marks the first revision to be released through PNNL’s Electronic Records & Information Capture Architecture (ERICA) database. Revision numbers that are whole numbers reflect major revisions typically involving changes to all chapters in the document. Revision numbers that include a decimal fraction reflect minor revisions, usually restricted to selected chapters or selected pages in the document. Revision Log: Rev. 0 (2/25/2005) Major revision and expansion. Rev. 0.1 (3/12/2007) Minor revision. Updated Chapters 5, 6 and 9 to reflect change in default ring calibration factor used in HEDP dose calculation software. Factor changed from 1.5 to 2.0 beginning January 1, 2007. Pages on which changes were made are as follows: 5.23, 5.69, 5.78, 5.80, 5.82, 6.3, 6.5, 6.29, 9.2.

  10. Hanford External Dosimetry Technical Basis Manual PNL-MA-842

    SciTech Connect (OSTI)

    Rathbone, Bruce A.

    2010-04-01

    The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at the U.S. Department of Energy (DOE) Hanford site. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with requirements of 10 CFR 835, the DOE Laboratory Accreditation Program, the DOE Richland Operations Office, DOE Office of River Protection, DOE Pacific Northwest Office of Science, and Hanford’s DOE contractors. The dosimetry system is operated by the Pacific Northwest National Laboratory (PNNL) Hanford External Dosimetry Program which provides dosimetry services to PNNL and all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since its inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. The first revision to be released through PNNL’s Electronic Records & Information Capture Architecture database was designated Revision 0. Revision numbers that are whole numbers reflect major revisions typically involving significant changes to all chapters in the document. Revision numbers that include a decimal fraction reflect minor revisions, usually restricted to selected chapters or selected pages in the document. Maintenance and distribution of controlled hard copies of the manual by PNNL was discontinued beginning with Revision 0.2.

  11. Development of engineering technology basis for industrialization of pyrometallurgical reprocessing

    SciTech Connect (OSTI)

    Koyama, Tadafumi; Hijikata, Takatoshi; Yokoo, Takeshi; Inoue, Tadashi

    2007-07-01

    Development of the engineering technology basis of pyrometallurgical reprocessing is a key issue for industrialization. For development of the transport technologies of molten salt and liquid cadmium at around 500 deg. C, a salt transport test rig and a metal transport test rig were installed in Ar glove box. Function of centrifugal pump and 1/2' declined tubing were confirmed with LiCl- KCl molten salt. The transport behavior of molten salt was found to follow that of water. Function of centrifugal pump, vacuum sucking and 1/2' declined tubing were confirmed with liquid Cd. With employing the transport technologies, industrialization applicable electro-refiner was newly designed and engineering-scale model was fabricated in Ar glove box. The electro-refiner has semi-continuous liquid Cd cathode instead of conventional one used in small-scale tests. With using actinide-simulating elements, demonstration of industrial-scale throughput will be carried out in this electro-refiner for more precise evaluation of industrialization potential of pyrometallurgical reprocessing. (authors)

  12. Hanford Technical Basis for Multiple Dosimetry Effective Dose Methodology

    SciTech Connect (OSTI)

    Hill, Robin L.; Rathbone, Bruce A.

    2010-08-01

    The current method at Hanford for dealing with the results from multiple dosimeters worn during non-uniform irradiation is to use a compartmentalization method to calculate the effective dose (E). The method, as documented in the current version of Section 6.9.3 in the 'Hanford External Dosimetry Technical Basis Manual, PNL-MA-842,' is based on the compartmentalization method presented in the 1997 ANSI/HPS N13.41 standard, 'Criteria for Performing Multiple Dosimetry.' With the adoption of the ICRP 60 methodology in the 2007 revision to 10 CFR 835 came changes that have a direct affect on the compartmentalization method described in the 1997 ANSI/HPS N13.41 standard, and, thus, to the method used at Hanford. The ANSI/HPS N13.41 standard committee is in the process of updating the standard, but the changes to the standard have not yet been approved. And, the drafts of the revision of the standard tend to align more with ICRP 60 than with the changes specified in the 2007 revision to 10 CFR 835. Therefore, a revised method for calculating effective dose from non-uniform external irradiation using a compartmental method was developed using the tissue weighting factors and remainder organs specified in 10 CFR 835 (2007).

  13. Climate Change: The Physical Basis and Latest Results

    ScienceCinema (OSTI)

    None

    2011-10-06

    The 2007 Assessment Report of the Intergovernmental Panel on Climate Change (IPCC) concludes: "Warming in the climate system is unequivocal." Without the contribution of Physics to climate science over many decades, such a statement would not have been possible. Experimental physics enables us to read climate archives such as polar ice cores and so provides the context for the current changes. For example, today the concentration of CO2 in the atmosphere, the second most important greenhouse gas, is 28% higher than any time during the last 800,000 years. Classical fluid mechanics and numerical mathematics are the basis of climate models from which estimates of future climate change are obtained. But major instabilities and surprises in the Earth System are still unknown. These are also to be considered when the climatic consequences of proposals for geo-engineering are estimated. Only Physics will permit us to further improve our understanding in order to provide the foundation for policy decisions facing the global climate change challenge.

  14. A premium price electricity market for the emerging biomass industry in the UK

    SciTech Connect (OSTI)

    Kettle, R.

    1995-11-01

    The Non-Fossil Fuel Obligation (NFFO) is the means by which the UK Government creates an initial market for renewable sources of electricity. For the first time the third round of the competition for NFFO contracts included a band for {open_quote}energy crops and agricultural and forestry wastes{close_quote}. The NFFO Order which obliges the Regional Electricity Companies (RECs) in England and Wales to contract for a specified electricity generating capacity from renewable resources was made in December 1994. It required 19.06 MW of wood gasification capacity and 103.81 MW from other energy crops and agricultural and forestry wastes. The purpose of these Orders is to create an initial market so that in the not too distant future the most promising renewables can compete without financial support. This paper describes how these projects are expected to contribute to this policy. It also considers how the policy objective of convergence under successive Orders between the price paid under the NFFO and the market price for electricity might be accomplished.

  15. US/UK second level panel discussions on the health and value of: Ageing and lifetime predictions (u)

    SciTech Connect (OSTI)

    Castro, Richard G

    2011-01-18

    Many healthy physics, engineering, and materials exchanges are being accomplished in ageing and lifetime prediction that directly supports US and UK Stockpile Management Programs. Lifetime assessment studies of silicon foams under compression - Joint AWE/LANLlLLNL study of compression set in stress cushions completed. Provides phenomenological prediction out to 50 years. Polymer volatile out-gassing studies - New exchange on the out-gassing of Ethylene Vinyl Acetate (EVA) using isotopic {sup 13}C labeling studies to interrogate mechanistic processes. Infra-red (IR) gas cell analytical capabilities developed by AWE will be used to monitor polymer out-gassing profiles. Pu Strength ageing Experiments and Constitutive Modeling - In recently compared modeling strategies for ageing effects on Pu yield strength at high strain rates, a US/UK consensus was reached on the general principle that the ageing effect is additive and not multiplicative. The fundamental mechanisms for age-strengthening in Pu remains unknown. Pu Surface and Interface Reactions - (1) US/UK secondment resulted in developing a metal-metal oxide model for radiation damaged studies consistent with a Modified Embedded Atom Method (MEAM) potential; and (2) Joint US/UK collaboration to study the role of impurities in hydride initiation. Detonator Ageing (wide range of activities) - (1) Long-term ageing study with field trials at Pantex incorporating materials from LANL, LLNL, SNL and AWE; (2) Characterization of PETN growth to detonation process; (3) Detonator performance modeling; and (4) Performance fault tree analysis. Benefits are a unified approach to lifetime prediction that Includes: materials characterization and the development of ageing models through improved understanding of the relationship between materials properties, ageing properties and detonator performance.

  16. Hanford External Dosimetry Technical Basis Manual PNL-MA-842

    SciTech Connect (OSTI)

    Rathbone, Bruce A.

    2010-01-01

    The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNL’s Hanford External Dosimetry Program (HEDP) which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee (HPDAC) which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since its inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. The first revision to be released through PNNL’s Electronic Records & Information Capture Architecture (ERICA) database was designated Revision 0. Revision numbers that are whole numbers reflect major revisions typically involving significant changes to all chapters in the document. Revision numbers that include a decimal fraction reflect minor revisions, usually restricted to selected chapters or selected pages in the document. Maintenance and distribution of controlled hard copies of the manual by PNNL was discontinued beginning with Revision 0.2. Revision Log: Rev. 0 (2/25/2005) Major revision and expansion. Rev. 0.1 (3/12/2007) Updated Chapters 5, 6 and 9 to reflect change in default ring calibration factor used in HEDP dose calculation software. Factor changed from 1.5 to 2.0 beginning January 1, 2007. Pages on which changes were made are as follows: 5.23, 5.69, 5.78, 5.80, 5.82, 6.3, 6.5, 6.29, and 9.2. Rev 0.2 (8/28/2009) Updated Chapters 3, 5, 6, 8 and 9. Chapters 6 and 8 were significantly expanded. References in the Preface and Chapters 1, 2, 4, and 7 were updated to reflect updates to DOE documents. Approved by HPDAC on 6/2/2009. Rev 1.0 (1/1/2010) Major revision. Updated all chapters to reflect the Hanford site wide implementation on January 1, 2010 of new DOE requirements for occupational radiation protection. The new requirements are given in the June 8, 2007 amendment to 10 CFR 835 Occupational Radiation Protection (Federal Register, June 8, 2007. Title 10 Part 835. U.S., Code of Federal Regulations, Vol. 72, No. 110, 31904-31941). Revision 1.0 to the manual replaces ICRP 26 dosimetry concepts and terminology with ICRP 60 dosimetry concepts and terminology and replaces external dose conversion factors from ICRP 51 with those from ICRP 74 for use in measurement of operational quantities with dosimeters. Descriptions of dose algorithms and dosimeter response characteristics, and field performance were updated to reflect changes in the neutron quality factors used in the measurement of operational quantities.

  17. The Structural Basis for Tight Control of PP2A Methylation and...

    Office of Scientific and Technical Information (OSTI)

    The Structural Basis for Tight Control of PP2A Methylation and Function by LCMT-1 Citation Details In-Document Search Title: The Structural Basis for Tight Control of PP2A ...

  18. Safety evaluation of MHTGR licensing basis accident scenarios

    SciTech Connect (OSTI)

    Kroeger, P.G.

    1989-04-01

    The safety potential of the Modular High-Temperature Gas Reactor (MHTGR) was evaluated, based on the Preliminary Safety Information Document (PSID), as submitted by the US Department of Energy to the US Nuclear Regulatory Commission. The relevant reactor safety codes were extended for this purpose and applied to this new reactor concept, searching primarily for potential accident scenarios that might lead to fuel failures due to excessive core temperatures and/or to vessel damage, due to excessive vessel temperatures. The design basis accident scenario leading to the highest vessel temperatures is the depressurized core heatup scenario without any forced cooling and with decay heat rejection to the passive Reactor Cavity Cooling System (RCCS). This scenario was evaluated, including numerous parametric variations of input parameters, like material properties and decay heat. It was found that significant safety margins exist, but that high confidence levels in the core effective thermal conductivity, the reactor vessel and RCCS thermal emissivities and the decay heat function are required to maintain this safety margin. Severe accident extensions of this depressurized core heatup scenario included the cases of complete RCCS failure, cases of massive air ingress, core heatup without scram and cases of degraded RCCS performance due to absorbing gases in the reactor cavity. Except for no-scram scenarios extending beyond 100 hr, the fuel never reached the limiting temperature of 1600/degree/C, below which measurable fuel failures are not expected. In some of the scenarios, excessive vessel and concrete temperatures could lead to investment losses but are not expected to lead to any source term beyond that from the circulating inventory. 19 refs., 56 figs., 11 tabs.

  19. City of Cambridge, Nebraska (Utility Company) | Open Energy Informatio...

    Open Energy Info (EERE)

    Yes Activity Buying Transmission Yes Activity Distribution Yes Activity Wholesale Marketing Yes Activity Retail Marketing Yes This article is a stub. You can help OpenEI by...

  20. SOME RECENT TECHNOLOGY DEVELOPMENTS FROM THE UK'S NATIONAL NUCLEAR LABORATORY TO ENABLE HAZARD CHARACTERISATION FOR NUCLEAR DECOMMISSIONING APPLICATIONS

    SciTech Connect (OSTI)

    Farfan, E.; Foley, T.

    2010-02-11

    Under its programme of self investment Internal Research and Development (IR&D), the UK's National Nuclear Laboratory (NNL) is addressing the requirement for development in technology to enable hazard characterisation for nuclear decommissioning applications. Three such examples are described here: (1) RadBall developed by the NNL (patent pending) is a deployable baseball-sized radiation mapping device which can, from a single location, locate and quantify radiation hazards. RadBall offers a means to collect information regarding the magnitude and distribution of radiation in a given cell, glovebox or room to support the development of a safe, cost effective decontamination strategy. RadBall requires no electrical supplies and is relatively small, making it easy to be deployed and used to map radiation hazards in hard to reach areas. Recent work conducted in partnership with the Savannah River National Laboratory (SRNL) is presented. (2) HiRAD (patent pending) has been developed by the NNL in partnership with Tracerco Ltd (UK). HiRAD is a real-time, remotely deployed, radiation detection device designed to operate in elevated levels of radiation (i.e. thousands and tens of thousands of Gray) as seen in parts of the nuclear industry. Like the RadBall technology, the HiRAD system does not require any electrical components, the small dimensions and flexibility of the device allow it to be positioned in difficult to access areas (such as pipe work). HiRAD can be deployed as a single detector, a chain, or as an array giving the ability to monitor large process areas. Results during the development and deployment of the technology are presented. (3) Wireless Sensor Network is a NNL supported development project led by the University of Manchester (UK) in partnership with Oxford University (UK). The project is concerned with the development of wireless sensor network technology to enable the underwater deployment and communication of miniaturised probes allowing pond monitoring and mapping. The potential uses, within the nuclear sector alone, are both numerous and significant in terms of the proceeding effort to clean up the UK's nuclear waste legacy.

  1. A new paradigm for the molecular basis of rubber elasticity

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Hanson, David E.; Barber, John L.

    2015-02-19

    The molecular basis for rubber elasticity is arguably the oldest and one of the most important questions in the field of polymer physics. The theoretical investigation of rubber elasticity began in earnest almost a century ago with the development of analytic thermodynamic models, based on simple, highly-symmetric configurations of so-called Gaussian chains, i.e. polymer chains that obey Markov statistics. Numerous theories have been proposed over the past 90 years based on the ansatz that the elastic force for individual network chains arises from the entropy change associated with the distribution of end-to-end distances of a free polymer chain. There aremore » serious philosophical objections to this assumption and others, such as the assumption that all network nodes undergo affine motion and that all of the network chains have the same length. Recently, a new paradigm for elasticity in rubber networks has been proposed that is based on mechanisms that originate at the molecular level. Using conventional statistical mechanics analyses, quantum chemistry, and molecular dynamics simulations, the fundamental entropic and enthalpic chain extension forces for polyisoprene (natural rubber) have been determined, along with estimates for the basic force constants. Concurrently, the complex morphology of natural rubber networks (the joint probability density distributions that relate the chain end-to-end distance to its contour length) has also been captured in a numerical model. When molecular chain forces are merged with the network structure in this model, it is possible to study the mechanical response to tensile and compressive strains of a representative volume element of a polymer network. As strain is imposed on a network, pathways of connected taut chains, that completely span the network along strain axis, emerge. Although these chains represent only a few percent of the total, they account for nearly all of the elastic stress at high strain. Here we provide a brief review of previous elasticity theories and their deficiencies, and present a new paradigm with an emphasis on experimental comparisons.« less

  2. Issues in UK cleanup and decommissioning; a strategic R and D programme

    SciTech Connect (OSTI)

    Tinsley, T.P.; Ashley, V.B.; Morgan, H.G.; Fairhall, G.A.

    2008-07-01

    Nexia Solutions is contracted to manage and carry out research on behalf of the Nuclear Decommissioning Authority (NDA). This paper will describe the nuclear research ongoing and how it fits in with the UK cleanup and decommissioning strategy. The aim of the strategic R and D programme is to assist the NDA in maintaining a technical portfolio which will:- - identify and address challenges and clean-up problems that do not have an existing solution; - resolve potential inconsistencies between sites in the technical bases for certain strategic decisions and their implementation; - maintain options while developing strategy (emerging risks); - save costs by developing multi-site solutions; - provide technology, skills and facilities on the timescale required. The strategy for the R and D programme has been developed from a top-level approach by understanding the challenges which need to be addressed and prioritising these according to the objectives of the programme. The programme has demonstrated that a technical portfolio comprising six areas, each containing a number of key themes, is appropriate to address the technical challenges which the NDA faces and aligns with the NDA's technical issues register. An important aspect of the R and D programme is that it should create opportunities for undertaking the NDA mission more effectively. This arises from the emphasis given in those technical programmes which define the challenge more precisely and thus provide a platform from which to produce innovative solutions. The paper will present an overview of the strategic R and D programme along with the key technical programme areas. Examples will be provided of the technical work ongoing, and the results obtained so far. (author)

  3. TECHNICAL BASIS FOR VENTILATION REQUIREMENTS IN TANK FARMS OPERATING SPECIFICATIONS DOCUMENTS

    SciTech Connect (OSTI)

    BERGLIN, E J

    2003-06-23

    This report provides the technical basis for high efficiency particulate air filter (HEPA) for Hanford tank farm ventilation systems (sometimes known as heating, ventilation and air conditioning [HVAC]) to support limits defined in Process Engineering Operating Specification Documents (OSDs). This technical basis included a review of older technical basis and provides clarifications, as necessary, to technical basis limit revisions or justification. This document provides an updated technical basis for tank farm ventilation systems related to Operation Specification Documents (OSDs) for double-shell tanks (DSTs), single-shell tanks (SSTs), double-contained receiver tanks (DCRTs), catch tanks, and various other miscellaneous facilities.

  4. Establishing the Technical Basis for Disposal of Heat-generating Waste in

    Energy Savers [EERE]

    Salt | Department of Energy Establishing the Technical Basis for Disposal of Heat-generating Waste in Salt Establishing the Technical Basis for Disposal of Heat-generating Waste in Salt The report summarizes available historic tests and the developed technical basis for disposal of heat-generating waste in salt, and the means by which a safety case for disposal of heat generating waste at a generic salt site can be initiated from the existing technical basis. Though the basis for a salt

  5. CRITICALITY SAFETY CONTROLS AND THE SAFETY BASIS AT PFP

    SciTech Connect (OSTI)

    Kessler, S

    2009-04-21

    With the implementation of DOE Order 420.1B, Facility Safety, and DOE-STD-3007-2007, 'Guidelines for Preparing Criticality Safety Evaluations at Department of Energy Non-Reactor Nuclear Facilities', a new requirement was imposed that all criticality safety controls be evaluated for inclusion in the facility Documented Safety Analysis (DSA) and that the evaluation process be documented in the site Criticality Safety Program Description Document (CSPDD). At the Hanford site in Washington State the CSPDD, HNF-31695, 'General Description of the FH Criticality Safety Program', requires each facility develop a linking document called a Criticality Control Review (CCR) to document performance of these evaluations. Chapter 5, Appendix 5B of HNF-7098, Criticality Safety Program, provided an example of a format for a CCR that could be used in lieu of each facility developing its own CCR. Since the Plutonium Finishing Plant (PFP) is presently undergoing Deactivation and Decommissioning (D&D), new procedures are being developed for cleanout of equipment and systems that have not been operated in years. Existing Criticality Safety Evaluations (CSE) are revised, or new ones written, to develop the controls required to support D&D activities. Other Hanford facilities, including PFP, had difficulty using the basic CCR out of HNF-7098 when first implemented. Interpretation of the new guidelines indicated that many of the controls needed to be elevated to TSR level controls. Criterion 2 of the standard, requiring that the consequence of a criticality be examined for establishing the classification of a control, was not addressed. Upon in-depth review by PFP Criticality Safety staff, it was not clear that the programmatic interpretation of criterion 8C could be applied at PFP. Therefore, the PFP Criticality Safety staff decided to write their own CCR. The PFP CCR provides additional guidance for the evaluation team to use by clarifying the evaluation criteria in DOE-STD-3007-2007. In reviewing documents used in classifying controls for Nuclear Safety, it was noted that DOE-HDBK-1188, 'Glossary of Environment, Health, and Safety Terms', defines an Administrative Control (AC) in terms that are different than typically used in Criticality Safety. As part of this CCR, a new term, Criticality Administrative Control (CAC) was defined to clarify the difference between an AC used for criticality safety and an AC used for nuclear safety. In Nuclear Safety terms, an AC is a provision relating to organization and management, procedures, recordkeeping, assessment, and reporting necessary to ensure safe operation of a facility. A CAC was defined as an administrative control derived in a criticality safety analysis that is implemented to ensure double contingency. According to criterion 2 of Section IV, 'Linkage to the Documented Safety Analysis', of DOESTD-3007-2007, the consequence of a criticality should be examined for the purposes of classifying the significance of a control or component. HNF-PRO-700, 'Safety Basis Development', provides control selection criteria based on consequence and risk that may be used in the development of a Criticality Safety Evaluation (CSE) to establish the classification of a component as a design feature, as safety class or safety significant, i.e., an Engineered Safety Feature (ESF), or as equipment important to safety; or merely provides defense-in-depth. Similar logic is applied to the CACs. Criterion 8C of DOE-STD-3007-2007, as written, added to the confusion of using the basic CCR from HNF-7098. The PFP CCR attempts to clarify this criterion by revising it to say 'Programmatic commitments or general references to control philosophy (e.g., mass control or spacing control or concentration control as an overall control strategy for the process without specific quantification of individual limits) is included in the PFP DSA'. Table 1 shows the PFP methodology for evaluating CACs. This evaluation process has been in use since February of 2008 and has proven to be simple and effective. Each control identified i

  6. Evolution of the Business Environment Surrounding the UK's Nuclear Site Cleanup Program

    SciTech Connect (OSTI)

    Miskimin, P.A.; Lees, P.M.; Wall, C.E.E.

    2006-07-01

    In April 2005 twenty civil nuclear sites in the United Kingdom became the responsibility of the Nuclear Decommissioning Authority (NDA), a new organization created by the British Government to manage the cleanup of these sites. As a key part of this transition, the NDA became the owner and manager of these sites, which formerly were owned by the site operators, British Nuclear Fuels Limited plc (BNFL) and the United Kingdom Atomic Energy Authority (UKAEA). This was one of the most significant events in the history of the United Kingdom's nuclear industry and represented a true sea change, affecting many aspects of life and business on and around these sites as well as nationally. The NDA's budget for the cleanup of the twenty sites and the management of the overall cleanup program is approximately pounds 2 Billion per annum, almost $4 Billion. It is important to note that approximately half of this amount is spent with the supply chains which serve the management and operations contractors, including pounds 500 million at Sellafield alone. Additionally, the site management and operations contractors receive most of the pounds 2 Billion through contracts between the NDA and the various site management companies. This represents a lot of government money moving through contracts between entities, which invokes procurement and contracting rules and regulations, that while not new, have not previously been this broadly applied to nuclear site cleanup activities throughout the UK. The current estimate for the total life cycle cleanup costs for all twenty civil nuclear sites is pounds 56 Billion, a figure that is likely to increase further. The first rules to mention are the European Union Procurement Guidelines, which are designed to help ensure that procurements involving government funds are conducted in an open, fair, and transparent environment. While it is difficult to argue with the intent of these rules, at least for now they are having a slowing down effect on placing contracts via the major procurements being conducted in support of the nuclear site cleanup program. The next most powerful influence is the NDA itself, which has oversight responsibility for procurements conducted by the site management and operations contractors. The NDA must, of necessity, maintain some level of review over major procurements, but how best to do so with a limited number of staff, without slowing down the awarding of contracts? More dramatic in their impact on the UK's nuclear industry will be the competitive procurements to be conducted by the NDA to select the best site operators for the twenty sites. These major procurements, while common in the USA and elsewhere, will be new to the NDA's nuclear site cleanup program. Considering the large contract values expected, the procurements should attract some of the best talent in nuclear site cleanup. It is anticipated that these procurements will necessitate contractors to compete at the highest level, leaving no stone unturned to maximize the chance of being selected. Contract awards are expected to be in the range of 100 million pounds to several billion pounds. The first such procurement is currently planned to begin in April 2006, according to the NDA's draft strategy document. Lastly, the business relationships with local suppliers to the nuclear sites are also changing. These suppliers will be required to compete, primarily for contracts let by subcontractors to the site management and operations contractors, and even by sub-sub contractors, rather than directly from the site management and operations contractors. The benign paternalism previously practiced at some sites by the management and operations contractors should also cease, of necessity. Many other business aspects will evolve as well, such as contract awards being based on best value, rather than on lowest price or lowest hourly rate. Electronic commerce is expected to become more widely used. Even as late as 2003, little electronic commerce was being utilized at the nuclear sites now being managed by the NDA. Contracting terms are expected to move toward a more commercial orientation, a process already begun. This paper will examine the changing procurement and contracting environment under the NDA's leadership and will provide information of interest to contractors wishing to win their share (and more) of business in the emerging nuclear site cleanup program in the United Kingdom. (authors)

  7. Enterprise Assessments Targeted Review of the Safety Basis at the Savannah

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    River Site F-Area Central Laboratory Facility - January 2016 | Department of Energy Basis at the Savannah River Site F-Area Central Laboratory Facility - January 2016 Enterprise Assessments Targeted Review of the Safety Basis at the Savannah River Site F-Area Central Laboratory Facility - January 2016 January 2016 Review of the Safety Basis F-Area Central Laboratory Facility at the Savannah River Site The Office of Nuclear Safety and Environmental Assessments, within the U.S. Department of

  8. Nuclear Safety Basis Program Review Overview and Management Oversight Standard Review Plan

    Broader source: Energy.gov [DOE]

    This SRP, Nuclear Safety Basis Program Review, consists of five volumes. It provides information to help strengthen the technical rigor of line management oversight and federal monitoring of DOE nuclear facilities. It provides a primer on the safety basis development and documentation process used by the DOE. It also provides a set of LOIs for the review of safety basis programs and documents of nuclear facilities at various stages of the facility life cycle.

  9. Report to the Secretary of Energy on Beyond Design Basis Event...

    Broader source: Energy.gov (indexed) [DOE]

    BDBEReportfinal.pdf More Documents & Publications Report to the Secretary of Energy on Beyond Design Basis Event Pilot Evaluations, Results and Recommendations for Improvements...

  10. Technical Basis and Considerations for DOE M 435.1-1 (Appendix A)

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1999-07-09

    This appendix establishes the technical basis of the order revision process and of each of the requirements included in the revised radioactive waste management order.

  11. Improving Department of Energy Capabilities for Mitigating Beyond Design Basis Events

    Broader source: Energy.gov [DOE]

    This is a level 1 operating experience document providing direction for Improving Department of Energy Capabilities for Mitigating Beyond Design Basis Events. [OE-1: 2013-01

  12. Structural basis for the prion-like MAVS filaments in antiviral...

    Office of Scientific and Technical Information (OSTI)

    in antiviral innate immunity Citation Details In-Document Search Title: Structural basis for the prion-like MAVS filaments in antiviral innate immunity Authors: Xu, Hui ; He, ...

  13. 2010 DOE National Science Bowl® Photos - Basis Charter School...

    Office of Science (SC) Website

    Basis Charter School National Science Bowl (NSB) NSB Home About National Science Bowl Contacts Regional Science Bowl Coordinators National Science Bowl FAQ's Alumni Past National ...

  14. CRAD, Review of Safety Basis Development - May 6, 2013 | Department of

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Energy Review of Safety Basis Development - May 6, 2013 CRAD, Review of Safety Basis Development - May 6, 2013 May 6, 2013 Review of Safety Basis Development for the Los Alamos National Laboratory Transuranic Waste Facility (HSS CRAD 45-59, Rev. 0) The review will consider selected aspects of the development of safety basis for the Transuranic Waste Facility (TWF) to assess the extent to which safety is integrated into the design of the TWF in accordance with DOE directives; in particular,

  15. Conference Abstracts & Book Chapters | Photosynthetic Antenna...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Solar Fuels, T. Wydrzynski and W. Hillier, Eds., Royal Society of Chemistry, Cambridge, UK. Frank HA, Magdaong N, Niedzwiedzki DM, LaFountain AM, Gardiner AT, Carey A-M,...

  16. Enecsys | Open Energy Information

    Open Energy Info (EERE)

    Enecsys Jump to: navigation, search Name: Enecsys Place: Cambridge, United Kingdom Zip: CB4 OBZ Product: UK-based micro-inverter developer. Coordinates: 43.003745, -89.017499...

  17. Criteria Document for B-plant Surveillance and Maintenance Phase Safety Basis Document

    SciTech Connect (OSTI)

    SCHWEHR, B.A.

    1999-08-31

    This document is required by the Project Hanford Managing Contractor (PHMC) procedure, HNF-PRO-705, Safety Basis Planning, Documentation, Review, and Approval. This document specifies the criteria that shall be in the B Plant surveillance and maintenance phase safety basis in order to obtain approval of the DOE-RL. This CD describes the criteria to be addressed in the S&M Phase safety basis for the deactivated Waste Fractionization Facility (B Plant) on the Hanford Site in Washington state. This criteria document describes: the document type and format that will be used for the S&M Phase safety basis, the requirements documents that will be invoked for the document development, the deactivated condition of the B Plant facility, and the scope of issues to be addressed in the S&M Phase safety basis document.

  18. Safety basis academy summary of project implementation from 2007-2009

    SciTech Connect (OSTI)

    Johnston, Julie A

    2009-01-01

    During fiscal years 2007 through 2009, in accordance with Performance Based Incentives with DOE/NNSA Los Alamos Site Office, Los Alamos National Security (LANS) implemented and operated a Safety Basis Academy (SBA) to facilitate uniformity in technical qualifications of safety basis professionals across the nuclear weapons complex. The implementation phase of the Safety Basis Academy required development, delivery, and finalizing a set of 23 courses. The courses developed are capable of supporting qualification efforts for both federal and contractor personnel throughout the DOE/NNSA Complex. The LANS Associate Director for Nuclear and High Hazard Operations (AD-NHHO) delegated project responsibillity to the Safety Basis Division. The project was assigned to the Safety Basis Technical Services (SB-TS) Group at Los Alamos National Laboratory (LANL). The main tasks were project needs analysis, design, development, implementation of instructional delivery, and evaluation of SBA courses. DOE/NNSA responsibility for oversight of the SBA project was assigned to the Chief of Defense for Nuclear Safety, and delegated to the Authorization Basis Senior Advisor, Continuous Learning Chair (CDNS-ABSA/CLC). NNSA developed a memorandum of agreement with LANS AD-NHHO. Through a memorandum of agreement initiated by NNSA, the DOE National Training Center (NTC) will maintain the set of Safety Basis Academy courses and is able to facilitate course delivery throughout the DOE Complex.

  19. Decline of radionuclides in the nearshore environment following nuclear reactor closure: A U.K. case study

    SciTech Connect (OSTI)

    Cundy, A.B.; Croudace, I.W.; Warwick, P.E.; Bains, M.E.D.

    1999-09-01

    Radioactive discharges from nuclear facilities are frequently made into the marine environment and their fate during and after cessation of discharges is a matter of interest and concern. This study examines the decline of the radionuclides {sup 60} and {sup 65}Zn along the southern UK. coast, over the per 1988--1998, following the closure of the steam-generating heavy water (SGHW) reactor at AEA Winfrith, Dorset, UK. {sup 60}Co and {sup 65}Zn (and other activation products such as {sup 63}Ni and {sup 55}Fe) were widely dispersed in the marine environment off the central south coast of England, due to authorized releases from AEA Winfrith. Significant interaction occurred with clay-rich sediments and biota. A general exponential decline in {sup 60}Co activities (and in {sup 65}Zn activity) is found in intertidal mudflat sediments, seaweed and marine fauna in different areas along the south coast following closure of the reactor in 1990. Effective half-lives are determined which vary from 1 to 4 years in surface sediments ({sup 60}Co only), 1--4 years in seaweed and 0.5--2.5 years in crustaceans, bivalves and molluscs. Physical mixing and bioturbation largely control the rate at which {sup 60}Co declines in surface sediments. Both {sup 60}Co and {sup 65}Zn show a relatively slow rate of decline in seaweed and in marine fauna, showing that even after the virtual cessation of discharge from nuclear facilities, contamination of these organisms may persist for a number of years, albeit at reduced activities. Reasons for this persistence are likely to include absorption of radionuclides from sediment, and release and recycling of radionuclides via breakdown of contaminated organic material.

  20. Structural basis for Notch1 engagement of Delta-like 4 (Journal...

    Office of Scientific and Technical Information (OSTI)

    Title: Structural basis for Notch1 engagement of Delta-like 4 Authors: Luca, Vincent C. ; Jude, Kevin M. ; Pierce, Nathan W. ; Nachury, Maxence V. ; Fischer, Suzanne ; Garcia, K. ...

  1. Structural Basis of UV DNA-Damage Recognition by the DDB1-DDB2...

    Office of Scientific and Technical Information (OSTI)

    Recognition by the DDB1-DDB2 Complex Citation Details In-Document Search Title: Structural Basis of UV DNA-Damage Recognition by the DDB1-DDB2 Complex Ultraviolet (UV) ...

  2. Structure of P-Glycoprotein Reveals a Molecular Basis for Poly...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Structure of P-Glycoprotein Reveals a Molecular Basis for Poly-Specific Drug Binding figure 1 Figure 1. Structure of P-gp. Many forms of cancer fail to respond to chemotherapy by ...

  3. Reducing Uncertainty in the Seismic Design Basis for the Waste Treatment Plant, Hanford, Washington

    SciTech Connect (OSTI)

    Brouns, Thomas M.; Rohay, Alan C.; Reidel, Steve; Gardner, Martin G.

    2007-02-27

    The seismic design basis for the Waste Treatment Plant (WTP) at the Department of Energys (DOE) Hanford Site near Richland was re-evaluated in 2005, resulting in an increase by up to 40% in the seismic design basis. The original seismic design basis for the WTP was established in 1999 based on a probabilistic seismic hazard analysis completed in 1996. The 2005 analysis was performed to address questions raised by the Defense Nuclear Facilities Safety Board (DNFSB) about the assumptions used in developing the original seismic criteria and adequacy of the site geotechnical surveys. The updated seismic response analysis used existing and newly acquired seismic velocity data, statistical analysis, expert elicitation, and ground motion simulation to develop interim design ground motion response spectra which enveloped the remaining uncertainties. The uncertainties in these response spectra were enveloped at approximately the 84th percentile to produce conservative design spectra, which contributed significantly to the increase in the seismic design basis.

  4. NSS 18.3 Verification of Authorization Basis Documentation 12/8/03

    Broader source: Energy.gov [DOE]

    The objective of this surveillance is for the Facility Representative to verify that the facility's configuration and operations remain consistent with the authorization basis.  As defined in DOE...

  5. Structural Basis of UV DNA-Damage Recognition by the DDB1-DDB2 Complex

    Office of Scientific and Technical Information (OSTI)

    (Journal Article) | SciTech Connect Structural Basis of UV DNA-Damage Recognition by the DDB1-DDB2 Complex Citation Details In-Document Search Title: Structural Basis of UV DNA-Damage Recognition by the DDB1-DDB2 Complex Ultraviolet (UV) light-induced pyrimidine photodimers are repaired by the nucleotide excision repair pathway. Photolesions have biophysical parameters closely resembling undamaged DNA, impeding discovery through damage surveillance proteins. The DDB1DDB2 complex serves in

  6. Los Alamos National Laboratory fission basis (Conference) | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    National Laboratory fission basis Citation Details In-Document Search Title: Los Alamos National Laboratory fission basis Authors: Keksis, August L [1] ; Chadwick, Mark B [1] + Show Author Affiliations Los Alamos National Laboratory Publication Date: 2011-05-06 OSTI Identifier: 1063939 Report Number(s): LA-UR-11-02744; LA-UR-11-2744 DOE Contract Number: AC52-06NA25396 Resource Type: Conference Resource Relation: Conference: 14th International Symposium on Reactor Dosimetry ; May 22, 2011 ;

  7. Technical Basis Spent Nuclear Fuel (SNF) Project Radiation and Contamination Trending Program

    SciTech Connect (OSTI)

    KURTZ, J.E.

    2000-05-10

    This report documents the technical basis for the Spent Nuclear Fuel (SNF) Program radiation and contamination trending program. The program consists of standardized radiation and contamination surveys of the KE Basin, radiation surveys of the KW basin, and radiation surveys of the Cold Vacuum Drying Facility (CVD) with the associated tracking. This report also discusses the remainder of radiological areas within the SNFP that do not have standardized trending programs and the basis for not having this program in those areas.

  8. Structural Basis of Selective Ubiquitination of TRF1 by SCFFbx4 (Journal

    Office of Scientific and Technical Information (OSTI)

    Article) | DOE PAGES Structural Basis of Selective Ubiquitination of TRF1 by SCFFbx4 Title: Structural Basis of Selective Ubiquitination of TRF1 by SCFFbx4 Authors: Zeng, Zhixiong ; Wang, Wei ; Yang, Yuting ; Chen, Yong ; Yang, Xiaomei ; Diehl, J. Alan ; Liu, Xuedong ; Lei, Ming Publication Date: 2010-02-01 OSTI Identifier: 1198117 Grant/Contract Number: AC02-06CH11357 Type: Published Article Journal Name: Developmental Cell Additional Journal Information: Journal Volume: 18; Journal Issue:

  9. Structural basis for the prion-like MAVS filaments in antiviral innate

    Office of Scientific and Technical Information (OSTI)

    immunity (Journal Article) | SciTech Connect Structural basis for the prion-like MAVS filaments in antiviral innate immunity Citation Details In-Document Search Title: Structural basis for the prion-like MAVS filaments in antiviral innate immunity Authors: Xu, Hui ; He, Xiaojing ; Zheng, Hui ; Huang, Lily J ; Hou, Fajian ; Yu, Zhiheng ; de la Cruz, Michael Jason ; Borkowski, Brian ; Zhang, Xuewu ; Chen, Zhijian J ; Jiang, Qiu-Xing [1] ; HHMI) [2] + Show Author Affiliations (UTSMC) (

  10. Structural Basis for Specificity and Flexibility in a Plant 4-Coumarate:CoA

    Office of Scientific and Technical Information (OSTI)

    Ligase (Journal Article) | SciTech Connect Structural Basis for Specificity and Flexibility in a Plant 4-Coumarate:CoA Ligase Citation Details In-Document Search Title: Structural Basis for Specificity and Flexibility in a Plant 4-Coumarate:CoA Ligase Authors: Li, Zhi ; Nair, Satish K. [1] + Show Author Affiliations UIUC Publication Date: 2015-12-04 OSTI Identifier: 1227510 Resource Type: Journal Article Resource Relation: Journal Name: Structure; Journal Volume: 23; Journal Issue: (11) ;

  11. Structural Basis of Selective Ubiquitination of TRF1 by SCFFbx4 (Journal

    Office of Scientific and Technical Information (OSTI)

    Article) | SciTech Connect Structural Basis of Selective Ubiquitination of TRF1 by SCFFbx4 Citation Details In-Document Search Title: Structural Basis of Selective Ubiquitination of TRF1 by SCFFbx4 Authors: Zeng, Zhixiong ; Wang, Wei ; Yang, Yuting ; Chen, Yong ; Yang, Xiaomei ; Diehl, J. Alan ; Liu, Xuedong ; Lei, Ming Publication Date: 2010-02-01 OSTI Identifier: 1198117 Grant/Contract Number: AC02-06CH11357 Type: Published Article Journal Name: Developmental Cell Additional Journal

  12. Structural Basis of UV DNA-Damage Recognition by the DDB1-DDB2 Complex

    Office of Scientific and Technical Information (OSTI)

    (Journal Article) | SciTech Connect Structural Basis of UV DNA-Damage Recognition by the DDB1-DDB2 Complex Citation Details In-Document Search Title: Structural Basis of UV DNA-Damage Recognition by the DDB1-DDB2 Complex Ultraviolet (UV) light-induced pyrimidine photodimers are repaired by the nucleotide excision repair pathway. Photolesions have biophysical parameters closely resembling undamaged DNA, impeding discovery through damage surveillance proteins. The DDB1DDB2 complex serves in

  13. Crystal Structures of mPGES-1 Inhibitor Complexes Form a Basis for the

    Office of Scientific and Technical Information (OSTI)

    Rational Design of Potent Analgesic and Anti-Inflammatory Therapeutics (Journal Article) | SciTech Connect Crystal Structures of mPGES-1 Inhibitor Complexes Form a Basis for the Rational Design of Potent Analgesic and Anti-Inflammatory Therapeutics Citation Details In-Document Search Title: Crystal Structures of mPGES-1 Inhibitor Complexes Form a Basis for the Rational Design of Potent Analgesic and Anti-Inflammatory Therapeutics Authors: Luz, John Gately ; Antonysamy, Stephen ; Kuklish,

  14. Crystal structure of a ;#8203;BRAF kinase domain monomer explains basis for

    Office of Scientific and Technical Information (OSTI)

    allosteric regulation (Journal Article) | SciTech Connect Crystal structure of a ;#8203;BRAF kinase domain monomer explains basis for allosteric regulation Citation Details In-Document Search Title: Crystal structure of a ;#8203;BRAF kinase domain monomer explains basis for allosteric regulation Authors: Thevakumaran, Neroshan ; Lavoie, Hugo ; Critton, David A. ; Tebben, Andrew ; Marinier, Anne ; Sicheri, Frank ; Therrien , Marc [1] ; Montreal) [2] ; BMS) [2] + Show Author Affiliations

  15. The Three-Dimensional Structural Basis of Type II Hyperprolinemia (Journal

    Office of Scientific and Technical Information (OSTI)

    Article) | SciTech Connect The Three-Dimensional Structural Basis of Type II Hyperprolinemia Citation Details In-Document Search Title: The Three-Dimensional Structural Basis of Type II Hyperprolinemia Type II hyperprolinemia is an autosomal recessive disorder caused by a deficiency in {Delta}{sup 1}-pyrroline-5-carboxylate dehydrogenase (P5CDH; also known as ALDH4A1), the aldehyde dehydrogenase that catalyzes the oxidation of glutamate semialdehyde to glutamate. Here, we report the first

  16. Non-homogeneous solutions of a Coulomb Schrdinger equation as basis set for scattering problems

    SciTech Connect (OSTI)

    Del Punta, J. A.; Ambrosio, M. J.; Gasaneo, G.; Zaytsev, S. A.; Ancarani, L. U.

    2014-05-15

    We introduce and study two-body Quasi Sturmian functions which are proposed as basis functions for applications in three-body scattering problems. They are solutions of a two-body non-homogeneous Schrdinger equation. We present different analytic expressions, including asymptotic behaviors, for the pure Coulomb potential with a driven term involving either Slater-type or Laguerre-type orbitals. The efficiency of Quasi Sturmian functions as basis set is numerically illustrated through a two-body scattering problem.

  17. Element composition and mineralogical characterisation of air pollution control residue from UK energy-from-waste facilities

    SciTech Connect (OSTI)

    Bogush, Anna; Stegemann, Julia A.; Wood, Ian; Roy, Amitava

    2015-02-15

    Highlights: • 66 elements, including “critical strategic elements” were determined in UK EfW APC residues. • Metal pollutants (Zn, Pb, As, Cd, Cu, Mo, Sb, Sn, Se, Ag and In) are enriched in APC residues. • Metal pollutants were widely associated with fine deposits of highly soluble CaCl{sub x}OH{sub 2−x}. • Specific metal (Zn, Pb, Cu)-bearing minerals were also detected in APC residues. - Abstract: Air pollution control (APC) residues from energy-from-waste (EfW) are alkaline (corrosive) and contain high concentrations of metals, such as zinc and lead, and soluble salts, such as chlorides and sulphates. The EPA 3050B-extractable concentrations of 66 elements, including critical elements of strategic importance for advanced electronics and energy technologies, were determined in eight APC residues from six UK EfW facilities. The concentrations of Ag (6–15 mg/kg) and In (1–13 mg/kg), as well as potential pollutants, especially Zn (0.26–0.73 wt.%), Pb (0.05–0.2 wt.%), As, Cd, Cu, Mo, Sb, Sn and Se were found to be enriched in all APC residues compared to average crustal abundances. Results from a combination of scanning electron microscopy with energy dispersive X-ray spectroscopy and also powder X-ray diffraction, thermal analysis and Fourier transform infrared spectroscopy give an exceptionally full understanding of the mineralogy of these residues, which is discussed in the context of other results in the literature. The present work has shown that the bulk of the crystalline phases present in the investigated APC residues include Ca-based phases, such as CaCl{sub x}OH{sub 2−x}, CaCO{sub 3}, Ca(OH){sub 2}, CaSO{sub 4}, and CaO, as well as soluble salts, such as NaCl and KCl. Poorly-crystalline aragonite was identified by FTIR. Sulphur appears to have complex redox speciation, presenting as both anhydrite and hannebachite in some UK EfW APC residues. Hazardous elements (Zn and Pb) were widely associated with soluble Ca- and Cl-bearing phases (e.g. CaCl{sub x}OH{sub 2−x} and sylvite), as well as unburnt organic matter and aluminosilicates. Specific metal-bearing minerals were also detected in some samples: e.g., Pb present as cerussite; Zn in gahnite, zincowoodwardite and copper nickel zinc oxide; Cu in tenorite, copper nickel zinc oxide and fedotovite. Aluminium foil pieces were present and abundantly covered by fine phases, particularly in any cracks, probably in the form of Friedel’s salt.

  18. The power of simplification: Operator interface with the AP1000{sup R} during design-basis and beyond design-basis events

    SciTech Connect (OSTI)

    Williams, M. G.; Mouser, M. R.; Simon, J. B.

    2012-07-01

    The AP1000{sup R} plant is an 1100-MWe pressurized water reactor with passive safety features and extensive plant simplifications that enhance construction, operation, maintenance, safety and cost. The passive safety features are designed to function without safety-grade support systems such as component cooling water, service water, compressed air or HVAC. The AP1000 passive safety features achieve and maintain safe shutdown in case of a design-basis accident for 72 hours without need for operator action, meeting the expectations provided in the European Utility Requirements and the Utility Requirement Document for passive plants. Limited operator actions may be required to maintain safe conditions in the spent fuel pool (SFP) via passive means. This safety approach therefore minimizes the reliance on operator action for accident mitigation, and this paper examines the operator interaction with the Human-System Interface (HSI) as the severity of an accident increases from an anticipated transient to a design basis accident and finally, to a beyond-design-basis event. The AP1000 Control Room design provides an extremely effective environment for addressing the first 72 hours of design-basis events and transients, providing ease of information dissemination and minimal reliance upon operator actions. Symptom-based procedures including Emergency Operating Procedures (EOPs), Abnormal Operating Procedures (AOPs) and Alarm Response Procedures (ARPs) are used to mitigate design basis transients and accidents. Use of the Computerized Procedure System (CPS) aids the operators during mitigation of the event. The CPS provides cues and direction to the operators as the event progresses. If the event becomes progressively worse or lasts longer than 72 hours, and depending upon the nature of failures that may have occurred, minimal operator actions may be required outside of the control room in areas that have been designed to be accessible using components that have been designed to be reliable in these conditions. The primary goal of any such actions is to maintain or refill the passive inventory available to cool the core, containment and spent fuel pool in the safety-related and seismically qualified Passive Containment Cooling Water Storage Tank (PCCWST). The seismically-qualified, ground-mounted Passive Containment Cooling Ancillary Water Storage Tank (PCCAWST) is also available for this function as appropriate. The primary effect of these actions would be to increase the coping time for the AP1000 during design basis events, as well as events such as those described above, from 72 hours without operator intervention to 7 days with minimal operator actions. These Operator actions necessary to protect the health and safety of the public are addressed in the Post-72 Hour procedures, as well as some EOPs, AOPs, ARPs and the Severe Accident Management Guidelines (SAMGs). Should the event continue to become more severe and plant conditions degrade further with indications of inadequate core cooling, the SAMGs provide guidance for strategies to address these hypothetical severe accident conditions. The AP1000 SAMG diagnoses and actions are prioritized to first utilize the AP1000 features that are expected to retain a damaged core inside the reactor vessel. Only one strategy is undertaken at any time. This strategy will be followed and its effectiveness evaluated before other strategies are undertaken. This is a key feature of both the symptom-oriented AP1000 EOPs and the AP1000 SAMGs which maximizes the probability of retaining a damaged core inside the reactor vessel and containment while minimizing the chances for confusion and human errors during implementation. The AP1000 SAMGs are simple and straight-forward and have been developed with considerable input from human factors and plant operations experts. Most importantly, and different from severe accident management strategies for other plants, the AP1000 SAMGs do not require diagnosis of the location of the core (i.e., whether reactor vessel failure has occurred). This is a fun

  19. Time-dependent density functional theory quantum transport simulation in non-orthogonal basis

    SciTech Connect (OSTI)

    Kwok, Yan Ho; Xie, Hang; Yam, Chi Yung; Chen, Guan Hua; Zheng, Xiao

    2013-12-14

    Basing on the earlier works on the hierarchical equations of motion for quantum transport, we present in this paper a first principles scheme for time-dependent quantum transport by combining time-dependent density functional theory (TDDFT) and Keldysh's non-equilibrium Green's function formalism. This scheme is beyond the wide band limit approximation and is directly applicable to the case of non-orthogonal basis without the need of basis transformation. The overlap between the basis in the lead and the device region is treated properly by including it in the self-energy and it can be shown that this approach is equivalent to a lead-device orthogonalization. This scheme has been implemented at both TDDFT and density functional tight-binding level. Simulation results are presented to demonstrate our method and comparison with wide band limit approximation is made. Finally, the sparsity of the matrices and computational complexity of this method are analyzed.

  20. Hamiltonian Light-Front Ffield Theory in a Basis Function Approach

    SciTech Connect (OSTI)

    Vary, J.P.; Honkanen, H.; Li, Jun; Maris, P.; Brodsky, S.J.; Harindranath, A.; de Teramond, G.F.; Sternberg, P.; Ng, E.G.; Yang, C.

    2009-05-15

    Hamiltonian light-front quantum field theory constitutes a framework for the non-perturbative solution of invariant masses and correlated parton amplitudes of self-bound systems. By choosing the light-front gauge and adopting a basis function representation, we obtain a large, sparse, Hamiltonian matrix for mass eigenstates of gauge theories that is solvable by adapting the ab initio no-core methods of nuclear many-body theory. Full covariance is recovered in the continuum limit, the infinite matrix limit. There is considerable freedom in the choice of the orthonormal and complete set of basis functions with convenience and convergence rates providing key considerations. Here, we use a two-dimensional harmonic oscillator basis for transverse modes that corresponds with eigensolutions of the soft-wall AdS/QCD model obtained from light-front holography. We outline our approach, present illustrative features of some non-interacting systems in a cavity and discuss the computational challenges.

  1. JLab Will Begin Testing its Public Address System on a Monthly Basis |

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Jefferson Lab Will Begin Testing its Public Address System on a Monthly Basis On April 20, Jefferson Lab Will Begin Testing its Public Address System on a Monthly Basis On Wednesday, April 20, Jefferson Lab will begin conducting a monthly test of its Public Address (PA) System - the live audible announcement feature - available through the lab's Cisco phones. Starting on April 20, these tests will occur at 5:30 p.m. on the third Wednesday of each month. The Public Address System may be used

  2. Basis for Section 3116 Determination for Salt Waste Disposal at the Savannah River Site

    Office of Environmental Management (EM)

    Fuel and High-Level Waste | Department of Energy Basis for Identification of Disposal Options for R and D for Spent Nuclear Fuel and High-Level Waste Basis for Identification of Disposal Options for R and D for Spent Nuclear Fuel and High-Level Waste The Used Fuel Disposition campaign (UFD) is selecting a set of geologic media for further study that spans a suite of behavior characteristics that impose a broad range of potential conditions on the design of the repository, the engineered

  3. Structural Basis of Wnt Signaling Inhibition by Dickkopf Binding to LRP5/6

    Office of Scientific and Technical Information (OSTI)

    (Journal Article) | SciTech Connect Basis of Wnt Signaling Inhibition by Dickkopf Binding to LRP5/6 Citation Details In-Document Search Title: Structural Basis of Wnt Signaling Inhibition by Dickkopf Binding to LRP5/6 Authors: Ahn, Victoria E. ; Chu, Matthew Ling-Hon ; Choi, Hee-Jung ; Tran, Denise ; Abo, Arie ; Weis, William I. Publication Date: 2011-11-01 OSTI Identifier: 1198118 Type: Published Article Journal Name: Developmental Cell Additional Journal Information: Journal Volume: 21;

  4. Structural basis of GSK-3 inhibition by N-terminal phosphorylation and by

    Office of Scientific and Technical Information (OSTI)

    the Wnt receptor LRP6 (Journal Article) | SciTech Connect Structural basis of GSK-3 inhibition by N-terminal phosphorylation and by the Wnt receptor LRP6 Citation Details In-Document Search Title: Structural basis of GSK-3 inhibition by N-terminal phosphorylation and by the Wnt receptor LRP6 Authors: Stamos, Jennifer L. ; Chu, Matthew Ling-Hon ; Enos, Michael D. ; Shah, Niket ; Weis, William I. [1] + Show Author Affiliations (Stanford) Publication Date: 2015-02-19 OSTI Identifier: 1168492

  5. Basis for Identification of Disposal Options for R and D for Spent Nuclear

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Fuel and High-Level Waste | Department of Energy Basis for Identification of Disposal Options for R and D for Spent Nuclear Fuel and High-Level Waste Basis for Identification of Disposal Options for R and D for Spent Nuclear Fuel and High-Level Waste The Used Fuel Disposition campaign (UFD) is selecting a set of geologic media for further study that spans a suite of behavior characteristics that impose a broad range of potential conditions on the design of the repository, the engineered

  6. Structural Basis for Microcin C7 Inactivation by the MccE Acetyltransferase

    Office of Scientific and Technical Information (OSTI)

    (Journal Article) | SciTech Connect SciTech Connect Search Results Journal Article: Structural Basis for Microcin C7 Inactivation by the MccE Acetyltransferase Citation Details In-Document Search Title: Structural Basis for Microcin C7 Inactivation by the MccE Acetyltransferase The antibiotic microcin C7 (McC) acts as a bacteriocide by inhibiting aspartyl-tRNA synthetase and stalling the protein translation machinery. McC is synthesized as a heptapeptide-nucleotide conjugate, which is

  7. Structural Basis of Selective Ubiquitination of TRF1 by SCF[superscript

    Office of Scientific and Technical Information (OSTI)

    Fbx4] (Journal Article) | SciTech Connect SciTech Connect Search Results Journal Article: Structural Basis of Selective Ubiquitination of TRF1 by SCF[superscript Fbx4] Citation Details In-Document Search Title: Structural Basis of Selective Ubiquitination of TRF1 by SCF[superscript Fbx4] TRF1 is a critical regulator of telomere length. As such, TRF1 levels are regulated by ubiquitin-dependent proteolysis via an SCF E3 ligase where Fbx4 contributes to substrate specification. Here, we report

  8. The Structural Basis for Tight Control of PP2A Methylation and Function by

    Office of Scientific and Technical Information (OSTI)

    LCMT-1 (Journal Article) | SciTech Connect The Structural Basis for Tight Control of PP2A Methylation and Function by LCMT-1 Citation Details In-Document Search Title: The Structural Basis for Tight Control of PP2A Methylation and Function by LCMT-1 Proper formation of protein phosphatase 2A (PP2A) holoenzymes is essential for the fitness of all eukaryotic cells. Carboxyl methylation of the PP2A catalytic subunit plays a critical role in regulating holoenzyme assembly; methylation is

  9. Universal basis of two-center functions. Test computations of certain diatomic molecules and ions

    SciTech Connect (OSTI)

    Kirnos, V.F.; Samsonov, B.F.; Cheglokov, E.I.

    1987-05-01

    It is shown that the basis of two-center functions is universal. The dependence of the nuclei of atoms comprising a molecule on charges and on the intranuclear spacing is separated explicitly in the integrals used in analyzing diatomic molecules. The basis integrals constructed once permitted rapid and effective execution of computations for the ground state potential curves for a number of electron systems: H/sub 2/, He/sub 2//sup 2 +/, HeH/sup +/, He/sub 2/, LiH, Li/sub 2/, HeB/sup +/, Be/sub 2/.

  10. Technical Basis Spent Nuclear Fuel (SNF) Project Radiation and Contamination Trending Program

    SciTech Connect (OSTI)

    ELGIN, J.C.

    2000-10-02

    This report documents the technical basis for the Spent Nuclear Fuel (SNF) Program radiation and contamination trending program. The program consists of standardized radiation and contamination surveys of the KE Basin, radiation surveys of the KW basin, radiation surveys of the Cold Vacuum Drying Facility (CVD), and radiation surveys of the Canister Storage Building (CSB) with the associated tracking. This report also discusses the remainder of radiological areas within the SNFP that do not have standardized trending programs and the basis for not having this program in those areas.

  11. Electron Anomalous Magnetic Moment in Basis Light-Front Quantization Approach

    SciTech Connect (OSTI)

    Zhao, Xingbo; Honkanen, Heli; Maris, Pieter; Vary, James P.; Brodsky, Stanley J.; /SLAC

    2012-02-17

    We apply the Basis Light-Front Quantization (BLFQ) approach to the Hamiltonian field theory of Quantum Electrodynamics (QED) in free space. We solve for the mass eigenstates corresponding to an electron interacting with a single photon in light-front gauge. Based on the resulting non-perturbative ground state light-front amplitude we evaluate the electron anomalous magnetic moment. The numerical results from extrapolating to the infinite basis limit reproduce the perturbative Schwinger result with relative deviation less than 1.2%. We report significant improvements over previous works including the development of analytic methods for evaluating the vertex matrix elements of QED.

  12. Analytic matrix elements for the two-electron atomic basis with logarithmic terms

    SciTech Connect (OSTI)

    Liverts, Evgeny Z.; Barnea, Nir

    2014-08-01

    The two-electron problem for the helium-like atoms in S-state is considered. The basis containing the integer powers of ln r, where r is a radial variable of the Fock expansion, is studied. In this basis, the analytic expressions for the matrix elements of the corresponding Hamiltonian are presented. These expressions include only elementary and special functions, what enables very fast and accurate computation of the matrix elements. The decisive contribution of the correct logarithmic terms to the behavior of the two-electron wave function in the vicinity of the triple-coalescence point is reaffirmed.

  13. Design-Basis Flood Estimation for Site Characterization at Nuclear Power Plants in the United States of America

    SciTech Connect (OSTI)

    Prasad, Rajiv; Hibler, Lyle F.; Coleman, Andre M.; Ward, Duane L.

    2011-11-01

    The purpose of this document is to describe approaches and methods for estimation of the design-basis flood at nuclear power plant sites. Chapter 1 defines the design-basis flood and lists the U.S. Nuclear Regulatory Commission's (NRC) regulations that require estimation of the design-basis flood. For comparison, the design-basis flood estimation methods used by other Federal agencies are also described. A brief discussion of the recommendations of the International Atomic Energy Agency for estimation of the design-basis floods in its member States is also included.

  14. Margin of Safety Definition and Examples Used in Safety Basis Documents and the USQ Process

    SciTech Connect (OSTI)

    Beaulieu, R. A.

    2013-10-03

    The Nuclear Safety Management final rule, 10 CFR 830, provides an undefined term, margin of safety (MOS). Safe harbors listed in 10 CFR 830, Table 2, such as DOE-STD-3009 use but do not define the term. This lack of definition has created the need for the definition. This paper provides a definition of MOS and documents examples of MOS as applied in a U.S. Department of Energy (DOE) approved safety basis for an existing nuclear facility. If we understand what MOS looks like regarding Technical Safety Requirements (TSR) parameters, then it helps us compare against other parameters that do not involve a MOS. This paper also documents parameters that are not MOS. These criteria could be used to determine if an MOS exists in safety basis documents. This paper helps DOE, including the National Nuclear Security Administration (NNSA) and its contractors responsible for the safety basis improve safety basis documents and the unreviewed safety question (USQ) process with respect to MOS.

  15. CRAD, Safety Basis- Oak Ridge National Laboratory High Flux Isotope Reactor

    Broader source: Energy.gov [DOE]

    A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Safety Basis in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor.

  16. CRAD, Safety Basis- Oak Ridge National Laboratory TRU ALPHA LLWT Project

    Broader source: Energy.gov [DOE]

    A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a November 2003 assessment of the Safety Basis portion of an Operational Readiness Review of the Oak Ridge National Laboratory TRU ALPHA LLWT Project.

  17. CRAD, Safety Basis- Los Alamos National Laboratory TA 55 SST Facility

    Broader source: Energy.gov [DOE]

    A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for an assessment of the Safety Basis at the Los Alamos National Laboratory TA 55 SST Facility.

  18. CRAD, Safety Basis- Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility

    Broader source: Energy.gov [DOE]

    A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for an assessment of the Safety Basis portion of an Operational Readiness Review at the Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility.

  19. CRAD, Safety Basis- Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR

    Broader source: Energy.gov [DOE]

    A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Safety Basis portion of an Operational Readiness Review of the Oak Ridge National Laboratory High Flux Isotope Reactor.

  20. CRAD, Safety Basis- Y-12 Enriched Uranium Operations Oxide Conversion Facility

    Broader source: Energy.gov [DOE]

    A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a January 2005 assessment of the Safety Basis at the Y-12 - Enriched Uranium Operations Oxide Conversion Facility.

  1. Tank Waste Remediation System (TWRS) Retrieval Authorization Basis Amendment Task Plan

    SciTech Connect (OSTI)

    HARRIS, J.P.

    1999-08-31

    This task plan is a documented agreement between Nuclear Safety and Licensing and Retrieval Engineering. The purpose of this task plan is to identify the scope of work, tasks and deliverables, responsibilities, manpower, and schedules associated with an authorization basis amendment as a result of the Waste Feed Delivery Program, Project W-211, Project W-521, and Project W-522.

  2. Tank Waste Remediation System (TWRS) Retrieval Authorization Basis Amendment Task Plan

    SciTech Connect (OSTI)

    HARRIS, J.P.

    2000-03-27

    This task plan is a documented agreement between Nuclear Safety and Licensing and Retrieval Engineering. The purpose of this task plan is to identify the scope of work, tasks and deliverables, responsibilities, manpower, and schedules associated with an authorization basis amendment as a result of the Waste Feed Delivery Program, Project W-211, Project W-521, and Project W-522.

  3. Sensitivity of the Properties of Ruthenium Blue Dimer to Method, Basis Set, and Continuum Model

    SciTech Connect (OSTI)

    Ozkanlar, Abdullah; Clark, Aurora E.

    2012-05-23

    The ruthenium blue dimer [(bpy)2RuIIIOH2]2O4+ is best known as the first well-defined molecular catalyst for water oxidation. It has been subject to numerous computational studies primarily employing density functional theory. However, those studies have been limited in the functionals, basis sets, and continuum models employed. The controversy in the calculated electronic structure and the reaction energetics of this catalyst highlights the necessity of benchmark calculations that explore the role of density functionals, basis sets, and continuum models upon the essential features of blue-dimer reactivity. In this paper, we report Kohn-Sham complete basis set (KS-CBS) limit extrapolations of the electronic structure of blue dimer using GGA (BPW91 and BP86), hybrid-GGA (B3LYP), and meta-GGA (M06-L) density functionals. The dependence of solvation free energy corrections on the different cavity types (UFF, UA0, UAHF, UAKS, Bondi, and Pauling) within polarizable and conductor-like polarizable continuum model has also been investigated. The most common basis sets of double-zeta quality are shown to yield results close to the KS-CBS limit; however, large variations are observed in the reaction energetics as a function of density functional and continuum cavity model employed.

  4. Dynamical properties of non-ideal plasma on the basis of effective potentials

    SciTech Connect (OSTI)

    Ramazanov, T. S.; Kodanova, S. K.; Moldabekov, Zh. A.; Issanova, M. K.

    2013-11-15

    In this work, stopping power has been calculated on the basis of the Coulomb logarithm using the effective potentials. Calculations of the Coulomb logarithm and stopping power for different interaction potentials and degrees of ionization are compared. The comparison with the data of other theoretical and experimental works was carried out.

  5. Development And Implementation Of A Strategic Technical Baseline Approach For Nuclear Decommissioning And Clean Up Programmes In The UK

    SciTech Connect (OSTI)

    Brownridge, M.; Ensor, B.

    2008-07-01

    The NDA mission as set out within the Energy Act 2004 and stated in the NDA strategy is clear: - 'to deliver a world class programme of safe, cost-effective, accelerated and environmentally responsible decommissioning of the UK's civil nuclear legacy in an open and transparent manner and with due regard to the socio-economic impacts on our communities. Critical to achieving the NDA main objective and overall mission is to accelerate and deliver clean-up programmes through the application of appropriate and innovative technology. The NDA remit also requires us to secure good practice by contractors and carry out and promote research into matters relating to the decommissioning and clean up of nuclear installations and sites. NDA have defined a strategic approach for the underpinning of operational and decommissioning activities where each nuclear site is required to write within the Life Time Plans (LTP) the proposed technical baseline for those activities. This enables the robustness of the activities to be assessed, the gaps and opportunities and accompanying Research and Developments (R and D) requirements to be highlighted and investment to be targeted at key technical issues. NDA also supports the development of a commercial framework where innovation is encouraged and improvements can be demonstrated against the technical baseline. In this paper we will present NDA's overall strategic approach, the benefits already realised and highlight the areas for continued development. In conclusion: The development and implementation of a strategic approach to robustly underpin the technical components of the lifetime plans for operational and decommissioning activities on NDA sites has been extremely successful. As well as showing how mature technology assumptions are and where the key gaps and risks are it has also provided a method for highlighting opportunities to improve on that baseline. The use of a common template across all NDA LTPs has enabled direct comparison of issues, identification of inter-site dependencies and scheduling hold points and a platform for sharing success and good practice. This deployment of TRLs and TBURDs across all 20 UK NDA sites is unique. The strategic approach is linked into wider areas in NDA's mission including NDA skills strategy and NDA's Direct Research Portfolio. NDA plan to ensure the strategic approach continues to evolve by the following activities: - Benchmarking the success of the TBURD and consistency of TRL evaluation to develop to a world class model; - Development of quantitative as well as qualitative methods of measuring the benefits realised; - Further support the development of technical interest groups where good practice is rewarded, shared, deployed and the benefit realised is measured; - Seek to reward innovation through the technical baselines and continue to develop the commercial framework. The progress described to date has summarised the work to develop the approach and indicated how it has been embedded and applied within three LTP cycles. NDA will further develop the TBURD through international benchmarking to create a process that is world class and clearly linked to delivery and innovation in order to reduce cost and schedule. (authors)

  6. Grid and basis adaptive polynomial chaos techniques for sensitivity and uncertainty analysis

    SciTech Connect (OSTI)

    Perk, Zoltn Gilli, Luca Lathouwers, Danny Kloosterman, Jan Leen

    2014-03-01

    The demand for accurate and computationally affordable sensitivity and uncertainty techniques is constantly on the rise and has become especially pressing in the nuclear field with the shift to Best Estimate Plus Uncertainty methodologies in the licensing of nuclear installations. Besides traditional, already well developed methods such as first order perturbation theory or Monte Carlo sampling Polynomial Chaos Expansion (PCE) has been given a growing emphasis in recent years due to its simple application and good performance. This paper presents new developments of the research done at TU Delft on such Polynomial Chaos (PC) techniques. Our work is focused on the Non-Intrusive Spectral Projection (NISP) approach and adaptive methods for building the PCE of responses of interest. Recent efforts resulted in a new adaptive sparse grid algorithm designed for estimating the PC coefficients. The algorithm is based on Gerstner's procedure for calculating multi-dimensional integrals but proves to be computationally significantly cheaper, while at the same it retains a similar accuracy as the original method. More importantly the issue of basis adaptivity has been investigated and two techniques have been implemented for constructing the sparse PCE of quantities of interest. Not using the traditional full PC basis set leads to further reduction in computational time since the high order grids necessary for accurately estimating the near zero expansion coefficients of polynomial basis vectors not needed in the PCE can be excluded from the calculation. Moreover the sparse PC representation of the response is easier to handle when used for sensitivity analysis or uncertainty propagation due to the smaller number of basis vectors. The developed grid and basis adaptive methods have been implemented in Matlab as the Fully Adaptive Non-Intrusive Spectral Projection (FANISP) algorithm and were tested on four analytical problems. These show consistent good performance both in terms of the accuracy of the resulting PC representation of quantities and the computational costs associated with constructing the sparse PCE. Basis adaptivity also seems to make the employment of PC techniques possible for problems with a higher number of input parameters (1520), alleviating a well known limitation of the traditional approach. The prospect of larger scale applicability and the simplicity of implementation makes such adaptive PC algorithms particularly appealing for the sensitivity and uncertainty analysis of complex systems and legacy codes.

  7. Correlation consistent basis sets for actinides. I. The Th and U atoms

    SciTech Connect (OSTI)

    Peterson, Kirk A.

    2015-02-21

    New correlation consistent basis sets based on both pseudopotential (PP) and all-electron Douglas-Kroll-Hess (DKH) Hamiltonians have been developed from double- to quadruple-zeta quality for the actinide atoms thorium and uranium. Sets for valence electron correlation (5f6s6p6d), cc − pV nZ − PP and cc − pV nZ − DK3, as well as outer-core correlation (valence + 5s5p5d), cc − pwCV nZ − PP and cc − pwCV nZ − DK3, are reported (n = D, T, Q). The -PP sets are constructed in conjunction with small-core, 60-electron PPs, while the -DK3 sets utilized the 3rd-order Douglas-Kroll-Hess scalar relativistic Hamiltonian. Both series of basis sets show systematic convergence towards the complete basis set limit, both at the Hartree-Fock and correlated levels of theory, making them amenable to standard basis set extrapolation techniques. To assess the utility of the new basis sets, extensive coupled cluster composite thermochemistry calculations of ThF{sub n} (n = 2 − 4), ThO{sub 2}, and UF{sub n} (n = 4 − 6) have been carried out. After accurately accounting for valence and outer-core correlation, spin-orbit coupling, and even Lamb shift effects, the final 298 K atomization enthalpies of ThF{sub 4}, ThF{sub 3}, ThF{sub 2}, and ThO{sub 2} are all within their experimental uncertainties. Bond dissociation energies of ThF{sub 4} and ThF{sub 3}, as well as UF{sub 6} and UF{sub 5}, were similarly accurate. The derived enthalpies of formation for these species also showed a very satisfactory agreement with experiment, demonstrating that the new basis sets allow for the use of accurate composite schemes just as in molecular systems composed only of lighter atoms. The differences between the PP and DK3 approaches were found to increase with the change in formal oxidation state on the actinide atom, approaching 5-6 kcal/mol for the atomization enthalpies of ThF{sub 4} and ThO{sub 2}. The DKH3 atomization energy of ThO{sub 2} was calculated to be smaller than the DKH2 value by ∼1 kcal/mol.

  8. Licensing topical report: application of probabilistic risk assessment in the selection of design basis accidents. [HTGR

    SciTech Connect (OSTI)

    Houghton, W.J.

    1980-06-01

    A probabilistic risk assessment (PRA) approach is proposed to be used to scrutinize selection of accident sequences. A technique is described in this Licensing Topical Report to identify candidates for Design Basis Accidents (DBAs) utilizing the risk assessment results. As a part of this technique, it is proposed that events with frequencies below a specified limit would not be candidates. The use of the methodology described is supplementary to the traditional, deterministic approach and may result, in some cases, in the selection of multiple failure sequences as DBAs; it may also provide a basis for not considering some traditionally postulated events as being DBAs. A process is then described for selecting a list of DBAs based on the candidates from PRA as supplementary to knowledge and judgments from past licensing practice. These DBAs would be the events considered in Chapter 15 of Safety Analysis Reports of high-temperature gas-cooled reactors (HTGRs).

  9. Comparison of CRBR design-basis events with those of foreign LMFBR plants

    SciTech Connect (OSTI)

    Agrawal, A.K.

    1983-04-01

    As part of the Construction Permit (CP) review of the Clinch River Breeder Reactor Plant (CRBR), the Brookhaven National Laboratory was asked to compare the Design Basis Accidents that are considered in CRBR Preliminary Safety Analysis Report with those of the foreign contemporary plants (PHENIX, SUPER-PHENIX, SNR-300, PFR, and MONJU). A brief introductory review of any special or unusual characteristics of these plants is given. This is followed by discussions of the design basis accidents and their acceptance criteria. In spite of some discrepancies due either to semantics or to licensing decisions, there appears to be a considerable degree of unanimity in the selection (definition) of DBAs in all of these plants.

  10. 105-K Basin material design basis feed description for spent nuclear fuel project facilities

    SciTech Connect (OSTI)

    Praga, A.N.

    1998-01-08

    Revisions 0 and 0A of this document provided estimated chemical and radionuclide inventories of spent nuclear fuel and sludge currently stored within the Hanford Site`s 105-K Basins. This Revision (Rev. 1) incorporates the following changes into Revision 0A: (1) updates the tables to reflect: improved cross section data, a decision to use accountability data as the basis for total Pu, a corrected methodology for selection of the heat generation basis fee, and a revised decay date; (2) adds section 3.3.3.1 to expand the description of the approach used to calculate the inventory values and explain why that approach yields conservative results; (3) changes the pre-irradiation braze beryllium value.

  11. Kinetically balanced Gaussian basis-set approach to relativistic Compton profiles of atoms

    SciTech Connect (OSTI)

    Jaiswal, Prerit; Shukla, Alok

    2007-02-15

    Atomic Compton profiles (CPs) are a very important property which provide us information about the momentum distribution of atomic electrons. Therefore, for CPs of heavy atoms, relativistic effects are expected to be important, warranting a relativistic treatment of the problem. In this paper, we present an efficient approach aimed at ab initio calculations of atomic CPs within a Dirac-Hartree-Fock (DHF) formalism, employing kinetically balanced Gaussian basis functions. The approach is used to compute the CPs of noble gases ranging from He to Rn, and the results have been compared to the experimental and other theoretical data, wherever possible. The influence of the quality of the basis set on the calculated CPs has also been systematically investigated.

  12. Hamiltonian Light-front Field Theory Within an AdS/QCD Basis

    SciTech Connect (OSTI)

    Vary, J.P.; Honkanen, H.; Li, Jun; Maris, P.; Brodsky, S.J.; Harindranath, A.; de Teramond, G.F.; Sternberg, P.; Ng, E.G.; Yang, C.; /LBL, Berkeley

    2009-12-16

    Non-perturbative Hamiltonian light-front quantum field theory presents opportunities and challenges that bridge particle physics and nuclear physics. Fundamental theories, such as Quantum Chromodynamics (QCD) and Quantum Electrodynamics (QED) offer the promise of great predictive power spanning phenomena on all scales from the microscopic to cosmic scales, but new tools that do not rely exclusively on perturbation theory are required to make connection from one scale to the next. We outline recent theoretical and computational progress to build these bridges and provide illustrative results for nuclear structure and quantum field theory. As our framework we choose light-front gauge and a basis function representation with two-dimensional harmonic oscillator basis for transverse modes that corresponds with eigensolutions of the soft-wall AdS/QCD model obtained from light-front holography.

  13. Polychromatic sparse image reconstruction and mass attenuation spectrum estimation via B-spline basis function expansion

    SciTech Connect (OSTI)

    Gu, Renliang E-mail: ald@iastate.edu; Dogandžić, Aleksandar E-mail: ald@iastate.edu

    2015-03-31

    We develop a sparse image reconstruction method for polychromatic computed tomography (CT) measurements under the blind scenario where the material of the inspected object and the incident energy spectrum are unknown. To obtain a parsimonious measurement model parameterization, we first rewrite the measurement equation using our mass-attenuation parameterization, which has the Laplace integral form. The unknown mass-attenuation spectrum is expanded into basis functions using a B-spline basis of order one. We develop a block coordinate-descent algorithm for constrained minimization of a penalized negative log-likelihood function, where constraints and penalty terms ensure nonnegativity of the spline coefficients and sparsity of the density map image in the wavelet domain. This algorithm alternates between a Nesterov’s proximal-gradient step for estimating the density map image and an active-set step for estimating the incident spectrum parameters. Numerical simulations demonstrate the performance of the proposed scheme.

  14. Technical Basis for Work Place Air Monitoring for the Plutonium Finishing Plan (PFP)

    SciTech Connect (OSTI)

    JONES, R.A.

    1999-10-06

    This document establishes the basis for the Plutonium Finishing Plant's (PFP) work place air monitoring program in accordance with the following requirements: Title 10, Code of Federal Regulations (CFR), Part 835 ''Occupational Radiation Protection''; Hanford Site Radiological Control Manual (HSRCM-1); HNF-PRO-33 1, Work Place Air Monitoring; WHC-SD-CP-SAR-021, Plutonium Finishing Plant Final Safety Analysis Report; and Applicable recognized national standards invoked by DOE Orders and Policies.

  15. Hydro-Kansas (HK) Research Project: Tests of a Physical Basis of

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Statistical Self-Similarity in Peak Flows in the Whitewater Basin, Kansas Hydro-Kansas (HK) Research Project: Tests of a Physical Basis of Statistical Self-Similarity in Peak Flows in the Whitewater Basin, Kansas Gupta, Vijay University of Colorado Furey, Peter Colorado Research Associates Mantila, Ricardo University of Colorado Krajewski, Witold University of Iowa Kruger, Anton The University of Iowa Clayton, Jordan US Geological Survey and University of Iowa Category: Atmospheric State and

  16. Integrated Safety Management System as the Basis for Work Planning and Control for Research and Development

    Broader source: Energy.gov [DOE]

    Slide Presentation by Rich Davies, Kami Lowry, Mike Schlender, Pacific Northwest National Laboratory (PNNL) and Ted Pietrok, Pacific Northwest Site Office (PNSO). Integrated Safety Management System as the Basis for Work Planning and Control for Research and Development. Work Planning and Control (WP&C) is essential to assuring the safety of workers and the public regardless of the scope of work Research and Development (R&D) activities are no exception.

  17. Tank waste remediation system retrieval and disposal mission authorization basis amendment task plan

    SciTech Connect (OSTI)

    Goetz, T.G.

    1998-01-08

    This task plan is a documented agreement between Nuclear Safety and Licensing and the Process Development group within the Waste Feed Delivery organization. The purpose of this task plan is to identify the scope of work, tasks and deliverables, responsibilities, manpower, and schedules associated with an authorization basis amendment as a result of the Waste Feed Waste Delivery Program, Project W-211, and Project W-TBD.

  18. Technical Basis for U. S. Department of Energy Nuclear Safety Policy, DOE Policy 420.1

    Broader source: Energy.gov [DOE]

    This document provides the technical basis for the Department of Energy (DOE) Policy (P) 420.1, Nuclear Safety Policy, dated 2-8-2011. It includes an analysis of the revised Policy to determine whether it provides the necessary and sufficient high-level expectations that will lead DOE to establish and implement appropriate requirements to assure protection of the public, workers, and the environment from the hazards of DOE’s operation of nuclear facilities.

  19. A probabilistic risk assessment of the LLNL Plutonium facility`s evaluation basis fire operational accident

    SciTech Connect (OSTI)

    Brumburgh, G.

    1994-08-31

    The Lawrence Livermore National Laboratory (LLNL) Plutonium Facility conducts numerous involving plutonium to include device fabrication, development of fabrication techniques, metallurgy research, and laser isotope separation. A Safety Analysis Report (SAR) for the building 332 Plutonium Facility was completed rational safety and acceptable risk to employees, the public, government property, and the environment. This paper outlines the PRA analysis of the Evaluation Basis Fire (EDF) operational accident. The EBF postulates the worst-case programmatic impact event for the Plutonium Facility.

  20. Demonstrating Structural Adequacy of Nuclear Power Plant Containment Structures for Beyond Design-Basis Pressure Loadings

    SciTech Connect (OSTI)

    Braverman, J.I.; Morante, R.

    2010-07-18

    ABSTRACT Demonstrating the structural integrity of U.S. nuclear power plant (NPP) containment structures, for beyond design-basis internal pressure loadings, is necessary to satisfy Nuclear Regulatory Commission (NRC) requirements and performance goals. This paper discusses methods for demonstrating the structural adequacy of the containment for beyond design-basis pressure loadings. Three distinct evaluations are addressed: (1) estimating the ultimate pressure capacity of the containment structure (10 CFR 50 and US NRC Standard Review Plan, Section 3.8) ; (2) demonstrating the structural adequacy of the containment subjected to pressure loadings associated with combustible gas generation (10 CFR 52 and 10 CFR 50); and (3) demonstrating the containment structural integrity for severe accidents (10 CFR 52 as well as SECY 90-016, SECY 93-087, and related NRC staff requirements memoranda (SRMs)). The paper describes the technical basis for specific aspects of the methods presented. It also presents examples of past issues identified in licensing activities related to these evaluations.

  1. Safety basis for the 241-AN-107 mixer pump installation and caustic addition

    SciTech Connect (OSTI)

    Van Vleet, R.J.

    1994-10-05

    This safety Basis was prepared to determine whether or not the proposed activities of installing a 76 HP jet mixer pump and the addition of approximately 50,000 gallons of 19 M (50:50 wt %) aqueous caustic are within the safety envelope as described by Tank Farms (chapter six of WHC-SD-WM-ISB-001, Rev. 0). The safety basis covers the components, structures and systems for the caustic addition and mixer pump installation. These include: installation of the mixer pump and monitoring equipment; operation of the mixer pump, process monitoring equipment and caustic addition; the pump stand, caustic addition skid, the electrical skid, the video camera system and the two densitometers. Also covered is the removal and decontamination of the mixer pump and process monitoring system. Authority for this safety basis is WHC-IP-0842 (Waste Tank Administration). Section 15.9, Rev. 2 (Unreviewed Safety Questions) of WHC-IP-0842 requires that an evaluation be performed for all physical modifications.

  2. Central Facilities Area Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables

    SciTech Connect (OSTI)

    Lisa Harvego; Brion Bennett

    2011-11-01

    Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Central Facilities Area facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facilityspecific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

  3. Materials and Security Consolidation Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables

    SciTech Connect (OSTI)

    Not Listed

    2011-09-01

    Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Materials and Security Consolidation Center facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

  4. Research and Education Campus Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables

    SciTech Connect (OSTI)

    L. Harvego; Brion Bennett

    2011-11-01

    U.S. Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory Research and Education Campus facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool to develop the radioactive waste management basis.

  5. Materials and Fuels Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables

    SciTech Connect (OSTI)

    Lisa Harvego; Brion Bennett

    2011-09-01

    Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Materials and Fuels Complex facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

  6. A Strategy for Skills to meet the demands of Nuclear Decommissioning and Clean-up in the UK

    SciTech Connect (OSTI)

    Brownridge, M.; Ensor, B.

    2008-07-01

    The NDA remit as set out within the Energy Act includes - 'to ensure the availability of skills required to deliver the overall decommissioning and nuclear clean-up mission'. The NDA approach to meeting their statutory obligation is by: - finding the best ways of re-training, re-skilling or re-deploying people in a way that encourages a more flexible workforce; - identifying and communicating the skills and workforce requirements to deliver the mission; and - developing the infrastructure and capability initiatives in line with long term needs, for example, a National Skills Academy for Nuclear, Nuclear Institute, National Graduate Scheme, and - developing locally specific provision. Firstly, NDA has set the requirement for nuclear sites to write down within the Life Time Plans (LTP), at a high level, their Site Skills Strategies; furthermore, a National Skills Working Group has been established to develop tactical cross sector solutions to support the NDA's Skills Strategy. In support of the short, medium and long term needs to meet demands of the NDA sites and the nuclear decommissioning sector, as well as being aware of the broader nuclear sector, investments have been made in infrastructure and skills programmes such as: - A National Skills Academy for Nuclear - including UK wide representation of the whole nuclear sector; - A Nuclear Institute in partnership with the University of Manchester focussing on world class research and skills in Radiation Sciences and Decommissioning Engineering; - Post Graduate sponsorship for decommissioning related projects; - A National Graduate Scheme partnership with nuclear related employers; - Vocational qualifications and Apprenticeship Schemes - Engaging 14-19 year old students to encourage the take up of Science related subjects; and - A sector wide 'Skills Passport'. In conclusion: The skills challenge has many dimensions but requires addressing due to the clear link to improved business performance and the availability of key resources in a diminishing and competitive environment. The diminishing skill base is due to reasons such as demographics and competition from other industries such as the oil industry. Getting the balance between meeting regional and national requirements will prove critical to success. The lack of clarity on the long term needs will also drive the strategy. NDA recognises that the work to date is the beginning of a long term approach and programme. We have developed a skills strategy that is consistent across all 20 sites and examples of key developments in infrastructure are in progress. Looking forward NDA will seek benchmarking opportunities and ways to make tangible links between skills and performance. (authors)

  7. Just in Time DSA-The Hanford Nuclear Safety Basis Strategy

    SciTech Connect (OSTI)

    Olinger, S. J.; Buhl, A. R.

    2002-02-26

    The U.S. Department of Energy, Richland Operations Office (RL) is responsible for 30 hazard category 2 and 3 nuclear facilities that are operated by its prime contractors, Fluor Hanford Incorporated (FHI), Bechtel Hanford, Incorporated (BHI) and Pacific Northwest National Laboratory (PNNL). The publication of Title 10, Code of Federal Regulations, Part 830, Subpart B, Safety Basis Requirements (the Rule) in January 2001 imposed the requirement that the Documented Safety Analyses (DSA) for these facilities be reviewed against the requirements of the Rule. Those DSA that do not meet the requirements must either be upgraded to satisfy the Rule, or an exemption must be obtained. RL and its prime contractors have developed a Nuclear Safety Strategy that provides a comprehensive approach for supporting RL's efforts to meet its long term objectives for hazard category 2 and 3 facilities while also meeting the requirements of the Rule. This approach will result in a reduction of the total number of safety basis documents that must be developed and maintained to support the remaining mission and closure of the Hanford Site and ensure that the documentation that must be developed will support: compliance with the Rule; a ''Just-In-Time'' approach to development of Rule-compliant safety bases supported by temporary exemptions; and consolidation of safety basis documents that support multiple facilities with a common mission (e.g. decontamination, decommissioning and demolition [DD&D], waste management, surveillance and maintenance). This strategy provides a clear path to transition the safety bases for the various Hanford facilities from support of operation and stabilization missions through DD&D to accelerate closure. This ''Just-In-Time'' Strategy can also be tailored for other DOE Sites, creating the potential for large cost savings and schedule reductions throughout the DOE complex.

  8. Technical basis for classification of low-activity waste fraction from Hanford site tanks

    SciTech Connect (OSTI)

    Petersen, C.A., Westinghouse Hanford

    1996-07-17

    The overall objective of this report is to provide a technical basis to support a U.S. Nuclear Regulatory Commission determination to classify the low-activity waste from the Hanford Site single-shell and double-shell tanks as `incidental` wastes after removal of additional radionuclides and immobilization.The proposed processing method, in addition to the previous radionuclide removal efforts, will remove the largest practical amount of total site radioactivity, attributable to high-level wastes, for disposal in a deep geologic repository. The remainder of the waste would be considered `incidental` waste and could be disposed onsite.

  9. Technical basis for classification of low-activity waste fraction from Hanford site tanks

    SciTech Connect (OSTI)

    Petersen, C.A.

    1996-09-20

    The overall objective of this report is to provide a technical basis to support a U.S. Nuclear Regulatory Commission determination to classify the low-activity waste from the Hanford Site single-shell and double-shell tanks as `incidental` wastes after removal of additional radionuclides and immobilization.The proposed processing method, in addition to the previous radionuclide removal efforts, will remove the largest practical amount of total site radioactivity, attributable to high-level waste, for disposal is a deep geologic repository. The remainder of the waste would be considered `incidental` waste and could be disposed onsite.

  10. Technical basis for cases N-629 and N-631 as an alternative for RTNDT reference temperature

    SciTech Connect (OSTI)

    Merkle, John Graham; Server, W. L.

    2007-01-01

    ASME Code Cases N-629/N-631, published in 1999, provided an important new approach to allow material specific, measured fracture toughness curves for ferritic steels in the code applications. This has enabled some of the nuclear power plants whose reactor pressure vessel materials reached a certain threshold level based on overly conservative rules to use an alternative RTNDT to justify continued operation of their plants. These code cases have been approved by the US Nuclear Regulatory Commission and these have been proposed to be codified in Appendix A and Appendix G of the ASME Boiler and Pressure Vessel Code. This paper summarizes the basis of this approach for the record.

  11. Structural Basis of Pre-existing Immunity to the 2009 H1N1 Pandemic

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Influenza Virus Structural Basis of Pre-existing Immunity to the 2009 H1N1 Pandemic Influenza Virus The emergence of the 2009 H1N1 influenza pandemic, also known as the "swine flu", marks the first human flu pandemic in 40 years and has caused significant human infection and mortality globally (1). The emergence of the 2009 H1N1 flu marks the first time that an influenza pandemic was triggered by a virus carrying the same hemagglutinin (HA) subtype as circulating seasonal strains.

  12. Current plans to characterize the design basis ground motion at the Yucca Mountain, Nevada Site

    SciTech Connect (OSTI)

    Simecka, W.B.; Grant, T.A.; Voegele, M.D.; Cline, K.M.

    1992-12-31

    A site at Yucca Mountain Nevada is currently being studied to assess its suitability as a potential host site for the nation`s first commercial high level waste repository. The DOE has proposed a new methodology for determining design-basis ground motions that uses both deterministic and probabilistic methods. The role of the deterministic approach is primary. It provides the level of detail needed by design engineers in the characterization of ground motions. The probabilistic approach provides a logical structured procedure for integrating the range of possible earthquakes that contribute to the ground motion hazard at the site. In addition, probabilistic methods will be used as needed to provide input for the assessment of long-term repository performance. This paper discusses the local tectonic environment, potential seismic sources and their associated displacements and ground motions. It also discusses the approach to assessing the design basis earthquake for the surface and underground facilities, as well as selected examples of the use of this type of information in design activities.

  13. Engineering Basis Document Review Supporting the Double Shell Tank (DST) System Specification Development

    SciTech Connect (OSTI)

    LEONARD, M.W.

    2000-03-14

    The Double-Shell Tank (DST) System is required to transition from its current storage mission to a storage and retrieval mission supporting the River Protection Project Phase 1 privatization, defined in HNF-SD-WM-MAR-008, Tank Waste Remediation System Mission Analysis Report. Requirements for the DST subsystems are being developed using the top-down systems engineering process outlined in HNF-SD-WM-SEMP-002, Tank Waste Remediation System Systems Engineering Management Plan. This top-down process considers existing designs to the extent that these designs impose unavoidable constraints on the Phase 1 mission. Existing engineering-basis documents were screened, and the unavoidable constraints were identified. The constraints identified herein will be added to the DST System specification (HNF-SD-WM-TRD-007, System Specification for the Double-Shell Tank System). While the letter revisions of the DST System specification were constructed with a less rigorous review of the existing engineering-basis documents, the Revision 0 release of the specification must incorporate the results of the review documented herein. The purpose of this document is to describe the screening process and criteria used to determine which constraints are unavoidable and to document the screening results.

  14. Development of Probabilistic Design Basis Earthquake (DBE) Parameters for Moderate and High Hazard Facilities at INEEL

    SciTech Connect (OSTI)

    S. M. Payne; V. W. Gorman; S. A. Jensen; M. E. Nitzel; M. J. Russell; R. P. Smith

    2000-03-01

    Design Basis Earthquake (DBE) horizontal and vertical response spectra are developed for moderate and high hazard facilities or Performance Categories (PC) 3 and 4, respectively, at the Idaho National Engineering and Environmental Laboratory (INEEL). The probabilistic DBE response spectra will replace the deterministic DBE response spectra currently in the U.S. Department of Energy Idaho Operations Office (DOE-ID) Architectural Engineering Standards that govern seismic design criteria for several facility areas at the INEEL. Probabilistic DBE response spectra are recommended to DOE Naval Reactors for use at the Naval Reactor Facility at INEEL. The site-specific Uniform Hazard Spectra (UHS) developed by URS Greiner Woodward Clyde Federal Services are used as the basis for developing the DBE response spectra. In 1999, the UHS for all INEEL facility areas were recomputed using more appropriate attenuation relationships for the Basin and Range province. The revised UHS have lower ground motions than those produced in the 1996 INEEL site-wide probabilistic ground motion study. The DBE response spectra were developed by incorporating smoothed broadened regions of the peak accelerations, velocities, and displacements defined by the site-specific UHS. Portions of the DBE response spectra were adjusted to ensure conservatism for the structural design process.

  15. Preliminary performance assessment for the Waste Isolation Pilot Plant, December 1992. Volume 2, Technical basis

    SciTech Connect (OSTI)

    Not Available

    1992-12-01

    Before disposing of transuranic radioactive waste in the Waste Isolation Pilot Plant (WIPP), the United States Department of Energy (DOE) must evaluate compliance with applicable long-term regulations of the United States Environmental Protection Agency (EPA). Sandia National Laboratories is conducting iterative performance assessments (PAs) of the WIPP for the DOE to provide interim guidance while preparing for a final compliance evaluation. This volume, Volume 2, contains the technical basis for the 1992 PA. Specifically, it describes the conceptual basis for consequence modeling and the PA methodology, including the selection of scenarios for analysis, the determination of scenario probabilities, and the estimation of scenario consequences using a Monte Carlo technique and a linked system of computational models. Additional information about the 1992 PA is provided in other volumes. Volume I contains an overview of WIPP PA and results of a preliminary comparison with the long-term requirements of the EPA`s Environmental Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes (40 CFR 191, Subpart B). Volume 3 contains the reference data base and values for input parameters used in consequence and probability modeling. Volume 4 contains uncertainty and sensitivity analyses related to the preliminary comparison with 40 CFR 191B. Volume 5 contains uncertainty and sensitivity analyses of gas and brine migration for undisturbed performance. Finally, guidance derived from the entire 1992 PA is presented in Volume 6.

  16. AP1000 Design Basis Event Simulation at the APEX-1000 Test Facility

    SciTech Connect (OSTI)

    Wright, Richard F.; Groome, John

    2004-07-01

    The AP1000 is a 1000 MWe advanced nuclear power plant that uses passive safety features to enhance plant safety and to provide significant and measurable improvements in plant simplification, reliability, investment protection and plant costs. The AP1000 relies heavily on the 600 MWe AP600 which received design certification in 1999. A critical part of the AP600 design certification process involved the testing of the passive safety systems. A one-fourth height, one-fourth pressure test facility, APEX-600, was constructed at the Oregon State University to study design basis events, and to provide a body of data to be used to validate the computer models used to analyze the AP600. This facility was extensively modified to reflect the design changes for AP1000 including higher power in the electrically heated rods representing the reactor core, and changes in the size of the pressurizer, core makeup tanks and automatic depressurization system. Several design basis events are being simulated at APEX-1000 including a double-ended direct vessel injection (DEDVI) line break and a 2-inch cold leg break. These tests show that the core remains covered with ample margin until gravity injection is established regardless of the initiating event. The tests also show that liquid entrainment from the upper plenum which is proportional to the reactor power does not impact the ability of the passive core cooling system to keep the core covered. (authors)

  17. A least-cost optimisation model of CO{sub 2} capture applied to major UK power plants within the EU-ETS framework

    SciTech Connect (OSTI)

    Kemp, A.G.; Kasim, A.S.

    2008-02-15

    Concerns about the cost of CO{sub 2} capture and sequestration, and the effectiveness of carbon abatement policies loom large in discussions on climate change mitigation. Several writers address the issue from various perspectives. This paper attempts to add relative realism to discussions on CO{sub 2} capture costs and the deployment of carbon capture technology in the UK by using publicly available company data on the long term capacity expansion and CO{sub 2} capture investment programmes of selected power plants in the UK. With an estimated 8 billion plan to install a generation capacity of GW and capture capability of 44 Mt CO{sub 2}/year, it is imperative to optimise this huge potential investment. A least-cost optimisation model was formulated and solved with the LP algorithm available in GAMS. The model was then applied to address a number of issues, including the choice of an optimal carbon abatement policy within the EU-ETS framework. The major findings of the study include (a) the long term total cost curve of CO{sub 2} capture has three phases rising, plateau, rising; (b) alternative capture technologies do not have permanent relative cost advantages or disadvantages; (c) Government incentives encourage carbon capture and the avoidance of emission penalty charges; and (d) the goals of EU-ETS are more effectively realised with deeper cuts in the EUA ratios than merely hiking the emission penalty, as proposed in EU-ETS Phase II.

  18. U.S. Department of Energy, Oak Ridge Operations Office Nuclear Facility Safety Basis Fundamentals Self-Study Guide [Fulfills ORO Safety Basis Competency 1, 2 (Part 1), or 7 (Part 1)

    Broader source: Energy.gov [DOE]

    "This self-study guide provides an overview of safety basis terminology, requirements, and activities that are applicable to DOE and Oak Ridge Operations Office (ORO) nuclear facilities on the Oak...

  19. Structural basis of GDP release and gating in G protein coupled Fe[superscript 2+] transport

    SciTech Connect (OSTI)

    Guilfoyle, Amy; Maher, Megan J.; Rapp, Mikaela; Clarke, Ronald; Harrop, Stephen; Jormakka, Mika

    2009-09-29

    G proteins are key molecular switches in the regulation of membrane protein function and signal transduction. The prokaryotic membrane protein FeoB is involved in G protein coupled Fe{sup 2+} transport, and is unique in that the G protein is directly tethered to the membrane domain. Here, we report the structure of the soluble domain of FeoB, including the G protein domain, and its assembly into an unexpected trimer. Comparisons between nucleotide free and liganded structures reveal the closed and open state of a central cytoplasmic pore, respectively. In addition, these data provide the first observation of a conformational switch in the nucleotide-binding G5 motif, defining the structural basis for GDP release. From these results, structural parallels are drawn to eukaryotic G protein coupled membrane processes.

  20. Composition and Technical Basis for K Basin Settler Sludge Simulant for Inspection, Retrieval, and Pump Testing

    SciTech Connect (OSTI)

    Schmidt, Andrew J.; Zacher, Alan H.

    2007-06-25

    This report provides the formulation and technical basis for a K Basin Settler Tank Sludge simulant that will be used by the K Basin Closure Project (KBC) to test and develop equipment/approaches for Settler Tank sludge level measurement and retrieval in a mock-up test system of the actual Settler Tanks. The sludge simulant may also be used to demonstrate that the TOYO high pressure positive displacement pump design (reversing valves and hollow balls) is suitable for transfer of Settler Tank sludge from the K West (KW) Basin to the Cold Vacuum Drying Facility (CVDF) (~500 ft). As requested the by the K Basins Sludge Treatment Project (STP) the simulant is comprised of non-radioactive (and non-uranium) constituents.

  1. Scientific basis for risk assessment and management of uranium mill tailings

    SciTech Connect (OSTI)

    Not Available

    1986-01-01

    A National Research Council study panel, convened by the Board on Radioactive Waste Management, has examined the scientific basis for risk assessment and management of uranium mill tailings and issued this final report containing a number of recommendations. Chapter 1 provides a brief introduction to the problem. Chapter 2 examines the processes of uranium extraction and the mechanisms by which radionuclides and toxic chemicals contained in the ore can enter the environment. Chapter 3 is devoted to a review of the evidence on health risks associated with radon and its decay products. Chapter 4 provides a consideration of conventional and possible new technical alternatives for tailings management. Chapter 5 explores a number of issues of comparative risk, provides a brief history of uranium mill tailings regulation, and concludes with a discussion of choices that must be made in mill tailing risk management. 211 refs., 30 figs., 27 tabs.

  2. Micrometer-scale fabrication of complex three dimensional lattice + basis structures in silicon

    SciTech Connect (OSTI)

    Burckel, D. Bruce; Resnick, Paul J.; Finnegan, Patrick S.; Sinclair, Michael B.; Davids, Paul S.

    2015-01-01

    A complementary metal oxide semiconductor (CMOS) compatible version of membrane projection lithography (MPL) for fabrication of micrometer-scale three-dimensional structures is presented. The approach uses all inorganic materials and standard CMOS processing equipment. In a single layer, MPL is capable of creating all 5 2D-Bravais lattices. Furthermore, standard semiconductor processing steps can be used in a layer-by-layer approach to create fully three dimensional structures with any of the 14 3D-Bravais lattices. The unit cell basis is determined by the projection of the membrane pattern, with many degrees of freedom for defining functional inclusions. Here we demonstrate several unique structural motifs, and characterize 2D arrays of unit cells with split ring resonators in a silicon matrix. The structures exhibit strong polarization dependent resonances and, for properly oriented split ring resonators (SRRs), coupling to the magnetic field of a normally incident transverse electromagnetic wave, a response unique to 3D inclusions.

  3. Breckinridge Project, initial effort. Report XI, Volume V. Critical review of the design basis. [Critical review

    SciTech Connect (OSTI)

    1982-01-01

    Report XI, Technical Audit, is a compendium of research material used during the Initial Effort in making engineering comparisons and decisions. Volumes 4 and 5 of Report XI present those studies which provide a Critical Review of the Design Basis. The Critical Review Report, prepared by Intercontinental Econergy Associates, Inc., summarizes findings from an extensive review of the data base for the H-Coal process design. Volume 4 presents this review and assessment, and includes supporting material; specifically, Design Data Tabulation (Appendix A), Process Flow Sheets (Appendix B), and References (Appendix C). Volume 5 is a continuation of the references of Appendix C. Studies of a proprietary nature are noted and referenced, but are not included in these volumes. They are included in the Limited Access versions of these reports and may be reviewed by properly cleared personnel in the offices of Ashland Synthetic Fuels, Inc.

  4. Criteria for calculating the efficiency of HEPA filters during and after design basis accidents

    SciTech Connect (OSTI)

    Bergman, W.; First, M.W.; Anderson, W.L.; Gilbert, H.; Jacox, J.W.

    1994-12-01

    We have reviewed the literature on the performance of high efficiency particulate air (HEPA) filters under normal and abnormal conditions to establish criteria for calculating the efficiency of HEPA filters in a DOE nonreactor nuclear facility during and after a Design Basis Accident (DBA). The literature review included the performance of new filters and parameters that may cause deterioration in the filter performance such as filter age, radiation, corrosive chemicals, seismic and rough handling, high temperature, moisture, particle clogging, high air flow and pressure pulses. The deterioration of the filter efficiency depends on the exposure parameters; in severe exposure conditions the filter will be structurally damaged and have a residual efficiency of 0%. Despite the many studies on HEPA filter performance under adverse conditions, there are large gaps and limitations in the data that introduce significant error in the estimates of HEPA filter efficiencies under DBA conditions. Because of this limitation, conservative values of filter efficiency were chosen when there was insufficient data.

  5. Advanced Test Reactor Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables

    SciTech Connect (OSTI)

    Lisa Harvego; Brion Bennett

    2011-11-01

    U.S. Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Advanced Test Reactor Complex facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. U.S. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool to develop the radioactive waste management basis.

  6. AUDIT REPORT Follow-up on Nuclear Safety: Safety Basis and Quality Assurance at the Los Alamos National

    Energy Savers [EERE]

    Nuclear Safety: Safety Basis and Quality Assurance at the Los Alamos National Laboratory DOE/IG-0941 July 2015 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 July 16, 2015 MEMORANDUM FOR THE SECRETARY FROM: Gregory H. Friedman Inspector General SUBJECT: INFORMATION: Audit Report: "Follow-up on Nuclear Safety: Safety Basis and Quality Assurance at the Los Alamos National Laboratory" BACKGROUND A primary

  7. Technical Basis for Certification of Seismic Design Criteria for the Waste Treatment Plant, Hanford, Washington

    SciTech Connect (OSTI)

    Brouns, T.M.; Rohay, A.C. [Pacific Northwest National Laboratory, Richland, WA (United States); Youngs, R.R. [Geomatrix Consultants, Inc., Oakland, CA (United States); Costantino, C.J. [C.J. Costantino and Associates, Valley, NY (United States); Miller, L.F. [U.S. Department of Energy, Office of River Protection, Richland, WA (United States)

    2008-07-01

    In August 2007, Secretary of Energy Samuel W. Bodman approved the final seismic and ground motion criteria for the Waste Treatment and Immobilization Plant (WTP) at the Department of Energy's (DOE) Hanford Site. Construction of the WTP began in 2002 based on seismic design criteria established in 1999 and a probabilistic seismic hazard analysis completed in 1996. The design criteria were reevaluated in 2005 to address questions from the Defense Nuclear Facilities Safety Board (DNFSB), resulting in an increase by up to 40% in the seismic design basis. DOE announced in 2006 the suspension of construction on the pretreatment and high-level waste vitrification facilities within the WTP to validate the design with more stringent seismic criteria. In 2007, the U.S. Congress mandated that the Secretary of Energy certify the final seismic and ground motion criteria prior to expenditure of funds on construction of these two facilities. With the Secretary's approval of the final seismic criteria in the summer of 2007, DOE authorized restart of construction of the pretreatment and high-level waste vitrification facilities. The technical basis for the certification of seismic design criteria resulted from a two-year Seismic Boreholes Project that planned, collected, and analyzed geological data from four new boreholes drilled to depths of approximately 1400 feet below ground surface on the WTP site. A key uncertainty identified in the 2005 analyses was the velocity contrasts between the basalt flows and sedimentary interbeds below the WTP. The absence of directly-measured seismic shear wave velocities in the sedimentary interbeds resulted in the use of a wider and more conservative range of velocities in the 2005 analyses. The Seismic Boreholes Project was designed to directly measure the velocities and velocity contrasts in the basalts and sediments below the WTP, reanalyze the ground motion response, and assess the level of conservatism in the 2005 seismic design criteria. The characterization and analysis effort included 1) downhole measurements of the velocity properties (including uncertainties) of the basalt/interbed sequences, 2) confirmation of the geometry of the contact between the various basalt and interbedded sediments through examination of retrieved core from the core-hole and data collected through geophysical logging of each borehole, and 3) prediction of ground motion response to an earthquake using newly acquired and historic data. The data and analyses reflect a significant reduction in the uncertainty in shear wave velocities below the WTP and result in a significantly lower spectral acceleration (i.e., ground motion). The updated ground motion response analyses and corresponding design response spectra reflect a 25% lower peak horizontal acceleration than reflected in the 2005 design criteria. These results provide confidence that the WTP seismic design criteria are conservative. (authors)

  8. Beyond-Design-Basis-Accidents Passive Containment-Cooling Spray System

    SciTech Connect (OSTI)

    Karameldin, Aly; Temraz, Hassan M. Elsawy; Ibrahim, Nady Attia [Atomic Energy Authority (Egypt)

    2001-10-15

    The proposed safety feature considered in this study aims to increase the safety margins of nuclear power plants by proposed water tanks located inside or outside the upper zone of the containment to be utilized for (a) residual heat removal of the reactor in case of station blackout or in case of normal reactor shutdown and (b) beyond-design-basis accidents, in which core melt and debris-concrete interaction take place, associated with accumulative containment pressure increase and partial loss of the active systems. The proposed passive containment system can be implemented by a special mechanism, which can allow the pressurization of the water in the tanks and therefore can enable an additional spray system to start in case of increasing the containment pressure over a certain value just below the design pressure. A conservative case study is that of a Westinghouse 3411-MW(thermal) power station, where the proposed passive containment cooling spray system (PCCSS) will start at a pressure of 6 bars and terminate at a pressure of 3 bars. A one-dimensional lumped model is postulated to describe the thermal and hydraulic process behavior inside the containment after a beyond-design-basis accident. The considered parameters are the spray mass flow rate, the initial droplet diameters, fuel-cooling time, and the ultimate containment pressure. The overall heat and mass balance inside the containment are carried out, during both the containment depressurization (by the spraying system) and pressurization (by the residual energies). The results show that the design of the PCCSS is viable and has a capability to maintain the containment below the design pressure passively for the required grace period of 72 h. Design curves of the proposed PCCSS indicate the effect of the spray flow rate and cooling time on the total sprayed volume during the grace period of 72 h. From these curves it can be concluded that for the grace period of 72 h, the required tank volumes are 3800 and 4700 m{sup 3}, corresponding to fuel-cooling times (time after shutdown) of two weeks and one week, respectively. This large quantity of water serves as an ultimate heat sink available for the residual heat removal in the case of station blackout. The optimal spraying droplet diameter, travel, and mass flow rate are 3 mm, 30 m, and 100 to 125 kg/s, respectively.

  9. Modular High Temperature Gas-Cooled Reactor Safety Basis and Approach

    SciTech Connect (OSTI)

    David Petti; Jim Kinsey; Dave Alberstein

    2014-01-01

    Various international efforts are underway to assess the safety of advanced nuclear reactor designs. For example, the International Atomic Energy Agency has recently held its first Consultancy Meeting on a new cooperative research program on high temperature gas-cooled reactor (HTGR) safety. Furthermore, the Generation IV International Forum Reactor Safety Working Group has recently developed a methodology, called the Integrated Safety Assessment Methodology, for use in Generation IV advanced reactor technology development, design, and design review. A risk and safety assessment white paper is under development with respect to the Very High Temperature Reactor to pilot the Integrated Safety Assessment Methodology and to demonstrate its validity and feasibility. To support such efforts, this information paper on the modular HTGR safety basis and approach has been prepared. The paper provides a summary level introduction to HTGR history, public safety objectives, inherent and passive safety features, radionuclide release barriers, functional safety approach, and risk-informed safety approach. The information in this paper is intended to further the understanding of the modular HTGR safety approach. The paper gives those involved in the assessment of advanced reactor designs an opportunity to assess an advanced design that has already received extensive review by regulatory authorities and to judge the utility of recently proposed new methods for advanced reactor safety assessment such as the Integrated Safety Assessment Methodology.

  10. Technical Basis for Radiological Emergency Plan Annex for WTD Emergency Response Plan: West Point Treatment Plant

    SciTech Connect (OSTI)

    Hickey, Eva E.; Strom, Daniel J.

    2005-08-01

    Staff of the King County Wastewater Treatment Division (WTD) have concern about the aftermath of a radiological dispersion event (RDE) leading to the introduction of significant quantities of radioactive material into the combined sanitary and storm sewer system in King County, Washington. Radioactive material could come from the use of a radiological dispersion device (RDD). RDDs include "dirty bombs" that are not nuclear detonations but are explosives designed to spread radioactive material (National Council on Radiation Protection and Measurements (NCRP) 2001). Radioactive material also could come from deliberate introduction or dispersion of radioactive material into the environment, including waterways and water supply systems. This document, Volume 3 of PNNL-15163 is the technical basis for the Annex to the West Point Treatment Plant (WPTP) Emergency Response Plan related to responding to a radiological emergency at the WPTP. The plan primarily considers response to radioactive material that has been introduced in the other combined sanitary and storm sewer system from a radiological dispersion device, but is applicable to any accidental or deliberate introduction of materials into the system.

  11. Solution to PDEs using radial basis function finite-differences (RBF-FD) on multiple GPUs

    SciTech Connect (OSTI)

    Bollig, Evan F.; Flyer, Natasha; Erlebacher, Gordon

    2012-08-30

    This paper presents parallelization strategies for the radial basis function-finite difference (RBF-FD) method. As a generalized finite differencing scheme, the RBF-FD method functions without the need for underlying meshes to structure nodes. It offers high-order accuracy approximation and scales as O(N) per time step, with N being with the total number of nodes. To our knowledge, this is the first implementation of the RBF-FD method to leverage GPU accelerators for the solution of PDEs. Additionally, this implementation is the first to span both multiple CPUs and multiple GPUs. OpenCL kernels target the GPUs and inter-processor communication and synchronization is managed by the Message Passing Interface (MPI). We verify our implementation of the RBF-FD method with two hyperbolic PDEs on the sphere, and demonstrate up to 9x speedup on a commodity GPU with unoptimized kernel implementations. On a high performance cluster, the method achieves up to 7x speedup for the maximum problem size of 27,556 nodes.

  12. APPARATUS FOR THE MASS ANALYSIS OF PLASMA ON A CONTINUOUS BASIS

    DOE Patents [OSTI]

    Neidigh, R.V.

    1963-07-01

    An apparatus for the mass analysis of plasmas on a continuous basis is described. The apparatus comprises a pair of parallel electrodes in a tubular member which serve as a velocity-selecting region for ions drawn by an accelerating potential through a tapered nose cone affixed to the tubular member. The magnetic force and electrostatic forces in the velocity-selecting region are made equal and opposite in direction to prevent the ionic species from striking either of the electrodes as they traverse the region. A pair of parallel plates is positioned within the tubular member and in alignment with the electrodes, but displaced slightly so as not to be seen by direct light coming through the entrance slit of the nose cone, and one of these plates serves as a collector plate. This collector plate is coupled to the vertical amplifier of an oscilloscope or other recorder to provide a continuous indication of the ionic coinposition of the plasma under analysis. ( DELTA EC)

  13. Technical Basis for Certification of Seismic Design Criteria for the Waste Treatment Plant, Hanford, Washington

    SciTech Connect (OSTI)

    Brouns, Thomas M.; Rohay, Alan C.; Youngs, Robert R.; Costantino, Carl J.; Miller, Lewis F.

    2008-02-28

    In August 2007, Secretary of Energy Samuel W. Bodman approved the final seismic and ground motion criteria for the Waste Treatment and Immobilization Plant (WTP) at the Department of Energys (DOE) Hanford Site. Construction of the WTP began in 2002 based on seismic design criteria established in 1999 and a probabilistic seismic hazard analysis completed in 1996. The design criteria were re-evaluated in 2005 to address questions from the Defense Nuclear Facilities Safety Board (DNFSB), resulting in an increase by up to 40% in the seismic design basis. DOE announced in 2006 the suspension of construction on the pretreatment and high-level waste vitrification facilities within the WTP to validate the design with more stringent seismic criteria. In 2007, the U.S. Congress mandated that the Secretary of Energy certify the final seismic and ground motion criteria prior to expenditure of funds on construction of these two facilities. With the Secretarys approval of the final seismic criteria this past summer, DOE authorized restart of construction of the pretreatment and high-level waste vitrification facilities.

  14. Natural micropolymorphism in human leukocyte antigens provides a basis for genetic control of antigen recognition

    SciTech Connect (OSTI)

    Archbold, Julia K.; Macdonald, Whitney A.; Gras, Stephanie; Ely, Lauren K.; Miles, John J.; Bell, Melissa J.; Brennan, Rebekah M.; Beddoe, Travis; Wilce, Matthew C.J.; Clements, Craig S.; Purcell, Anthony W.; McCluskey, James; Burrows, Scott R.; Rossjohn, Jamie

    2009-07-10

    Human leukocyte antigen (HLA) gene polymorphism plays a critical role in protective immunity, disease susceptibility, autoimmunity, and drug hypersensitivity, yet the basis of how HLA polymorphism influences T cell receptor (TCR) recognition is unclear. We examined how a natural micropolymorphism in HLA-B44, an important and large HLA allelic family, affected antigen recognition. T cell-mediated immunity to an Epstein-Barr virus determinant (EENLLDFVRF) is enhanced when HLA-B*4405 was the presenting allotype compared with HLA-B*4402 or HLA-B*4403, each of which differ by just one amino acid. The micropolymorphism in these HLA-B44 allotypes altered the mode of binding and dynamics of the bound viral epitope. The structure of the TCR-HLA-B*4405EENLLDFVRF complex revealed that peptide flexibility was a critical parameter in enabling preferential engagement with HLA-B*4405 in comparison to HLA-B*4402/03. Accordingly, major histocompatibility complex (MHC) polymorphism can alter the dynamics of the peptide-MHC landscape, resulting in fine-tuning of T cell responses between closely related allotypes.

  15. Micrometer-scale fabrication of complex three dimensional lattice + basis structures in silicon

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Burckel, D. Bruce; Resnick, Paul J.; Finnegan, Patrick S.; Sinclair, Michael B.; Davids, Paul S.

    2015-01-01

    A complementary metal oxide semiconductor (CMOS) compatible version of membrane projection lithography (MPL) for fabrication of micrometer-scale three-dimensional structures is presented. The approach uses all inorganic materials and standard CMOS processing equipment. In a single layer, MPL is capable of creating all 5 2D-Bravais lattices. Furthermore, standard semiconductor processing steps can be used in a layer-by-layer approach to create fully three dimensional structures with any of the 14 3D-Bravais lattices. The unit cell basis is determined by the projection of the membrane pattern, with many degrees of freedom for defining functional inclusions. Here we demonstrate several unique structural motifs, andmorecharacterize 2D arrays of unit cells with split ring resonators in a silicon matrix. The structures exhibit strong polarization dependent resonances and, for properly oriented split ring resonators (SRRs), coupling to the magnetic field of a normally incident transverse electromagnetic wave, a response unique to 3D inclusions.less

  16. Application of the MELCOR code to design basis PWR large dry containment analysis.

    SciTech Connect (OSTI)

    Phillips, Jesse; Notafrancesco, Allen (USNRC, Office of Nuclear Regulatory Research, Rockville, MD); Tills, Jack Lee (Jack Tills & Associates, Inc., Sandia Park, NM)

    2009-05-01

    The MELCOR computer code has been developed by Sandia National Laboratories under USNRC sponsorship to provide capability for independently auditing analyses submitted by reactor manufactures and utilities. MELCOR is a fully integrated code (encompassing the reactor coolant system and the containment building) that models the progression of postulated accidents in light water reactor power plants. To assess the adequacy of containment thermal-hydraulic modeling incorporated in the MELCOR code for application to PWR large dry containments, several selected demonstration designs were analyzed. This report documents MELCOR code demonstration calculations performed for postulated design basis accident (DBA) analysis (LOCA and MSLB) inside containment, which are compared to other code results. The key processes when analyzing the containment loads inside PWR large dry containments are (1) expansion and transport of high mass/energy releases, (2) heat and mass transfer to structural passive heat sinks, and (3) containment pressure reduction due to engineered safety features. A code-to-code benchmarking for DBA events showed that MELCOR predictions of maximum containment loads were equivalent to similar predictions using a qualified containment code known as CONTAIN. This equivalency was found to apply for both single- and multi-cell containment models.

  17. Using compliance audits as the basis for developing an effective mechanical integrity program

    SciTech Connect (OSTI)

    Kiihne, E.J.; Mannan, M. [RMT/Jones and Neuse, Inc., Austin, TX (United States)

    1996-08-01

    The OSHA Process Safety Management (PSM) rule requires all covered facilities to conduct a compliance audit every three years. In addition, all the audit findings must be resolved within a reasonable time period. The process industry as a whole is lagging behind in compliance with mechanical integrity program requirements as demonstrated by the high number of OSHA citations issued to-date on mechanical integrity-related issues. This paper analyzes the findings of several PSM compliance audits and develops recommendations for developing effective mechanical integrity programs. The six explicit requirements of mechanical integrity, i.e. covered equipment, written procedures, training, inspection and testing, equipment deficiencies, and quality assurance are analyzed in the following manner: Number of OSHA citations in mechanical integrity and the distribution of these citations between the six specific requirements. Comparison of the OSHA citations with the audit findings from PSM compliance audits conducted by the authors. Using the conclusions from the OSHA citations and PSM compliance audits as a basis for developing effective mechanical integrity programs.

  18. Application of Radial Basis Functional Link Networks to Exploration for Proterozoic Mineral Deposits in Central Iran

    SciTech Connect (OSTI)

    Behnia, Pouran [Geological Survey of Iran, Geomatics Department (Iran, Islamic Republic of)], E-mail: pouranb@yahoo.com

    2007-06-15

    The metallogeny of Central Iran is characterized mainly by the presence of several iron, apatite, and uranium deposits of Proterozoic age. Radial Basis Function Link Networks (RBFLN) were used as a data-driven method for GIS-based predictive mapping of Proterozoic mineralization in this area. To generate the input data for RBFLN, the evidential maps comprising stratigraphic, structural, geophysical, and geochemical data were used. Fifty-eight deposits and 58 'nondeposits' were used to train the network. The operations for the application of neural networks employed in this study involve both multiclass and binary representation of evidential maps. Running RBFLN on different input data showed that an increase in the number of evidential maps and classes leads to a larger classification sum of squared error (SSE). As a whole, an increase in the number of iterations resulted in the improvement of training SSE. The results of applying RBFLN showed that a successful classification depends on the existence of spatially well distributed deposits and nondeposits throughout the study area.

  19. Human-system Interfaces to Automatic Systems: Review Guidance and Technical Basis

    SciTech Connect (OSTI)

    OHara, J.M.; Higgins, J.C.

    2010-01-31

    Automation has become ubiquitous in modern complex systems and commercial nuclear power plants are no exception. Beyond the control of plant functions and systems, automation is applied to a wide range of additional functions including monitoring and detection, situation assessment, response planning, response implementation, and interface management. Automation has become a 'team player' supporting plant personnel in nearly all aspects of plant operation. In light of the increasing use and importance of automation in new and future plants, guidance is needed to enable the NRC staff to conduct safety reviews of the human factors engineering (HFE) aspects of modern automation. The objective of the research described in this report was to develop guidance for reviewing the operator's interface with automation. We first developed a characterization of the important HFE aspects of automation based on how it is implemented in current systems. The characterization included five dimensions: Level of automation, function of automation, modes of automation, flexibility of allocation, and reliability of automation. Next, we reviewed literature pertaining to the effects of these aspects of automation on human performance and the design of human-system interfaces (HSIs) for automation. Then, we used the technical basis established by the literature to develop design review guidance. The guidance is divided into the following seven topics: Automation displays, interaction and control, automation modes, automation levels, adaptive automation, error tolerance and failure management, and HSI integration. In addition, we identified insights into the automaton design process, operator training, and operations.

  20. TECHNICAL BASIS FOR EVALUATING SURFACE BARRIERS TO PROTECT GROUNDWATER FROM DEEP VADOSE ZONE CONTAMINATION

    SciTech Connect (OSTI)

    FAYER JM; FREEDMAN VL; WARD AL; CHRONISTER GB

    2010-02-24

    The U.S. DOE and its predecessors released nearly 2 trillion liters (450 billion gallons) of contaminated liquid into the vadose zone at the Hanford Site. Some of the contaminants currently reside in the deeper parts of the vadose zone where they are much less accessible to characterization, monitoring, and typical remediation activities. The DOE Richland Operations Office (DOE-RL) prepared a treatability test plan in 2008 to examine remediation options for addressing contaminants in the deep vadose zone; one of the technologies identified was surface barriers (also known as engineered barriers, covers, and caps). In the typical configuration, the contaminants are located relatively close to the surface, generally within 15 m, and thus they are close to the base of the surface barrier. The proximity of the surface barrier under these conditions yielded few concerns about the effectiveness of the barrier at depth, particularly for cases in which the contaminants were in a lined facility. At Hanford, however, some unlined sites have contaminants located well below depths of 15 m. The issue raised about these sites is the degree of effectiveness of a surface barrier in isolating contaminants in the deep vadose zone. Previous studies by Hanford Site and PNNL researchers suggest that surface barriers have the potential to provide a significant degree of isolation of deep vadose zone contaminants. The studies show that the actual degree of isolation is site-specific and depends on many factors, including recharge rates, barrier size, depth of contaminants, geohydrologic properties ofthe sediments, and the geochemical interactions between the contaminants and the sediments. After the DOE-RL treatability test plan was published, Pacific Northwest National Laboratory was contracted to review the information available to support surface barrier evaluation for the deep vadose zone, identify gaps in the information and outcomes necessary to fill the data gaps, and outline tasks to achieve those outcomes. Full understanding of contaminant behavior in the deep vadose zone is constrained by four key data gaps: limited access; limited data; limited time; and the lack of an accepted predictive capability for determining whether surface barriers can effectively isolate deep vadose zone contaminants. Activities designed to fill these data gaps need to have these outcomes: (1) common evaluation methodology that provides a clear, consistent, and defensible basis for evaluating groundwater impacts caused by placement of a surface barrier above deep vadose zone contamination; (2) deep vadose zone data that characterize the lithology, the spatial distribution of moisture and contaminants, the physical, chemical, and biological process that affect the mobility of each contaminant, and the impacts to the contaminants following placement of a surface barrier; (3) subsurface monitoring to provide subsurface characterization of initial conditions and changes that occur during and following remediation activities; and (4) field observations that span years to decades to validate the evaluation methodology. A set of six proposed tasks was identified to provide information needed to address the above outcomes. The proposed tasks are: (1) Evaluation Methodology - Develop common evaluation methodology that will provide a clear, consistent, and defensible basis for evaluating groundwater impacts caused by placement of a surface barrier above deep vadose zone contamination. (2) Case Studies - Conduct case studies to demonstrate the applicability ofthe common evaluation methodology and provide templates for subsequent use elsewhere. Three sites expected to have conditions that would yield valuable information and experience pertinent to deep vadose zone contamination were chosen to cover a range of conditions. The sites are BC Cribs and Trenches, U Plant Cribs, and the T Farm Interim Cover. (3) Subsurface Monitoring Technologies - Evaluate minimally invasive geophysical approaches for delineating subsurface plumes and monitoring their migration in the deep

  1. Structural basis for effectiveness of siderophore-conjugated monocarbams against clinically relevant strains of Pseudomonas aeruginosa

    SciTech Connect (OSTI)

    Han, Seungil; Zaniewski, Richard P.; Marr, Eric S.; Lacey, Brian M.; Tomaras, Andrew P.; Evdokimov, Artem; Miller, J. Richard; Shanmugasundaram, Veerabahu

    2012-02-08

    Pseudomonas aeruginosa is an opportunistic Gram-negative pathogen that causes nosocomial infections for which there are limited treatment options. Penicillin-binding protein PBP3, a key therapeutic target, is an essential enzyme responsible for the final steps of peptidoglycan synthesis and is covalently inactivated by {beta}-lactam antibiotics. Here we disclose the first high resolution cocrystal structures of the P. aeruginosa PBP3 with both novel and marketed {beta}-lactams. These structures reveal a conformational rearrangement of Tyr532 and Phe533 and a ligand-induced conformational change of Tyr409 and Arg489. The well-known affinity of the monobactam aztreonam for P. aeruginosa PBP3 is due to a distinct hydrophobic aromatic wall composed of Tyr503, Tyr532, and Phe533 interacting with the gem-dimethyl group. The structure of MC-1, a new siderophore-conjugated monocarbam complexed with PBP3 provides molecular insights for lead optimization. Importantly, we have identified a novel conformation that is distinct to the high-molecular-weight class B PBP subfamily, which is identifiable by common features such as a hydrophobic aromatic wall formed by Tyr503, Tyr532, and Phe533 and the structural flexibility of Tyr409 flanked by two glycine residues. This is also the first example of a siderophore-conjugated triazolone-linked monocarbam complexed with any PBP. Energetic analysis of tightly and loosely held computed hydration sites indicates protein desolvation effects contribute significantly to PBP3 binding, and analysis of hydration site energies allows rank ordering of the second-order acylation rate constants. Taken together, these structural, biochemical, and computational studies provide a molecular basis for recognition of P. aeruginosa PBP3 and open avenues for future design of inhibitors of this class of PBPs.

  2. NNSA?s Computing Strategy, Acquisition Plan, and Basis for Computing Time Allocation

    SciTech Connect (OSTI)

    Nikkel, D J

    2009-07-21

    This report is in response to the Omnibus Appropriations Act, 2009 (H.R. 1105; Public Law 111-8) in its funding of the National Nuclear Security Administration's (NNSA) Advanced Simulation and Computing (ASC) Program. This bill called for a report on ASC's plans for computing and platform acquisition strategy in support of stockpile stewardship. Computer simulation is essential to the stewardship of the nation's nuclear stockpile. Annual certification of the country's stockpile systems, Significant Finding Investigations (SFIs), and execution of Life Extension Programs (LEPs) are dependent on simulations employing the advanced ASC tools developed over the past decade plus; indeed, without these tools, certification would not be possible without a return to nuclear testing. ASC is an integrated program involving investments in computer hardware (platforms and computing centers), software environments, integrated design codes and physical models for these codes, and validation methodologies. The significant progress ASC has made in the past derives from its focus on mission and from its strategy of balancing support across the key investment areas necessary for success. All these investment areas must be sustained for ASC to adequately support current stockpile stewardship mission needs and to meet ever more difficult challenges as the weapons continue to age or undergo refurbishment. The appropriations bill called for this report to address three specific issues, which are responded to briefly here but are expanded upon in the subsequent document: (1) Identify how computing capability at each of the labs will specifically contribute to stockpile stewardship goals, and on what basis computing time will be allocated to achieve the goal of a balanced program among the labs. (2) Explain the NNSA's acquisition strategy for capacity and capability of machines at each of the labs and how it will fit within the existing budget constraints. (3) Identify the technical challenges facing the program and a strategy to resolve them.

  3. Human System Simulation in Support of Human Performance Technical Basis at NPPs

    SciTech Connect (OSTI)

    David Gertman; Katya Le Blanc; alan mecham; william phoenix; Magdy Tawfik; Jeffrey Joe

    2010-06-01

    This paper focuses on strategies and progress toward establishing the Idaho National Laboratorys (INLs) Human Systems Simulator Laboratory at the Center for Advanced Energy Studies (CAES), a consortium of Idaho State Universities. The INL is one of the National Laboratories of the US Department of Energy. One of the first planned applications for the Human Systems Simulator Laboratory is implementation of a dynamic nuclear power plant simulation (NPP) where studies of operator workload, situation awareness, performance and preference will be carried out in simulated control rooms including nuclear power plant control rooms. Simulation offers a means by which to review operational concepts, improve design practices and provide a technical basis for licensing decisions. In preparation for the next generation power plant and current government and industry efforts in support of light water reactor sustainability, human operators will be attached to a suite of physiological measurement instruments and, in combination with traditional Human Factors Measurement techniques, carry out control room tasks in simulated advanced digital and hybrid analog/digital control rooms. The current focus of the Human Systems Simulator Laboratory is building core competence in quantitative and qualitative measurements of situation awareness and workload. Of particular interest is whether introduction of digital systems including automated procedures has the potential to reduce workload and enhance safety while improving situation awareness or whether workload is merely shifted and situation awareness is modified in yet to be determined ways. Data analysis is carried out by engineers and scientists and includes measures of the physical and neurological correlates of human performance. The current approach supports a user-centered design philosophy (see ISO 13407 Human Centered Design Process for Interactive Systems, 1999) wherein the context for task performance along with the requirements of the end-user are taken into account during the design process and the validity of design is determined through testing of real end users

  4. Physics Basis for the Advanced Tokamak Fusion Power Plant ARIES-AT

    SciTech Connect (OSTI)

    S.C. Jardin; C.E. Kessel; T.K. Mau; R.L. Miller; F. Najmabadi; V.S. Chan; M.S. Chu; R. LaHaye; L.L. Lao; T.W. Petrie; P. Politzer; H.E. St. John; P. Snyder; G.M. Staebler; A.D. Turnbull; W.P. West

    2003-10-07

    The advanced tokamak is considered as the basis for a fusion power plant. The ARIES-AT design has an aspect ratio of A always equal to R/a = 4.0, an elongation and triangularity of kappa = 2.20, delta = 0.90 (evaluated at the separatrix surface), a toroidal beta of beta = 9.1% (normalized to the vacuum toroidal field at the plasma center), which corresponds to a normalized beta of bN * 100 x b/(I(sub)P(MA)/a(m)B(T)) = 5.4. These beta values are chosen to be 10% below the ideal-MHD stability limit. The bootstrap-current fraction is fBS * I(sub)BS/I(sub)P = 0.91. This leads to a design with total plasma current I(sub)P = 12.8 MA, and toroidal field of 11.1 T (at the coil edge) and 5.8 T (at the plasma center). The major and minor radii are 5.2 and 1.3 m, respectively. The effects of H-mode edge gradients and the stability of this configuration to non-ideal modes is analyzed. The current-drive system consists of ICRF/FW for on-axis current drive and a lower-hybrid system for off-axis. Tran sport projections are presented using the drift-wave based GLF23 model. The approach to power and particle exhaust using both plasma core and scrape-off-layer radiation is presented.

  5. Nuclear-Renewable Hybrid System Economic Basis for Electricity, Fuel, and Hydrogen

    SciTech Connect (OSTI)

    Charles Forsberg; Steven Aumeier

    2014-04-01

    Concerns about climate change and altering the ocean chemistry are likely to limit the use of fossil fuels. That implies a transition to a low-carbon nuclear-renewable electricity grid. Historically variable electricity demand was met using fossil plants with low capital costs, high operating costs, and substantial greenhouse gas emissions. However, the most easily scalable very-low-emissions generating options, nuclear and non-dispatchable renewables (solar and wind), are capital-intensive technologies with low operating costs that should operate at full capacities to minimize costs. No combination of fully-utilized nuclear and renewables can meet the variable electricity demand. This implies large quantities of expensive excess generating capacity much of the time. In a free market this results in near-zero electricity prices at times of high nuclear renewables output and low electricity demand with electricity revenue collapse. Capital deployment efficiency—the economic benefit derived from energy systems capital investment at a societal level—strongly favors high utilization of these capital-intensive systems, especially if low-carbon nuclear renewables are to replace fossil fuels. Hybrid energy systems are one option for better utilization of these systems that consumes excess energy at times of low prices to make some useful product.The economic basis for development of hybrid energy systems is described for a low-carbon nuclear renewable world where much of the time there are massivequantities of excess energy available from the electric sector.Examples include (1) high-temperature electrolysis to generate hydrogen for non-fossil liquid fuels, direct use as a transport fuel, metal reduction, etc. and (2) biorefineries.Nuclear energy with its concentrated constant heat output may become the enabling technology for economically-viable low-carbon electricity grids because hybrid nuclear systems may provide an economic way to produce dispatachable variable electricity with economic base-load operation of the reactor.

  6. Drain Tank Information for Developing Design Basis of the Preliminary Design

    SciTech Connect (OSTI)

    Ferrada, Juan J

    2012-02-01

    Tokamak Cooling Water System (TCWS) drain tanks (DTs) serve two functions: normal operation and safety operation. Normal DTs are used for regular maintenance operations when draining is necessary. Safety DTs are used to receive the water leaked into the Vacuum Vessel (VV) after an in-vessel loss of coolant accident (LOCA) event. The preliminary design of the DTs shall be based on the information provided by this document. The capacity of the normal DTs is estimated based on the internal volume of in-vessel components [e.g., First Wall/Blanket (FW/BLK) and Divertor (DIV)]; Neutral Beam Injector (NBI) components; and TCWS piping, heat exchangers, electric heaters, pump casing, pressurizers, and valves. Water volumes have been updated based on 2004-design information, changes adopted because of approved Project Change Requests (PCRs), and data verification by US ITER and AREVA Federal Services, the US ITER A and E Company. Two tanks will store water from normal draining operations of the FW/BLK and DIV Primary Heat Transfer Systems (PHTSs). One tank will store water from normal draining operations of the NBI PHTS. The capacity of the safety DTs is based on analysis of a design basis accident: a large leak from in-vessel components. There are two safety DTs that will receive water from a VV LOCA event and drainage from the VV, as needed. In addition, there is one sump tank for the DIV that will be used for collecting drain water from the draining and drying processes and specifically for draining the DIV system as the DIV cassette lines are at a lower elevation than the DT connection point. Information documented in this report must be refined and verified during the preliminary design of the DTs, and there are several aspects to be considered to complete the preliminary design. Input to these design considerations is discussed in this report and includes, but is not limited to, water inventory; operating procedures/maintenance; Failure Modes and Effects Analysis (FMEA); tank layout and dimensions, including design margin; classification under French Nuclear Pressure Directives, Equipements Sous Pression Nucleaires (ESPN); and adaptations for construction.

  7. Drain Tank Information for Developing Design Basis of the Preliminary Design - R00

    SciTech Connect (OSTI)

    Ferrada, Juan J [ORNL

    2011-01-01

    Tokamak Cooling Water System (TCWS) drain tanks (DTs) serve two functions: normal operation and safety operation. Normal DTs are used for regular maintenance operations when draining is necessary. Safety DTs are used to receive the water leaked into the Vacuum Vessel (VV) after an in-vessel loss of cooling accident (LOCA) event. The preliminary design of the DTs shall be based on the information provided by this document. The capacity of the normal DTs is estimated based on the internal volume of in-vessel components [e.g., First Wall/Blanket (FW/BLK) and Divertor (DIV)], Neutral Beam Injector (NBI) components, and TCWS piping, heat exchangers, electric heaters, pump casing, pressurizers, and valves. Water volumes have been updated based on 2004 design information, changes adopted because of approved Project Change Requests (PCRs), and data verification by U.S. ITER. Two tanks will store water from normal draining operations of the FW/BLK and DIV Primary Heat Transfer Systems (PHTSs). One tank will store water from normal draining operations of the NBI PHTS. The capacity of the safety DTs is based on analysis of a design-basis accident:1 a large leak from in-vessel components. There are two safety DTs that will receive water from a VV LOCA event and drainage from the VV, as needed. In addition, there is one sump tank for the DIV that will be used for collecting drain water from the draining and drying processes and specifically for draining the DIV system as the DIV cassettes lines are at a lower elevation than the DT connection point. Information documented in this report must be refined and verified during the preliminary design of the DTs, and there are several aspects to be considered to complete the preliminary design. Input to these design considerations is discussed in this report and includes, but is not limited to, water inventory; operating procedures/maintenance; Failure Modes and Effects Analysis (FMEA); tank layout anddimensions, including design margin; classification under French Nuclear Pressure Directives, Equipements Sous Pression Nucleaires (ESPN); and adaptations for construction.

  8. Office of Enterprse Assessments Review of the West Valley Demonstration Project Emergency Management Program Technical Basis and Emergency Preparedness

    Energy Savers [EERE]

    Office of Enterprise Assessments Review of the West Valley Demonstration Project Emergency Management Program Technical Basis and Emergency Preparedness December 2014 Office of Environment, Safety and Health Assessments Office of Enterprise Assessments U.S. Department of Energy Table of Contents Acronyms ..................................................................................................................................................... ii 1.0 Purpose

  9. Ingestion of phosphorus-32 at Massachusetts Institute of Technology, Cambridge, Massachusetts, identified on August 19, 1995

    SciTech Connect (OSTI)

    1995-12-01

    On Monday, October 16, 1995, the Massachussetts Institue of Technology (MIT, the licensee) notified the US Nuclear Regulatory Commission (NRC) of an incident involving ingestion of phosphorus-32 by a researcher at the MIT Center for Cancer Research. The licensee informed the NRC that a researcher had reported the incident on August 19. The licensee initially estimated the intake as 500 microcuries (19 MBq) and the dose as 4000 millirem (40 mSv) to the individual. On October 12, the licensee informed the researcher that its final intake estimate was 579 microcuries (21 MBq), just under the 600 microcuries (22 MBq) which would represent an overexposure. On October 17, the NRC established an Incident Investigation Team to investigate the case. NRC also contracted with Lawrence Livermore National Laboratory and Oak Ridge Institute for Science and Education to do independent dose assessments of the urine sample data and the whole-body data. The Team concluded that the licensee`s final intake and dose estimates were in accordance with accepted scientific references and NRC guidance. However, recognizing the uncertainties involved in the use of models to simulate human characteristics, the Team determined the intake would be better characterized as likely falling within a range of 500 to 750 microcuries (19--28 NMq). An NRC medical consultant concluded that no symptoms or acute effects should be observed from an intake of this level.

  10. SEMI-ANNUAL REPORTS FOR CE FLNG, LLC (CAMBRIDGE) - DK. NO. 12-123-LNG -

    Office of Environmental Management (EM)

    Department of Energy 4: DOE Notice of Availability of the Special Environmental Analysis SEA-04: DOE Notice of Availability of the Special Environmental Analysis Potomac Generating Station DOE has prepared a Special Environmental Analysis (SEA) for Actions Taken under U.S. Department of Energy Emergency Orders Regarding Operation of the Potomac River Generating Station in Alexandria, Virginia, and is announcing its availability. In the SEA, DOE examines environmental impacts from the

  11. Long-Baseline Neutrino Experiment (LBNE)Water Cherenkov Detector Basis of Estimate Forms and Backup Documentation LBNE Far Site Internal Review (December 6-9, 2011)

    SciTech Connect (OSTI)

    Stewart J.; Diwan, M.; Dolph, J.; Novakova, P.; Sharma, R.; Stewart, J.; Viren, B.; Russo, T.; Kaducak, M.; Mantsch, P.; Paulos, B.; Feyzi, F.; Sullivan, G.; Bionta, R.; Fowler, J.; Warner, D.; Bahowick, S.; Van Berg, R.; Kearns, E.; Hazen, E.; Sinnis, G.; Sanchez, M.

    2011-12-09

    Basis of Estimate (BOE) forms and backup documentation developed for the Water Cherenkov Detector (WCD) option for the far detector of the Long Baseline Neutrino Experiment (LBNE)

  12. Widening the envelope of UK HLW vitrification - Experimental studies with high waste loadings and new product formulations on a full scale non-active vitrification plant

    SciTech Connect (OSTI)

    Short, R.; Gribble, N. [Nexia Solutions, Sellafield, Cumbria, CA20 1PG (United Kingdom); Riley, A. [Sellafield Ltd, Sellafield, Seascale, Cumbria, CA20 1PG, UK (United Kingdom)

    2008-07-01

    The Vitrification Test Rig is a full scale waste vitrification plant that processes non-radioactive liquid HLW simulants based on the active waste streams produced by the reprocessing plants in the UK. Previous work on the rig has primarily concerned increasing the operational envelopes for the active waste vitrification plants at Sellafield to accommodate higher throughputs of Blended waste streams, higher waste oxide incorporation rates in the vitrified products, and the incorporation of legacy waste streams from early reactor commissioning and reprocessing operations at Sellafield. Recent operations have focussed on four main areas; dilute liquid feeds, very high Magnox waste stream incorporation levels, alternative base glass formulations and providing an operational envelope for 28 %w/w Magnox waste vitrification. This paper details the work performed and the major findings of that work. In summary: The VTR has been successfully used to determine operational envelopes and product quality for several HLW feed variations that will allow WVP to increase overall plant throughput via increased waste loading in canisters, increased HLW feed rates or a combination of both. The VTR has also demonstrated the ability to go to waste incorporations, feed rates and glass compositions that are currently beyond WVP specified limits, but that are feasible for future vitrification regimes. In addition, the VTR has trialled dilute feeds similar to those that are likely to be received by WVP in the future and the data obtained from these experiments will allow WVP to prepare adequately for the high throughput challenge of such feeds. Furthermore, new equipment has been trialled on the VTR in water feed mode to determine its suitability and operational limitations for WVP. Future operations will, in the short term, be concerned with increasing the throughput of WVP and are likely to focus on HLW decommissioning operations waste streams in the longer term. (authors)

  13. Evaluation of the Scaling of the APEX-1000 Test Facility to AP1000 for Design Basis Events

    SciTech Connect (OSTI)

    Wright, Richard F.; Gagnon, Andre; Skinner, Jesse; Groome, John

    2004-07-01

    The AP1000 is a 1000 MWe advanced nuclear power plant that uses passive safety features to enhance plant safety and to provide significant and measurable improvements in plant simplification, reliability, investment protection and plant costs. The AP1000 relies heavily on the 600 MWe AP600 which received design certification in 1999. A critical part of the AP600 design certification process involved the testing of the passive safety systems. A one-fourth height, one-fourth pressure test facility, APEX-600, was constructed at the Oregon State University to study design basis events, and to provide a body of data to be used to validate the computer models used to analyze the AP600. This facility was extensively modified to reflect the design changes for AP1000 including higher power in the electrically heated rods representing the reactor core, and changes in the size of the pressurizer, core makeup tanks and automatic depressurization system. Several design basis events have been simulated at APEX-1000 including double-ended direct vessel injection (DEDVI) line break, 2-inch cold leg break, and inadvertent actuation of the automatic depressurization system. These events were analyzed as part of the AP1000 safety analysis using the NOTRUMP computer code. Applying the scaling factors that were used to size the APEX-1000 facility, the test results can be compared to the NOTRUMP plant simulations. These comparisons indicate the similarity between the design basis events in AP1000 and APEX-1000, the adequacy of the scaling of APEX-1000, and the applicability of the NOTRUMP code. (authors)

  14. Basis for Section 3116 Determination for the Idaho Nuclear Technology and Engineering Center Tank Farm Facility at the Idaho National Laboratory

    Office of Environmental Management (EM)

    NE-ID-11226 Revision 0 Basis for Section 3116 Determination for the Idaho Nuclear Technology and Engineering Center Tank Farm Facility November 2006 DOE/NE-ID-11226 Revision 0 Basis for Section 3116 Determination for the Idaho Nuclear Technology and Engineering Center Tank Farm Facility November 2006 ii CONTENTS ACRONYMS.............................................................................................................................................. vii 1. INTRODUCTION AND

  15. Basis to demonstrate compliance with the National Emission Standards for Hazardous Air Pollutants for the Stand-off Experiments Range

    SciTech Connect (OSTI)

    Michael Sandvig

    2011-01-01

    The purpose of this report is to provide the basis and the documentation to demonstrate general compliance with the National Emission Standard for Hazardous Air Pollutants (NESHAPS) 40 CFR 61 Subpart H, National Emission Standards for Emissions of Radionuclides Other Than Radon from Department of Energy Facilities, (the Standard) for outdoor linear accelerator operations at the Idaho National Laboratory (INL) Stand-off Experiments Range (SOX). The intent of this report is to inform and gain acceptance of this methodology from the governmental bodies regulating the INL.

  16. Genomic and experimental evidence for multiple metabolic functions in the RidA/YjgF/YER057c/UK114 (Rid) protein family

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Niehaus, Thomas D.; Gerdes, Svetlana; Hodge-Hanson, Kelsey; Zhukov, Aleksey; Cooper, Arthur J.L.; ElBadawi-Sidhu, Mona; Fiehn, Oliver; Downs, Diana M.; Hanson, Andrew D.

    2015-05-15

    It is now recognized that enzymatic or chemical side-reactions can convert normal metabolites to useless or toxic ones and that a suite of enzymes exists to mitigate such metabolite damage. Examples are the reactive imine/enamine intermediates produced by threonine dehydratase, which damage the pyridoxal 5'-phosphate cofactor of various enzymes causing inactivation. This damage is pre-empted by RidA proteins, which hydrolyze the imines before they do harm. RidA proteins belong to the YjgF/YER057c/UK114 family (here renamed the Rid family). Most other members of this diverse and ubiquitous family lack defined functions. Phylogenetic analysis divided the Rid family into a widely distributed,more » apparently archetypal RidA subfamily and seven other subfamilies (Rid1 to Rid7) that are largely confined to bacteria and often co-occur in the same organism with RidA and each other. The Rid1 to Rid3 subfamilies, but not the Rid4 to Rid7 subfamilies, have a conserved arginine residue that, in RidA proteins, is essential for imine-hydrolyzing activity. Analysis of the chromosomal context of bacterial RidA genes revealed clustering with genes for threonine dehydratase and other pyridoxal 5'-phosphate-dependent enzymes, which fits with the known RidA imine hydrolase activity. Clustering was also evident between Rid family genes and genes specifying FAD-dependent amine oxidases or enzymes of carbamoyl phosphate metabolism. Biochemical assays showed that Salmonella enterica RidA and Rid2, but not Rid7, can hydrolyze imines generated by amino acid oxidase. Genetic tests indicated that carbamoyl phosphate overproduction is toxic to S. enterica cells lacking RidA, and metabolomic profiling of Rid knockout strains showed ten-fold accumulation of the carbamoyl phosphate-related metabolite dihydroorotate. Like the archetypal RidA subfamily, the Rid2, and probably the Rid1 and Rid3 subfamilies, have imine-hydrolyzing activity and can pre-empt damage from imines formed by amine oxidases as well as by pyridoxal 5'-phosphate enzymes. The RidA subfamily has an additional damage pre-emption role in carbamoyl phosphate metabolism that has yet to be biochemically defined. As a result, the Rid4 to Rid7 subfamilies appear not to hydrolyze imines and thus remain mysterious.« less

  17. Geochemistry Technical Basis Document

    SciTech Connect (OSTI)

    Benedict, Jr, F Christopher; Rose, Timothy P; Thomas, James M; Waddell, Richard; Jacobson, Roger

    2004-03-18

    This document presents a methodology whereby geochemical data can more effectively contribute to the development , calibration, and verification of groundwater flow and slute transport models for the Underground Test Area (UGTA) Project.

  18. design basis threat

    National Nuclear Security Administration (NNSA)

    training courses, and additional full-time instructors.

    • The shift to an "Elite Forces," or Tactical Response Force (TRF) model, to transform NNSA's protective forces...

    • Development, Testing and Validation of a Waste Assay System for the Measurement and Characterisation of Active Spent Fuel Element Debris From UK Magnox Reactors - 12533

      SciTech Connect (OSTI)

      Mason, John A.; Burke, Kevin J.; Looman, Marc R.; Towner, Antony C.N.; Phillips, Martin E.

      2012-07-01

      This paper describes the development, testing and validation of a waste measurement instrument for characterising active remote handled radioactive waste arising from the operation of Magnox reactors in the United Kingdom. Following operation in UK Magnox gas cooled reactors and a subsequent period of cooling, parts of the magnesium-aluminium alloy cladding were removed from spent fuel and the uranium fuel rods with the remaining cladding were removed to Sellafield for treatment. The resultant Magnox based spent fuel element debris (FED), which constitutes active intermediate level waste (ILW) has been stored in concrete vaults at the reactor sites. As part of the decommissioning of the FED vaults the FED must be removed, measured and characterised and placed in intermediate storage containers. The present system was developed for use at the Trawsfynydd nuclear power station (NPS), which is in the decommissioning phase, but the approach is potentially applicable to FED characterisation at all of the Magnox reactors. The measurement system consists of a heavily shielded and collimated high purity Germanium (HPGe) detector with electromechanical cooling and a high count-rate preamplifier and digital multichannel pulse height analyser. The HPGe based detector system is controlled by a software code, which stores the measurement result and allows a comprehensive analysis of the measured FED data. Fuel element debris is removed from the vault and placed on a tray to a uniform depth of typically 10 cm for measurement. The tray is positioned approximately 1.2 meters above the detector which views the FED through a tungsten collimator with an inverted pyramid shape. At other Magnox sites the positions may be reversed with the shielded and collimated HPGe detector located above the tray on which the FED is measured. A comprehensive Monte Carlo modelling and analysis of the measurement process has been performed in order to optimise the measurement geometry and eliminate interferences from radioactive sources and FED in the immediate vicinity of the measurement position. The detector system has been calibrated and high activity radioactive sources of Cs-137, Co-60 and Na-22 have been used to validate the measurement process. The data acquisition and analysis software code has been tested and validated in keeping with the software quality assurance requirements of both ISO:9001-2008 - TICK-IT in the UK and NQA-1. The measurement and analysis system has been comprehensively tested with high activity sources, is flexible and may be applicable to a wide range of remote handled radioactive waste measurement applications. It is due to be installed at Trawsfynydd NPS later this year. This paper describes the Waste Tray Assay System (WTAS) that has been developed for the measurement of Magnox FED waste. The WTAS has been tested with a range of radioactive sources and its operation has been simulated with benchmarked MCNP Monte Carlo calculations. The measurement software has been validated as has the operation of the system for a range of strong radioactive sources. A system based on the design is due for installation and operation in 2012. The system has application to the measurement of Magnox Fuel Element Debris (FED) waste at other Magnox reactor sites. The major design objective of the WTAS that has been achieved is the ability of the assay system to determine the content of Cs-137, and in turn to enable the fissile burden to be assessed using a radionuclide fingerprint, in the presence of higher and highly variable quantities of Co-60, typically from nimonic springs. The approach can be used in other Magnox FED waste configurations where the detector is located above the FED waste sorting tray and where the collimation is fixed below the detector and at a distance above the tray. In this case, which has also been investigated, there are different shielding problems and mechanical support issues. The extensive use of MCNP Monte Carlo modelling to simulate the geometry of the sorting cell and the distribution of radioactive sources has helped to ensure that all of the detector shielding requirements are addressed and suitable Cs-137 and Co-60 discrimination can be achieved. The WTAS in its present form or in other configurations has relevance to the measurement of other active ILW and highly active RH waste. Examples include high activity RH LLW and RH TRU (Transuranic) waste as defined in the United States arising from both commercial nuclear and Department of Energy (DOE) operations. The analysis is able to analyse a range of radionuclides beyong those expected in the Magnox FED cases. (authors)

    • Development of Site-Specific Soil Design Basis Earthquake (DBE) Parameters for the Integrated Waste Treatment Unit (IWTU)

      SciTech Connect (OSTI)

      Payne, Suzette

      2008-08-01

      Horizontal and vertical PC 3 (2,500 yr) Soil Design Basis Earthquake (DBE) 5% damped spectra, corresponding time histories, and strain-compatible soil properties were developed for the Integrated Waste Treatment Unit (IWTU). The IWTU is located at the Idaho Nuclear Technology and Engineering Center (INTEC) at the Idaho National Laboratory (INL). Mean and 84th percentile horizontal DBE spectra derived from site-specific site response analyses were evaluated for the IWTU. The horizontal and vertical PC 3 (2,500 yr) Soil DBE 5% damped spectra at the 84th percentile were selected for Soil Structure Interaction (SSI) analyses at IWTU. The site response analyses were performed consistent with applicable Department of Energy (DOE) Standards, recommended guidance of the Nuclear Regulatory Commission (NRC), American Society of Civil Engineers (ASCE) Standards, and recommendations of the Blue Ribbon Panel (BRP) and Defense Nuclear Facilities Safety Board (DNFSB).

  1. After Action Report:Idaho National Laboratory (INL) 2014 Multiple Facility Beyond Design Basis (BDBE) Evaluated Drill October 21, 2014

    SciTech Connect (OSTI)

    V. Scott Barnes

    2014-12-01

    On October 21, 2014, Idaho National Laboratory (INL), in coordination with local jurisdictions, and Department of Energy (DOE) Idaho Operations Office (DOE ID) conducted an evaluated drill to demonstrate the ability to implement the requirements of DOE O 151.1C, “Comprehensive Emergency Management System” when responding to a beyond design basis event (BDBE) scenario as outlined in the Office of Health, Safety, and Security Operating Experience Level 1 letter (OE-1: 2013-01). The INL contractor, Battelle Energy Alliance, LLC (BEA), in coordination with CH2M-WG Idaho, LLC (CWI), and Idaho Treatment Group LLC (ITG), successfully demonstrated appropriate response measures to mitigate a BDBE event that would impact multiple facilities across the INL while protecting the health and safety of personnel, the environment, and property. Offsite response organizations participated to demonstrate appropriate response measures.

  2. Light Water Reactor Sustainability Program Technical Basis Guide Describing How to Perform Safety Margin Configuration Risk Management

    SciTech Connect (OSTI)

    Curtis Smith; James Knudsen; Bentley Harwood

    2013-08-01

    The INL has carried out a demonstration of the RISMC approach for the purpose of configuration risk management. We have shown how improved accuracy and realism can be achieved by simulating changes in risk as a function of different configurations in order to determine safety margins as the plant is modified. We described the various technical issues that play a role in these configuration-based calculations with the intent that future applications can take advantage of the analysis benefits while avoiding some of the technical pitfalls that are found for these types of calculations. Specific recommendations have been provided on a variety of topics aimed at improving the safety margin analysis and strengthening the technical basis behind the analysis process.

  3. Representation of a complex Green function on a real basis: Generalization to a three-body system

    SciTech Connect (OSTI)

    Li Tieniu; Shakeshaft, Robin; Piraux, Bernard

    2003-05-01

    We develop further a new method for employing a set of real basis functions to represent the Green function at energies in the continuum, without regard for the asymptotic boundary conditions. The method is based on the analyticity of the Green function with respect to its underlying time scale. The diagonalization of large matrices is unnecessary. Although a large complex symmetric linear system of equations must be solved, this can be done with high stability and efficiency by using a generalization of the Cholesky decomposition of real positive definite symmetric matrices. We present results of test applications to {sup 1}S-wave electron scattering from a hydrogen atom and photodetachment of the negative hydrogen ion. The extension from two- to three-body collisions entails the use of projection operators to distinguish different groups of asymptotic channels.

  4. 105-K Basin Material Design Basis Feed Description for Spent Nuclear Fuel (SNF) Project Facilities VOL 1 Fuel

    SciTech Connect (OSTI)

    PACKER, M.J.

    1999-11-04

    Metallic uranium Spent Nuclear Fuel (SNF) is currently stored within two water filled pools, 105-KE Basin (KE Basin) and 105-KW Basin (KW Basin), at the United States Department of Energy (U.S. DOE) Hanford Site, in southeastern Washington State. The Spent Nuclear Fuel Project (SNF Project) is responsible to DOE for operation of these fuel storage pools and for the 2100 metric tons of SNF materials that they contain. The SNF Project mission includes safe removal and transportation of all SNF from these storage basins to a new storage facility in the 200 East Area. To accomplish this mission, the SNF Project modifies the existing KE Basin and KW Basin facilities and constructs two new facilities: the 100 K Area Cold Vacuum Drying Facility (CVDF), which drains and dries the SNF; and the 200 East Area Canister Storage Building (CSB), which stores the SNF. The purpose of this document is to describe the design basis feed compositions for materials stored or processed by SNF Project facilities and activities. This document is not intended to replace the Hanford Spent Fuel Inventory Baseline (WHC 1994b), but only to supplement it by providing more detail on the chemical and radiological inventories in the fuel (this volume) and sludge. A variety of feed definitions is required to support evaluation of specific facility and process considerations during the development of these new facilities. Six separate feed types have been identified for development of new storage or processing facilities. The approach for using each feed during design evaluations is to calculate the proposed facility flowsheet assuming each feed. The process flowsheet would then provide a basis for material compositions and quantities which are used in follow-on calculations.

  5. Basis for Section 3116 Determination for the Idaho Nuclear Technology and Engineering Center Tank Farm Facility at the Idaho National Laboratory

    Broader source: Energy.gov [DOE]

    This 3116 Basis Document addresses the disposal of stabilized residuals in the TFF, and the TFF tank system, and disposal of the tanks, vaults, and associated piping and ancillary equipment at...

  6. Comment on “Rethinking first-principles electron transport theories with projection operators: The problems caused by partitioning the basis set” [J. Chem. Phys. 139, 114104 (2013)

    SciTech Connect (OSTI)

    Brandbyge, Mads

    2014-05-07

    In a recent paper Reuter and Harrison [J. Chem. Phys. 139, 114104 (2013)] question the widely used mean-field electron transport theories, which employ nonorthogonal localized basis sets. They claim these can violate an “implicit decoupling assumption,” leading to wrong results for the current, different from what would be obtained by using an orthogonal basis, and dividing surfaces defined in real-space. We argue that this assumption is not required to be fulfilled to get exact results. We show how the current/transmission calculated by the standard Greens function method is independent of whether or not the chosen basis set is nonorthogonal, and that the current for a given basis set is consistent with divisions in real space. The ambiguity known from charge population analysis for nonorthogonal bases does not carry over to calculations of charge flux.

  7. Establishing a Cost Basis for Converting the High Flux Isotope Reactor from High Enriched to Low Enriched Uranium Fuel

    SciTech Connect (OSTI)

    Primm, Trent; Guida, Tracey

    2010-02-01

    Under the auspices of the Global Threat Reduction Initiative Reduced Enrichment for Research and Test Reactors Program, the National Nuclear Security Administration /Department of Energy (NNSA/DOE) has, as a goal, to convert research reactors worldwide from weapons grade to non-weapons grade uranium. The High Flux Isotope Reactor (HFIR) at Oak Ridge National Lab (ORNL) is one of the candidates for conversion of fuel from high enriched uranium (HEU) to low enriched uranium (LEU). A well documented business model, including tasks, costs, and schedules was developed to plan the conversion of HFIR. Using Microsoft Project, a detailed outline of the conversion program was established and consists of LEU fuel design activities, a fresh fuel shipping cask, improvements to the HFIR reactor building, and spent fuel operations. Current-value costs total $76 million dollars, include over 100 subtasks, and will take over 10 years to complete. The model and schedule follows the path of the fuel from receipt from fuel fabricator to delivery to spent fuel storage and illustrates the duration, start, and completion dates of each subtask to be completed. Assumptions that form the basis of the cost estimate have significant impact on cost and schedule.

  8. Structural Basis for a Switch in Receptor Binding Specificity of Two H5N1 Hemagglutinin Mutants

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Zhu, Xueyong; Viswanathan, Karthik; Raman, Rahul; Yu, Wenli; Sasisekharan, Ram; Wilson, Ian A.

    2015-11-01

    Avian H5N1 influenza viruses continue to spread in wild birds and domestic poultry with sporadic infection in humans. Receptor binding specificity changes are a prerequisite for H5N1 viruses and other zoonotic viruses to be transmitted among humans. Previous reported hemagglutinin (HA) mutants from ferret-transmissible H5N1 viruses of A/Viet Nam/1203/04 and A/Indonesia/5/05 showed slightly increased, but still very weak, binding to human receptors. From mutagenesis and glycan array studies, we previously identified two H5N1 HA mutants that could more effectively switch receptor specificity to human-like α2-6 linked sialosides with avidity comparable to wild-type H5 HA binding to avian-like α2-3 linked sialosides.more »Here, crystal structures of these two H5 HA mutants free and in complex with human and avian glycan receptor analogues reveal the structural basis for their preferential binding to human receptors. These findings suggest continuous surveillance should be maintained to monitor and assess human-to-human transmission potential of H5N1 viruses.« less

  9. Criteria for calculating the efficiency of deep-pleated HEPA filters with aluminum separators during and after design basis accidents

    SciTech Connect (OSTI)

    Bergman, W.; First, M.W.; Anderson, W.L.; Gilbert, H.; Jacox, J.W.

    1995-02-01

    The authors have reviewed the literature on the performance of high efficiency particulate air (HEPA) filters under normal and abnormal conditions to establish criteria for calculating the efficiency of HEPA filters in a DOE nonreactor nuclear facility during and after a Design Basis Accident (DBA). This study is only applicable to the standard deep-pleated HEPA filter with aluminum separators as specified in ASME N509. The literature review included the performance of new filters and parameters that may cause deterioration in the filter performance such as filter age, radiation, corrosive chemicals, seismic and rough handling, high temperature, moisture, particle clogging, high air flow and pressure pulses. The deterioration of the filter efficiency depends on the exposure parameters; in severe exposure conditions the filter will be structurally damaged and have a residual efficiency of 0%. Despite the many studies on HEPA filter performance under adverse conditions, there are large gaps and limitations in the data that introduce significant error in the estimates of HEPA filter efficiencies under DBA conditions. Because of this limitation, conservative values of filter efficiency were chosen when there was insufficient data.

  10. Excitation of helium Rydberg states and doubly excited resonances in strong extreme ultraviolet fields: Full-dimensional quantum dynamics using exponentially tempered Gaussian basis sets

    SciTech Connect (OSTI)

    Kaprlov-?nsk, Petra Ruth; mydke, Jan; Department of Radiation and Chemical Physics, Institute of Physics, Academy of Sciences of the Czech Republic, Na Slovance 2, 182 21 Prague 8 ; Civi, Svatopluk

    2013-09-14

    Recently optimized exponentially tempered Gaussian basis sets [P. R. Kapralova-Zdanska and J. Smydke, J. Chem. Phys. 138, 024105 (2013)] are employed in quantitative simulations of helium absorption cross-sections and two-photon excitation yields of doubly excited resonances. Linearly polarized half-infinite and Gaussian laser pulses at wavelengths 3858 nm and large intensities up to 100 TW/cm{sup 2} are considered. The emphasis is laid on convergence of the results with respect to the quality of the Gaussian basis sets (typically limited by a number of partial waves, density, and spatial extent of the basis functions) as well as to the quality of the basis set of field-free states (typically limited by the maximum rotational quantum number and maximum excitation of the lower electron). Particular attention is paid to stability of the results with respect to varying complex scaling parameter. Moreover, the study of the dynamics is preceded by a thorough check of helium energies and oscillator strengths as they are obtained with the exponentially tempered Gaussian basis sets, being also compared with yet unpublished emission wavelengths measured in electric discharge experiments.

  11. Possible Methods to Estimate Core Location in a Beyond-Design-Basis Accident at a GE BWR with a Mark I Containment Stucture

    SciTech Connect (OSTI)

    Walston, S; Rowland, M; Campbell, K

    2011-07-27

    It is difficult to track to the location of a melted core in a GE BWR with Mark I containment during a beyond-design-basis accident. The Cooper Nuclear Station provided a baseline of normal material distributions and shielding configurations for the GE BWR with Mark I containment. Starting with source terms for a design-basis accident, methods and remote observation points were investigated to allow tracking of a melted core during a beyond-design-basis accident. The design of the GE BWR with Mark-I containment highlights an amazing poverty of expectations regarding a common mode failure of all reactor core cooling systems resulting in a beyond-design-basis accident from the simple loss of electric power. This design is shown in Figure 1. The station blackout accident scenario has been consistently identified as the leading contributor to calculated probabilities for core damage. While NRC-approved models and calculations provide guidance for indirect methods to assess core damage during a beyond-design-basis loss-of-coolant accident (LOCA), there appears to be no established method to track the location of the core directly should the LOCA include a degree of fuel melt. We came to the conclusion that - starting with detailed calculations which estimate the release and movement of gaseous and soluble fission products from the fuel - selected dose readings in specific rooms of the reactor building should allow the location of the core to be verified.

  12. Analysis of main steam isolation valve leakage in design basis accidents using MELCOR 1.8.6 and RADTRAD.

    SciTech Connect (OSTI)

    Salay, Michael; Kalinich, Donald A.; Gauntt, Randall O.; Radel, Tracy E.

    2008-10-01

    Analyses were performed using MELCOR and RADTRAD to investigate main steam isolation valve (MSIV) leakage behavior under design basis accident (DBA) loss-of-coolant (LOCA) conditions that are presumed to have led to a significant core melt accident. Dose to the control room, site boundary and LPZ are examined using both approaches described in current regulatory guidelines as well as analyses based on best estimate source term and system response. At issue is the current practice of using containment airborne aerosol concentrations as a surrogate for the in-vessel aerosol concentration that exists in the near vicinity of the MSIVs. This study finds current practice using the AST-based containment aerosol concentrations for assessing MSIV leakage is non-conservative and conceptually in error. A methodology is proposed that scales the containment aerosol concentration to the expected vessel concentration in order to preserve the simplified use of the AST in assessing containment performance under assumed DBA conditions. This correction is required during the first two hours of the accident while the gap and early in-vessel source terms are present. It is general practice to assume that at {approx}2hrs, recovery actions to reflood the core will have been successful and that further core damage can be avoided. The analyses performed in this study determine that, after two hours, assuming vessel reflooding has taken place, the containment aerosol concentration can then conservatively be used as the effective source to the leaking MSIV's. Recommendations are provided concerning typical aerosol removal coefficients that can be used in the RADTRAD code to predict source attenuation in the steam lines, and on robust methods of predicting MSIV leakage flows based on measured MSIV leakage performance.

  13. Technical basis for flawed cylinder test specification to assure adequate fracture resistance of ISO high-strength steel cylinder

    SciTech Connect (OSTI)

    Rana, M.D.; Smith, J.H.; Tribolet, R.O.

    1997-11-01

    High-pressure industrial gases (such as oxygen, nitrogen, argon, hydrogen, etc.) are stored and transported in portable cylinders. ISO TC58 SC3 has developed a draft specification 9809 for design and fabrication of high-pressure cylinders with maximum tensile strength limitation of 1,100 N/mm{sup 2}. In order to extend the ISO 9809 rules for higher than 1,100 N/mm{sup 2} strength level cylinders, a working group WG14 was formed in 1989 to develop new rules to assure adequate fracture resistance. In 1994, WG14 recommended a simple, but unique flawed cylinder test method for design qualification of the cylinder and acceptance criteria to assure adequate fracture resistance. WG14 also recommended Charpy-V-notch impact tests to control the required fracture resistance on production cylinders. This paper presents the technical basis that was employed in developing the flawed cylinder test method and acceptance criteria. The specification was developed for seamless steel cylinders having actual strength in the range of 1,100 to 1,400 N/mm{sup 2} and cylindrical section wall thickness in the range of 3 to 10 mm. Flawed cylinder tests were conducted on several hundred cylinders of varying sizes and strength levels. The specification requires to demonstrate LEAK-BEFORE-BREAK performance of the cylinder having flaw length equal to 1.6 (o.d. {times} t{sub design}){sup 0.5} at failure pressure = (t{sub design}/t{sub actual}) x Design Pressure.

  14. Technical basis for flawed cylinder test specification to assure adequate fracture resistance of ISO high strength steel cylinder

    SciTech Connect (OSTI)

    Rana, M.D.; Smith, J.H.; Tribolet, R.O.

    1996-12-01

    High pressure industrial gases (such as oxygen, nitrogen, argon, hydrogen, etc.) are stored and transported in portable cylinders. ISO TC58 SC3 has developed a draft specification 9809 for design and fabrication of high pressure cylinders with maximum tensile strength limitation of 1,100 N/mm{sup 2}. In order to extend the ISO 9809 rules for higher than 1,100 N/mm{sup 2} strength level cylinders, a working group WG14 was formed in 1989 to develop new rules to assure adequate fracture resistance. In 1994, WG14 recommended a simple, but unique flawed cylinder test method for design qualification of the cylinder and acceptance criteria to assure adequate fracture resistance. WG14 also recommended Charpy-V-Notch impact tests to control the required fracture resistance on production cylinders. This paper presents the technical basis that was employed in developing the flawed cylinder test method and acceptance criteria. The specification was developed for seamless steel cylinders having actual strength in the range of 1,100 to 1,400 N/mm{sup 2} and cylindrical section wall thickness in the range of 3mm to 10mm. Flawed cylinder tests were conducted on several hundred cylinders of varying sizes and strength levels. The specification requires to demonstrate LEAK-BEFORE-BREAK performance of the cylinder having flaw length equal to 1.6(O.D. {times} t{sub design}){sup 0.5} at failure pressure = (t{sub design}/t{sub actual}) {times} Design Pressure.

  15. Structural basis of the heterodimerization of the MST and RASSF SARAH domains in the Hippo signalling pathway

    SciTech Connect (OSTI)

    Hwang, Eunha; Cheong, Hae-Kap; Mushtaq, Ameeq Ul; Kim, Hye-Yeon; Yeo, Kwon Joo; Kim, Eunhee; Lee, Woo Cheol; Hwang, Kwang Yeon; Cheong, Chaejoon; Jeon, Young Ho

    2014-07-01

    The heterodimeric structure of the MST1 and RASSF5 SARAH domains is presented. A comparison of homodimeric and heterodimeric interactions provides a structural basis for the preferential association of the SARAH heterodimer. Despite recent progress in research on the Hippo signalling pathway, the structural information available in this area is extremely limited. Intriguingly, the homodimeric and heterodimeric interactions of mammalian sterile 20-like (MST) kinases through the so-called ‘SARAH’ (SAV/RASSF/HPO) domains play a critical role in cellular homeostasis, dictating the fate of the cell regarding cell proliferation or apoptosis. To understand the mechanism of the heterodimerization of SARAH domains, the three-dimensional structures of an MST1–RASSF5 SARAH heterodimer and an MST2 SARAH homodimer were determined by X-ray crystallography and were analysed together with that previously determined for the MST1 SARAH homodimer. While the structure of the MST2 homodimer resembled that of the MST1 homodimer, the MST1–RASSF5 heterodimer showed distinct structural features. Firstly, the six N-terminal residues (Asp432–Lys437), which correspond to the short N-terminal 3{sub 10}-helix h1 kinked from the h2 helix in the MST1 homodimer, were disordered. Furthermore, the MST1 SARAH domain in the MST1–RASSF5 complex showed a longer helical structure (Ser438–Lys480) than that in the MST1 homodimer (Val441–Lys480). Moreover, extensive polar and nonpolar contacts in the MST1–RASSF5 SARAH domain were identified which strengthen the interactions in the heterodimer in comparison to the interactions in the homodimer. Denaturation experiments performed using urea also indicated that the MST–RASSF heterodimers are substantially more stable than the MST homodimers. These findings provide structural insights into the role of the MST1–RASSF5 SARAH domain in apoptosis signalling.

  16. Ab Initio Calculation of Nuclear Magnetic Resonance Chemical Shift Anisotropy Tensors 1. Influence of Basis Set on the Calculation of 31P Chemical Shifts

    SciTech Connect (OSTI)

    Alam, T.M.

    1998-09-01

    The influence of changes in the contracted Gaussian basis set used for ab initio calculations of nuclear magnetic resonance (NMR) phosphorous chemical shift anisotropy (CSA) tensors was investigated. The isotropic chemical shitl and chemical shift anisotropy were found to converge with increasing complexity of the basis set at the Hartree-Fock @IF) level. The addition of d polarization function on the phosphorous nucIei was found to have a major impact of the calculated chemical shi~ but diminished with increasing number of polarization fimctions. At least 2 d polarization fimctions are required for accurate calculations of the isotropic phosphorous chemical shift. The introduction of density fictional theory (DFT) techniques through tie use of hybrid B3LYP methods for the calculation of the phosphorous chemical shift tensor resulted in a poorer estimation of the NMR values, even though DFT techniques result in improved energy and force constant calculations. The convergence of the W parametem with increasing basis set complexity was also observed for the DFT calculations, but produced results with consistent large deviations from experiment. The use of a HF 6-31 l++G(242p) basis set represents a good compromise between accuracy of the simulation and the complexity of the calculation for future ab initio calculations of 31P NMR parameters in larger complexes.

  17. Building America Technology Solutions for New and Existing Homes: Boiler Control Replacement for Hydronically Heated Multifamily Buildings, Cambridge, Massachusetts

    Broader source: Energy.gov [DOE]

    The ARIES Collaborative partnered with Homeowners' Rehab Inc., a nonprofit affordable housing owner, to upgrade the central hydronic heating system in a 42-unit housing development, reducing heating energy use by an average of 19%.

  18. Seismic Imaging and Inversion: Application of Linear Theory (2012), Cambridge University Press, co-authored with Bob Stolt

    SciTech Connect (OSTI)

    Weglein, Arthur B.; Stolt, Bob H.

    2012-03-01

    Extracting information from seismic data requires knowledge of seismic wave propagation and reflection. The commonly used method involves solving linearly for a reflectivity at every point within the Earth, but this book follows an alternative approach which invokes inverse scattering theory. By developing the theory of seismic imaging from basic principles, the authors relate the different models of seismic propagation, reflection and imaging - thus providing links to reflectivity-based imaging on the one hand and to nonlinear seismic inversion on the other. The comprehensive and physically complete linear imaging foundation developed presents new results at the leading edge of seismic processing for target location and identification. This book serves as a fundamental guide to seismic imaging principles and algorithms and their foundation in inverse scattering theory and is a valuable resource for working geoscientists, scientific programmers and theoretical physicists.

  19. A computational method for solving stochastic ItVolterra integral equations based on stochastic operational matrix for generalized hat basis functions

    SciTech Connect (OSTI)

    Heydari, M.H.; Hooshmandasl, M.R.; Maalek Ghaini, F.M.; Cattani, C.

    2014-08-01

    In this paper, a new computational method based on the generalized hat basis functions is proposed for solving stochastic ItVolterra integral equations. In this way, a new stochastic operational matrix for generalized hat functions on the finite interval [0,T] is obtained. By using these basis functions and their stochastic operational matrix, such problems can be transformed into linear lower triangular systems of algebraic equations which can be directly solved by forward substitution. Also, the rate of convergence of the proposed method is considered and it has been shown that it is O(1/(n{sup 2}) ). Further, in order to show the accuracy and reliability of the proposed method, the new approach is compared with the block pulse functions method by some examples. The obtained results reveal that the proposed method is more accurate and efficient in comparison with the block pule functions method.

  20. Report to the Secretary of Energy on Beyond Design Basis Event Pilot Evaluations, Results and Recommendations for Improvements to Enhance Nuclear Safety at DOE Nuclear Facilities, January 2013

    Broader source: Energy.gov [DOE]

    In the six months after the March 2011 Fukushima Daiichi nuclear power plant accident in Japan, the U.S. Department of Energy (DOE) took several actions to review the safety of its nuclear facilities and identify situations where near-term improvements could be made. These actions and recommendations were addressed in an August 2011 report to the Secretary of Energy, Review of Requirements and Capabilities for Analyzing and Responding to Beyond Design Basis Events.

  1. On the ground state calculation of a many-body system using a self-consistent basis and quasi-Monte Carlo: An application to water hexamer

    SciTech Connect (OSTI)

    Georgescu, Ionu? Mandelshtam, Vladimir A.; Jitomirskaya, Svetlana

    2013-11-28

    Given a quantum many-body system, the Self-Consistent Phonons (SCP) method provides an optimal harmonic approximation by minimizing the free energy. In particular, the SCP estimate for the vibrational ground state (zero temperature) appears to be surprisingly accurate. We explore the possibility of going beyond the SCP approximation by considering the system Hamiltonian evaluated in the harmonic eigenbasis of the SCP Hamiltonian. It appears that the SCP ground state is already uncoupled to all singly- and doubly-excited basis functions. So, in order to improve the SCP result at least triply-excited states must be included, which then reduces the error in the ground state estimate substantially. For a multidimensional system two numerical challenges arise, namely, evaluation of the potential energy matrix elements in the harmonic basis, and handling and diagonalizing the resulting Hamiltonian matrix, whose size grows rapidly with the dimensionality of the system. Using the example of water hexamer we demonstrate that such calculation is feasible, i.e., constructing and diagonalizing the Hamiltonian matrix in a triply-excited SCP basis, without any additional assumptions or approximations. Our results indicate particularly that the ground state energy differences between different isomers (e.g., cage and prism) of water hexamer are already quite accurate within the SCP approximation.

  2. Generalizing the self-healing diffusion Monte Carlo approach to finite temperature: a path for the optimization of low-energy many-body basis expansions

    SciTech Connect (OSTI)

    Kim, Jeongnim; Reboredo, Fernando A

    2014-01-01

    The self-healing diffusion Monte Carlo method for complex functions [F. A. Reboredo J. Chem. Phys. {\\bf 136}, 204101 (2012)] and some ideas of the correlation function Monte Carlo approach [D. M. Ceperley and B. Bernu, J. Chem. Phys. {\\bf 89}, 6316 (1988)] are blended to obtain a method for the calculation of thermodynamic properties of many-body systems at low temperatures. In order to allow the evolution in imaginary time to describe the density matrix, we remove the fixed-node restriction using complex antisymmetric trial wave functions. A statistical method is derived for the calculation of finite temperature properties of many-body systems near the ground state. In the process we also obtain a parallel algorithm that optimizes the many-body basis of a small subspace of the many-body Hilbert space. This small subspace is optimized to have maximum overlap with the one expanded by the lower energy eigenstates of a many-body Hamiltonian. We show in a model system that the Helmholtz free energy is minimized within this subspace as the iteration number increases. We show that the subspace expanded by the small basis systematically converges towards the subspace expanded by the lowest energy eigenstates. Possible applications of this method to calculate the thermodynamic properties of many-body systems near the ground state are discussed. The resulting basis can be also used to accelerate the calculation of the ground or excited states with Quantum Monte Carlo.

  3. Night-time naturally ventilated offices: Statistical simulations of window-use patterns from field monitoring

    SciTech Connect (OSTI)

    Yun, Geun Young; Steemers, Koen

    2010-07-15

    This paper investigates occupant behaviour of window-use in night-time naturally ventilated offices on the basis of a pilot field study, conducted during the summers of 2006 and 2007 in Cambridge, UK, and then demonstrates the effects of employing night-time ventilation on indoor thermal conditions using predictive models of occupant window-use. A longitudinal field study shows that occupants make good use of night-time natural ventilation strategies when provided with openings that allow secure ventilation, and that there is a noticeable time of day effect in window-use patterns (i.e. increased probability of action on arrival and departure). We develop logistic models of window-use for night-time naturally ventilated offices, which are subsequently applied to a behaviour algorithm, including Markov chains and Monte Carlo methods. The simulations using the behaviour algorithm demonstrate a good agreement with the observational data of window-use, and reveal how building design and occupant behaviour collectively affect the thermal performance of offices. They illustrate that the provision of secure ventilation leads to more frequent use of the window, and thus contributes significantly to the achievement of a comfortable indoor environment during the daytime occupied period. For example, the maximum temperature for a night-time ventilated office is found to be 3 C below the predicted value for a daytime-only ventilated office. (author)

  4. TU-F-18A-04: Use of An Image-Based Material-Decomposition Algorithm for Multi-Energy CT to Determine Basis Material Densities

    SciTech Connect (OSTI)

    Li, Z; Leng, S; Yu, L; McCollough, C

    2014-06-15

    Purpose: Published methods for image-based material decomposition with multi-energy CT images have required the assumption of volume conservation or accurate knowledge of the x-ray spectra and detector response. The purpose of this work was to develop an image-based material-decomposition algorithm that can overcome these limitations. Methods: An image-based material decomposition algorithm was developed that requires only mass conservation (rather than volume conservation). With this method, using multi-energy CT measurements made with n=4 energy bins, the mass density of each basis material and of the mixture can be determined without knowledge of the tube spectra and detector response. A digital phantom containing 12 samples of mixtures from water, calcium, iron, and iodine was used in the simulation (Siemens DRASIM). The calibration was performed by using pure materials at each energy bin. The accuracy of the technique was evaluated in noise-free and noisy data under the assumption of an ideal photon-counting detector. Results: Basis material densities can be estimated accurately by either theoretic calculation or calibration with known pure materials. The calibration approach requires no prior information about the spectra and detector response. Regression analysis of theoretical values versus estimated values results in excellent agreement for both noise-free and noisy data. For the calibration approach, the R-square values are 0.9960+/−0.0025 and 0.9476+/−0.0363 for noise-free and noisy data, respectively. Conclusion: From multi-energy CT images with n=4 energy bins, the developed image-based material decomposition method accurately estimated 4 basis material density (3 without k-edge and 1 with in the range of the simulated energy bins) even without any prior information about spectra and detector response. This method is applicable to mixtures of solutions and dissolvable materials, where volume conservation assumptions do not apply. CHM receives research support from NIH and Siemens Healthcare.

  5. Microcavity Polaritonics: Optically-Steering Interacting Quantum Liquids on

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    a Chip | MIT-Harvard Center for Excitonics Microcavity Polaritonics: Optically-Steering Interacting Quantum Liquids on a Chip October 17, 2013 at 3pm/36-428 Jeremy Baumberg Department of Physics NanoPhotonics Centre, University of Cambridge, UK baumberg002_001 Abstract: Constructing ultra-high finesse semiconductor microcavities produces quasiparticles called exciton polaritons which can Bose condense even up to room temperature. The resulting macroscopic quantum states are directly visible

  6. Appendices for the Basis Document

    Broader source: Energy.gov [DOE]

    INTEC Tank Farm Facility Closure Supporting Tables and Photographs - In support of the Tank Farm Facility (TFF) closure, inventory tables were generated for all tanks that have been cleaned up to...

  7. Design Basis Threat Policy (U)

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2004-10-01

    This Order is classified and will not be available on the Directives Portal. For distribution, NA employees should contact Jon Todd, 202-586-2579; all other DOE employees should contact Ron Francis, 301-903-6874. Does not cancel other directives.

  8. Design Basis Threat Policy (U)

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2005-11-29

    This Order is classified and will not be available on the Directives Portal. For distribution, contact John Fitzgibbons, 301-903-1361, john.fitzgibbons@hq.doe.gov. Cancels: DOE O 470.3

  9. Appendices for the Basis Document

    Office of Environmental Management (EM)

    A-1 Appendix A INTEC Tank Farm Facility Closure Supporting Tables and Photographs A-2 Appendix A INTEC Tank Farm Facility Closure Supporting Tables and Photographs In support of the Tank Farm Facility (TFF) closure, inventory tables were generated for all tanks that have been cleaned up to this point; these tables are presented is Section A-1. Inventories at closure for all of the tanks that have been cleaned show that Tank WM-182 contains the highest Ci content. The inventory at closure for

  10. Agni UK Inc | Open Energy Information

    Open Energy Info (EERE)

    Kingdom Zip: EC2Y 8AD Sector: Biofuels Product: Focused on design and development of fuel cells, co(tri)generation technology, biofuels and CO2 sequestration technology....

  11. Uk'e koley: No Footprint

    Energy Savers [EERE]

    Nay'dini'aa Na' Presenter: Brian Winnestaffer For: Jim Shaginoff Before After Ø Nay'dini'aa Na' meaning: a log across the river Ø Our Tribe has long been devoted to being a good steward to the environment, understanding that it is our responsibility to take care of the land that has been loaned to us for the short time we are here. Ø Historically harvested resources include salmon, moose, caribou, beluga whale, grizzly and black bear, dall sheep, beaver and numerous other animals and plants

  12. Energy Events UK Ltd | Open Energy Information

    Open Energy Info (EERE)

    Expo is an event organiser dedicated to clean, efficient, sustainable energy consumption within the corporate world. Coordinates: 51.506325, -0.127144 Show Map Loading...

  13. Dario.Castiglione@awe.co.uk

    Office of Environmental Management (EM)

    ... Volume Twin Cell Heat-Flow Calorimeters ... IMOG. 12 Combustion Techniques Underpinning method for 'soft' waste assay to ... counting. No internalexternal source ...

  14. UK - NETL Cooperation | Open Energy Information

    Open Energy Info (EERE)

    Cooperation AgencyCompany Organization National Energy Technology Laboratory Partner United Kingdom Sector Energy Website http:www.netl.doe.govtechno Country United Kingdom...

  15. Dario.Castiglione@awe.co.uk

    Office of Environmental Management (EM)

    DRSG Comments to DOE Smart Grid RFI: Addressing Policy and Logistical Challenges DRSG- 1 DOE Smart Grid RFI Titled "Addressing Policy and Logistical Challenges to Smart Grid Implementation" Submitted by the Demand Response and Smart Grid Coalition (DRSG) November 1, 2010 DRSG Comments to DOE Smart Grid RFI: Addressing Policy and Logistical Challenges DRSG- 2 I. Definition and Scope 1. What significant policy challenges are likely to remain unaddressed if we employ Title XIII's

  16. UK FT PDU Facility Draft EA

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    42S Final Supplemental Environmental Assessment for University of Kentucky Small-Scale Pilot Plant for the Gasification of Coal and Coal-Biomass Blends and Conversion of Derived Syngas to Liquid Fuels via Fischer-Tropsch Synthesis Lexington, KY February 2014 Prepared for: Department of Energy National Energy Technology Laboratory This page intentionally left blank. Final Supplemental Environmental Assessment DOE/EA-1642S Fischer-Tropsch Process Development Unit February 2014 Cover Sheet Proposed

  17. Argent Energy UK Ltd | Open Energy Information

    Open Energy Info (EERE)

    Motherwell, Scotland, United Kingdom Zip: ML1 5FA Product: Motherwell-based waste-to-energy biodiesel producer that has an operational plant in Scotland. Coordinates:...

  18. Electronic structure basis for the extraordinary magnetoresistance in WTe2

    SciTech Connect (OSTI)

    Pletikosi?, I.; Ali, Mazhar N.; Fedorov, A. V.; Cava, R. J.; Valla, T.

    2014-11-19

    The electronic structure basis of the extremely large magnetoresistance in layered non-magnetic tungsten ditelluride has been investigated by angle-resolved photoelectron spectroscopy. Hole and electron pockets of approximately the same size were found at the Fermi level, suggesting that carrier compensation should be considered the primary source of the effect. The material exhibits a highly anisotropic, quasi one-dimensional Fermi surface from which the pronounced anisotropy of the magnetoresistance follows. As a result, a change in the Fermi surface with temperature was found and a high-density-of-states band that may take over conduction at higher temperatures and cause the observed turn-on behavior of the magnetoresistance in WTe? was identified.

  19. Crystallographic analysis of human hemoglobin elucidates the structural basis of the potent and dual antisickling activity of pyridyl derivatives of vanillin

    SciTech Connect (OSTI)

    Abdulmalik, Osheiza; Ghatge, Mohini S.; Musayev, Faik N.; Parikh, Apurvasena; Chen, Qiukan; Yang, Jisheng; Nnamani, Ijeoma; Danso-Danquah, Richmond; Eseonu, Dorothy N.; Asakura, Toshio; Abraham, Donald J.; Venitz, Jurgen; Safo, Martin K.

    2011-11-01

    Pyridyl derivatives of vanillin increase the fraction of the more soluble oxygenated sickle hemoglobin and/or directly increase the solubility of deoxygenated sickle hemoglobin. Crystallographic analysis reveals the structural basis of the potent and dual antisickling activity of these derivatives. Vanillin has previously been studied clinically as an antisickling agent to treat sickle-cell disease. In vitro investigations with pyridyl derivatives of vanillin, including INN-312 and INN-298, showed as much as a 90-fold increase in antisickling activity compared with vanillin. The compounds preferentially bind to and modify sickle hemoglobin (Hb S) to increase the affinity of Hb for oxygen. INN-312 also led to a considerable increase in the solubility of deoxygenated Hb S under completely deoxygenated conditions. Crystallographic studies of normal human Hb with INN-312 and INN-298 showed that the compounds form Schiff-base adducts with the N-terminus of the ?-subunits to constrain the liganded (or relaxed-state) Hb conformation relative to the unliganded (or tense-state) Hb conformation. Interestingly, while INN-298 binds and directs its meta-positioned pyridine-methoxy moiety (relative to the aldehyde moiety) further down the central water cavity of the protein, that of INN-312, which is ortho to the aldehyde, extends towards the surface of the protein. These studies suggest that these compounds may act to prevent sickling of SS cells by increasing the fraction of the soluble high-affinity Hb S and/or by stereospecific inhibition of deoxygenated Hb S polymerization.

  20. US Energy Sector Vulnerabilities to Climate Change

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    ... Cambridge Energy Research Associates (IHS CERA 2010) similarly estimates that by 2030, ... Cambridge: Cambridge University Press. http:amap.noacia. AMS (American Meteorological ...

  1. Molecular Basis for Complement Recognition and Inhibition Determined by Crystallographic Studies of the Staphylococcal Complement Inhibitor (SCIN) Bound to C3c and C3b

    SciTech Connect (OSTI)

    Garcia, Brandon L.; Ramyar, Kasra X.; Tzekou, Apostolia; Ricklin, Daniel; McWhorter, William J.; Lambris, John D.; Geisbrecht, Brian V.

    2010-10-22

    The human complement system plays an essential role in innate and adaptive immunity by marking and eliminating microbial intruders. Activation of complement on foreign surfaces results in proteolytic cleavage of complement component 3 (C3) into the potent opsonin C3b, which triggers a variety of immune responses and participates in a self-amplification loop mediated by a multi-protein assembly known as the C3 convertase. The human pathogen Staphylococcus aureus has evolved a sophisticated and potent complement evasion strategy, which is predicated upon an arsenal of potent inhibitory proteins. One of these, the staphylococcal complement inhibitor (SCIN), acts at the level of the C3 convertase (C3bBb) and impairs downstream complement function by trapping the convertase in a stable but inactive state. Previously, we have shown that SCIN binds C3b directly and competitively inhibits binding of human factor H and, to a lesser degree, that of factor B to C3b. Here, we report the co-crystal structures of SCIN bound to C3b and C3c at 7.5 and 3.5 {angstrom} limiting resolution, respectively, and show that SCIN binds a critical functional area on C3b. Most significantly, the SCIN binding site sterically occludes the binding sites of both factor H and factor B. Our results give insight into SCIN binding to activated derivatives of C3, explain how SCIN can recognize C3b in the absence of other complement components, and provide a structural basis for the competitive C3b-binding properties of SCIN. In the future, this may suggest templates for the design of novel complement inhibitors based upon the SCIN structure.

  2. Volatility basis-set approach simulation of organic aerosol formation in East Asia: implications for anthropogenic-biogenic interaction and controllable amounts

    SciTech Connect (OSTI)

    Matsui, H.; Koike, Makoto; Kondo, Yutaka; Takami, A.; Fast, Jerome D.; Kanaya, Y.; Takigawa, M.

    2014-09-16

    Organic aerosol (OA) simulations using the volatility basis-set approach were made for East Asia and its outflow region. Model simulations were evaluated through comparisons with OA measured by aerosol mass spectrometers in and around Tokyo (at Komaba and Kisai in summer 2003 and 2004) and over the outflow region in East Asia (at Fukue and Hedo in spring 2009). The simulations with aging processes of organic vapors reasonably well reproduced mass concentrations, temporal variations, and formation efficiency of observed OA at all sites. As OA mass was severely underestimated in the simulations without the aging processes, the oxidations of organic vapors are essential for reasonable OA simulations over East Asia. By considering the aging processes, simulated OA concentrations considerably increased from 0.24 to 1.28 g m-3 in the boundary layer over the whole of East Asia. OA formed from the interaction of anthropogenic and biogenic sources was also enhanced by the aging processes. The fraction of controllable OA was estimated to be 87 % of total OA over the whole of East Asia, showing that most of the OA in our simulations formed anthropogenically (controllable). A large portion of biogenic secondary OA (78 % of biogenic secondary OA) formed through the influence of anthropogenic sources. The high fraction of controllable OA in our simulations is likely because anthropogenic emissions are dominant over East Asia and OA formation is enhanced by anthropogenic sources and their aging processes. Both the amounts (from 0.18 to 1.12 g m-3) and the fraction (from 75 % to 87 %) of controllable OA were increased by aging processes of organic vapors over East Asia.

  3. Comparative genomics of the white-rot fungi, Phanerochaete carnosa and P. chrysosporium, to elucidate the genetic basis of the distinct wood types they colonize

    SciTech Connect (OSTI)

    Suzuki, Hitoshi; MacDonald, Jacqueline; Syed, Khajamohiddin; Salamov, Asaf; Hori, Chiaki; Aerts, Andrea; Henrissat, Bernard; Wiebenga, Ad; vanKuyk, Patricia A.; Barry, Kerrie; Lindquist, Erika; LaButti, Kurt; Lapidus, Alla; Lucas, Susan; Coutinho, Pedro; Gong, Yunchen; Samejima, Masahiro; Mahadevan, Radhakrishnan; Abou-Zaid, Mamdouh; de Vries, Ronald P.; Igarashi, Kiyohiko; Yadav, Jagit S.; Grigoriev, Igor V.; Master, Emma R.

    2012-02-17

    Background Softwood is the predominant form of land plant biomass in the Northern hemisphere, and is among the most recalcitrant biomass resources to bioprocess technologies. The white rot fungus, Phanerochaete carnosa, has been isolated almost exclusively from softwoods, while most other known white-rot species, including Phanerochaete chrysosporium, were mainly isolated from hardwoods. Accordingly, it is anticipated that P. carnosa encodes a distinct set of enzymes and proteins that promote softwood decomposition. To elucidate the genetic basis of softwood bioconversion by a white-rot fungus, the present study reports the P. carnosa genome sequence and its comparative analysis with the previously reported P. chrysosporium genome. Results P. carnosa encodes a complete set of lignocellulose-active enzymes. Comparative genomic analysis revealed that P. carnosa is enriched with genes encoding manganese peroxidase, and that the most divergent glycoside hydrolase families were predicted to encode hemicellulases and glycoprotein degrading enzymes. Most remarkably, P. carnosa possesses one of the largest P450 contingents (266 P450s) among the sequenced and annotated wood-rotting basidiomycetes, nearly double that of P. chrysosporium. Along with metabolic pathway modeling, comparative growth studies on model compounds and chemical analyses of decomposed wood components showed greater tolerance of P. carnosa to various substrates including coniferous heartwood. Conclusions The P. carnosa genome is enriched with genes that encode P450 monooxygenases that can participate in extractives degradation, and manganese peroxidases involved in lignin degradation. The significant expansion of P450s in P. carnosa, along with differences in carbohydrate- and lignin-degrading enzymes, could be correlated to the utilization of heartwood and sapwood preparations from both coniferous and hardwood species.

  4. The Effects of Degraded Digital Instrumentation and Control Systems on Human-system Interfaces and Operator Performance: HFE Review Guidance and Technical Basis

    SciTech Connect (OSTI)

    O'Hara, J.M.; W. Gunther, G. Martinez-Guridi

    2010-02-26

    New and advanced reactors will use integrated digital instrumentation and control (I&C) systems to support operators in their monitoring and control functions. Even though digital systems are typically highly reliable, their potential for degradation or failure could significantly affect operator performance and, consequently, impact plant safety. The U.S. Nuclear Regulatory Commission (NRC) supported this research project to investigate the effects of degraded I&C systems on human performance and plant operations. The objective was to develop human factors engineering (HFE) review guidance addressing the detection and management of degraded digital I&C conditions by plant operators. We reviewed pertinent standards and guidelines, empirical studies, and plant operating experience. In addition, we conducted an evaluation of the potential effects of selected failure modes of the digital feedwater system on human-system interfaces (HSIs) and operator performance. The results indicated that I&C degradations are prevalent in plants employing digital systems and the overall effects on plant behavior can be significant, such as causing a reactor trip or causing equipment to operate unexpectedly. I&C degradations can impact the HSIs used by operators to monitor and control the plant. For example, sensor degradations can make displays difficult to interpret and can sometimes mislead operators by making it appear that a process disturbance has occurred. We used the information obtained as the technical basis upon which to develop HFE review guidance. The guidance addresses the treatment of degraded I&C conditions as part of the design process and the HSI features and functions that support operators to monitor I&C performance and manage I&C degradations when they occur. In addition, we identified topics for future research.

  5. Information basis for developing comprehensive waste management system-US-Japan joint nuclear energy action plan waste management working group phase I report.

    SciTech Connect (OSTI)

    Nutt, M.; Nuclear Engineering Division

    2010-05-25

    The activity of Phase I of the Waste Management Working Group under the United States - Japan Joint Nuclear Energy Action Plan started in 2007. The US-Japan JNEAP is a bilateral collaborative framework to support the global implementation of safe, secure, and sustainable, nuclear fuel cycles (referred to in this document as fuel cycles). The Waste Management Working Group was established by strong interest of both parties, which arise from the recognition that development and optimization of waste management and disposal system(s) are central issues of the present and future nuclear fuel cycles. This report summarizes the activity of the Waste Management Working Group that focused on consolidation of the existing technical basis between the U.S. and Japan and the joint development of a plan for future collaborative activities. Firstly, the political/regulatory frameworks related to nuclear fuel cycles in both countries were reviewed. The various advanced fuel cycle scenarios that have been considered in both countries were then surveyed and summarized. The working group established the working reference scenario for the future cooperative activity that corresponds to a fuel cycle scenario being considered both in Japan and the U.S. This working scenario involves transitioning from a once-through fuel cycle utilizing light water reactors to a one-pass uranium-plutonium fuel recycle in light water reactors to a combination of light water reactors and fast reactors with plutonium, uranium, and minor actinide recycle, ultimately concluding with multiple recycle passes primarily using fast reactors. Considering the scenario, current and future expected waste streams, treatment and inventory were discussed, and the relevant information was summarized. Second, the waste management/disposal system optimization was discussed. Repository system concepts were reviewed, repository design concepts for the various classifications of nuclear waste were summarized, and the factors to consider in repository design and optimization were then discussed. Japan is considering various alternatives and options for the geologic disposal facility and the framework for future analysis of repository concepts was discussed. Regarding the advanced waste and storage form development, waste form technologies developed in both countries were surveyed and compared. Potential collaboration areas and activities were next identified. Disposal system optimization processes and techniques were reviewed, and factors to consider in future repository design optimization activities were also discussed. Then the potential collaboration areas and activities related to the optimization problem were extracted.

  6. TECHNICAL BASIS FOR DOE STANDARD 3013 EQUIVALENCY SUPPORTING REDUCED TEMPERATURE STABILIZATION OF OXALATE-DERIVED PLUTONIUM OXIDE PRODUCED BY THE HB-LINE FACILITY AT SAVANNAH RIVER SITE

    SciTech Connect (OSTI)

    Duffey, J.; Livingston, R.; Berg, J.; Veirs, D.

    2012-07-02

    The HB-Line (HBL) facility at the Savannah River Site (SRS) is designed to produce high-purity plutonium dioxide (PuO{sub 2}) which is suitable for future use in production of Mixed Oxide (MOX) fuel. The MOX Fuel Fabrication Facility (MFFF) requires PuO{sub 2} feed to be packaged per the U.S. Department of Energy (DOE) Standard 3013 (DOE-STD-3013) to comply with the facility's safety basis. The stabilization conditions imposed by DOE-STD-3013 for PuO{sub 2} (i.e., 950 C for 2 hours) preclude use of the HBL PuO{sub 2} in direct fuel fabrication and reduce the value of the HBL product as MFFF feedstock. Consequently, HBL initiated a technical evaluation to define acceptable operating conditions for production of high-purity PuO{sub 2} that fulfills the DOE-STD-3013 criteria for safe storage. The purpose of this document is to demonstrate that within the defined operating conditions, the HBL process will be equivalent for meeting the requirements of the DOE-STD-3013 stabilization process for plutonium-bearing materials from the DOE complex. The proposed 3013 equivalency reduces the prescribed stabilization temperature for high-purity PuO{sub 2} from oxalate precipitation processes from 950 C to 640 C and places a limit of 60% on the relative humidity (RH) at the lowest material temperature. The equivalency is limited to material produced using the HBL established flow sheet, for example, nitric acid anion exchange and Pu(IV) direct strike oxalate precipitation with stabilization at a minimum temperature of 640 C for four hours (h). The product purity must meet the MFFF acceptance criteria of 23,600 {micro}g/g Pu (i.e., 2.1 wt %) total impurities and chloride content less than 250 {micro}g/g of Pu. All other stabilization and packaging criteria identified by DOE-STD-3013-2012 or earlier revisions of the standard apply. Based on the evaluation of test data discussed in this document, the expert judgment of the authors supports packaging the HBL product under a 3013 equivalency. Under the defined process conditions and associated material specifications, the high-purity PuO{sub 2} produced in HBL presents no unique safety concerns for packaging or storage in the 3013 required configuration. The PuO{sub 2} produced using the HBL flow sheet conditions will have a higher specific surface area (SSA) than PuO{sub 2} stabilized at 950 C and, consequently, under identical conditions will adsorb more water from the atmosphere. The greatest challenge to HBL operators will be controlling moisture content below 0.5 wt %. However, even at the 0.5 wt % moisture limit, the maximum acceptable pressure of a stoichiometric mixture of hydrogen and oxygen in the 3013 container is greater than the maximum possible pressure for the HBL PuO{sub 2} product.

  7. travel-demand-modeling

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Demand Modeler, Cambridge Systematics, Tallahassee, FL Abstract ... Travel demand ... Ahmed Mohideen Travel Demand Modeler Cambridge Systematics, Tallahassee, FL Transportation ...

  8. Embargoed:

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Molecular clocks control mutation rate in human cells November 20, 2015 Embargoed: 1600 London time / 1100 US Eastern Time on 09 November 2015 Cancer and ageing could be predetermined by the speed of molecular clocks CAMBRIDGE, UK, and LOS ALAMOS, N.M., Nov. 9, 2015-Every cell in the human body contains a copy of the human genome. Through the course of a lifetime all cells are thought to acquire mutations in their genomes. Some of the mutational processes generating these mutations do so in

  9. gkm993 1..7

    Office of Scientific and Technical Information (OSTI)

    Nucleic Acids Research, 2007, 1-7 doi:10.1093/nar/gkm993 Data growth and its impact on the SCOP database: new developments Antonina Andreeva 1, *, Dave Howorth 1 , John-Marc Chandonia 2,3 , Steven E. Brenner 2 , Tim J. P. Hubbard 4 , Cyrus Chothia 5 and Alexey G. Murzin 1 1 MRC Centre for Protein Engineering, Hills Road, Cambridge CB2 0QH, UK, 2 Department of Plant and Microbial Biology, 461A Koshland Hall 3102, University of California, Berkeley, CA 94720-3102, 3 Physical Biosciences Division,

  10. Events Beyond Design Safety Basis Analysis

    Broader source: Energy.gov [DOE]

    This Safety Alert provides information on a safety concern related to the identification and mitigation of events that may fall outside those analyzed in the documented safety analysis. [Safety Bulletin 2011-01

  11. NDRPProtocolTechBasisCompiled020705.doc

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    ... These two vendors were either the DuPont Chemical Company or the Kodak Company. These films were created, wrapped in a double-sided paper shield (white on the outside to reflect ...

  12. Morphological basis of tolerance to ozone

    SciTech Connect (OSTI)

    Evans, M.J.; Dekker, N.P.; Cabral-Anderson, L.J.; Shami, S.G.

    1985-06-01

    The purpose of this research was to study Type 1 epithelial cells in the ozone (O/sub 3/)-tolerant lung epithelium. Rats were made tolerant by exposure to 0.5 ppm O/sub 3/ for 2 days and allowed to recover in air. Reexposure to a lethal concentration of O/sub 3/ (6 ppm) at 3, 7, and 15 days of recovery revealed that tolerance was present at 3 days but almost absent at 7 and 15 days of recovery. Using Type 2 cell proliferation as a means of quantitating Type 1 cell injury, it was observed that when the preexposed rats were reexposed to 0.5 ppm at 3, 7, and 15 days, very little Type 1 cell injury occurred at 3 days. However, at 7 and 15 days the amount of Type 1 cell injury was the same as that associated with the original exposure. To determine whether there was any change in the alveolar epithelial cell populations between the periods of tolerance (3 days) and its decline (7 and 15 days), the percentage of tritiated thymidine (( /sup 3/H)TdR-labeled Type 1 and 2 cells at these times were determined. There was a significant decrease in (/sup 3/H)TdR-labeled Type 1 and 2 cells between the third and fifteenth days of recovery as excess cells were sloughed off and the tissue returned to normal. Using electron microscopic morphometry, Type 1 and 2 cells were then studied during the decline of tolerance. No change was found in the morphology of Type 2 cells; however, the morphology of Type 1 cells revealed a 58% decrease in surface area and a 25% increase in the arithmetic mean thickness when tolerance was present at 3 days. As tolerance declined (7 and 15 days), Type 1 cell morphology returned to normal. It was concluded that tolerance exists when the surface area of a cell exposed to a particular concentration of ozone is small enough so that the existing antioxidant mechanism contained within that cell volume can protect it from damage.

  13. Structural Basis for the Promiscuous Biosynthetic Prenylation...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Torrey Pines Road, La Jolla, California 92037, USA 2Laboratory of Cell Biotechnology, Biotechnology Research Center, The University of Tokyo, 1-1-1 Yayoi, Bunkyo-ku, Tokyo ...

  14. Modular HTGR Safety Basis and Approach

    SciTech Connect (OSTI)

    Thomas Hicks

    2011-08-01

    The Next Generation Nuclear Plant (NGNP) will be a licensed commercial high temperature gas-cooled reactor (HTGR) capable of producing electricity and/or high temperature process heat for industrial markets supporting a range of end-user applications. The NGNP Project has adopted the 10 CFR 52 Combined License (COL) process, as recommended in the NGNP Licensing Strategy - A Report to Congress, dated August 2008, as the foundation for the NGNP licensing strategy [DOE/NRC 2008]. Nuclear Regulatory Commission (NRC) licensing of the NGNP plant utilizing this process will demonstrate the efficacy for licensing future HTGRs for commercial industrial applications. This information paper is one in a series of submittals that address key generic issues of the priority licensing topics as part of the process for establishing HTGR regulatory requirements. This information paper provides a summary level introduction to HTGR history, public safety objectives, inherent and passive safety features, radionuclide release barriers, functional safety approach, and risk-informed safety approach. The information in this paper is intended to further the understanding of the modular HTGR safety approach with the NRC staff and public stakeholders. The NGNP project does not expect to receive comments on this information paper because other white papers are addressing key generic issues of the priority licensing topics in greater detail.

  15. Structural Basis for Activation of Cholera Toxin

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    of the human small intestine. There, it secretes cholera toxin (CT), a protein whose A1 subunit (CTA1) triggers a series of events culminating in the massive efflux of...

  16. EEG's Preliminary Comments on Basis of Characterization

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    12-03 07,58 FROM,LM TECHNOLOGIES INC ID,5052343008 PAGE ENVIRONMENTAL EVALUATION GROUP , OPPORTUNrTY ( ~ nve ACTION 8'.1PlOYER 1007 WYOMING BOULEVARD, N.E. SUITE F-2 ALBUQUERQUE, NEW MEXICO 87100 (505) 828-1003 FAX (~) 826.1062 ~.:":o September 17, 1999 Dr -Ines Triay. Manager Carlsbad Area Office U-S. Department of Energy P.O. Box 3090 Carlsbad. NM 88221-3090 -,' '0,-. - Dear Dr. Triay: EEG's preliminary comments on the Fundamental Bases of the Characterizaf;on ReCfl.tirement... for

  17. Structural basis for biomolecular recognition in overlapping...

    Office of Scientific and Technical Information (OSTI)

    Resource Type: Journal Article Resource Relation: Journal Name: Nature Communications; Journal Volume: 5; Journal Issue: 09, 2014 Publisher: Nature Publishing Group Research Org: ...

  18. Structural Basis for Activation of Cholera Toxin

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    culprit is the bacterium Vibrio cholerae, which can be ingested through contaminated food or water and colonizes the mucous membrane of the human small intestine. There, it...

  19. Setting clear expectations for safety basis development

    SciTech Connect (OSTI)

    MORENO, M.R.

    2003-05-03

    DOE-RL has set clear expectations for a cost-effective approach for achieving compliance with the Nuclear Safety Management requirements (10 CFR 830, Nuclear Safety Rule) which will ensure long-term benefit to Hanford. To facilitate implementation of these expectations, tools were developed to streamline and standardize safety analysis and safety document development resulting in a shorter and more predictable DOE approval cycle. A Hanford Safety Analysis and Risk Assessment Handbook (SARAH) was issued to standardized methodologies for development of safety analyses. A Microsoft Excel spreadsheet (RADIDOSE) was issued for the evaluation of radiological consequences for accident scenarios often postulated for Hanford. A standard Site Documented Safety Analysis (DSA) detailing the safety management programs was issued for use as a means of compliance with a majority of 3009 Standard chapters. An in-process review was developed between DOE and the Contractor to facilitate DOE approval and provide early course correction. As a result of setting expectations and providing safety analysis tools, the four Hanford Site waste management nuclear facilities were able to integrate into one Master Waste Management Documented Safety Analysis (WM-DSA).

  20. Complex basis functions revisited: Implementation with applications...

    Office of Scientific and Technical Information (OSTI)

    Additional Journal Information: Journal Volume: 142; Journal Issue: 5; Journal ID: ISSN 0021-9606 Publisher: American Institute of Physics Sponsoring Org: USDOE Country of ...

  1. Nuclear Safety Basis Training Program Manager

    Broader source: Energy.gov [DOE]

    **This is an Excepted Service position. This appointment will not confer Competitive Service career-conditional or career tenure status. This means that if you are selected, you would have to...

  2. Climate Change 2001: The Scientific Basis

    Office of Scientific and Technical Information (OSTI)

    of the Forcing Concept 6.3 Well-Mixed Greenhouse Gases 6.3.1 Carbon Dioxide 6.3.2 Methane and Nitrous Oxide 6.3.3 Halocarbons 6.3.4 Total Well-Mixed Greenhouse Gas...

  3. Structural Basis for Activation of Cholera Toxin

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    The culprit is the bacterium Vibrio cholerae, which can be ingested through contaminated food or water and colonizes the mucous membrane of the human small intestine. There, it...

  4. Structural Basis for Activation of Cholera Toxin

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    is the bacterium Vibrio cholerae, which can be ingested through contaminated food or water and colonizes the mucous membrane of the human small intestine. There, it secretes...

  5. Readiness to proceed: Characterization planning basis

    SciTech Connect (OSTI)

    Adams, M.R.

    1998-01-19

    This report summarizes characterization requirements, data availability, and data acquisition plans in support of the Phase 1 Waste Feed Readiness to Proceed Mid-Level Logic. It summarizes characterization requirements for the following program planning documents: Waste Feed Readiness Mid-Level Logic and Decomposition (in development); Master blue print (not available); Tank Waste Remediation System (TWRS) Operations and Utilization Plan and Privatization Contract; Enabling assumptions (not available); Privatization low-activity waste (LAW) Data Quality Objective (DQO); Privatization high-level waste (HLW) DQO (draft); Problem-specific DQOs (in development); Interface control documents (draft). Section 2.0 defines the primary objectives for this report, Section 3.0 discusses the scope and assumptions, and Section 4.0 identifies general characterization needs and analyte-specific characterization needs or potential needs included in program documents and charts. Section 4.0 also shows the analyses that have been conducted, and the archive samples that are available for additional analyses. Section 5.0 discusses current plans for obtaining additional samples and analyses to meet readiness-to-proceed requirements. Section 6.0 summarizes sampling needs based on preliminary requirements and discusses other potential characterization needs. Many requirements documents are preliminary. In many cases, problem-specific DQOs have not been drafted, and only general assumptions about the document contents could be obtained from the authors. As a result, the readiness-to-proceed characterization requirements provided in this document are evolving and may change.

  6. Results from Beyond Design Basis Event Pilots

    Broader source: Energy.gov [DOE]

    Presenter: Mike Hillman, Program Manager, Office of Health, Safety and Security, US Department of Energy

  7. Technical Basis for Assessing Uranium Bioremediation Performance

    SciTech Connect (OSTI)

    PE Long; SB Yabusaki; PD Meyer; CJ Murray; AL N’Guessan

    2008-04-01

    In situ bioremediation of uranium holds significant promise for effective stabilization of U(VI) from groundwater at reduced cost compared to conventional pump and treat. This promise is unlikely to be realized unless researchers and practitioners successfully predict and demonstrate the long-term effectiveness of uranium bioremediation protocols. Field research to date has focused on both proof of principle and a mechanistic level of understanding. Current practice typically involves an engineering approach using proprietary amendments that focuses mainly on monitoring U(VI) concentration for a limited time period. Given the complexity of uranium biogeochemistry and uranium secondary minerals, and the lack of documented case studies, a systematic monitoring approach using multiple performance indicators is needed. This document provides an overview of uranium bioremediation, summarizes design considerations, and identifies and prioritizes field performance indicators for the application of uranium bioremediation. The performance indicators provided as part of this document are based on current biogeochemical understanding of uranium and will enable practitioners to monitor the performance of their system and make a strong case to clients, regulators, and the public that the future performance of the system can be assured and changes in performance addressed as needed. The performance indicators established by this document and the information gained by using these indicators do add to the cost of uranium bioremediation. However, they are vital to the long-term success of the application of uranium bioremediation and provide a significant assurance that regulatory goals will be met. The document also emphasizes the need for systematic development of key information from bench scale tests and pilot scales tests prior to full-scale implementation.

  8. Basis for OUO | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    DOE O 471.3 Admin Chg 1, Identifying and Protecting Official Use Only Information. DOE M 471.3-1 Admin Chg 1, Manual for Identifying and Protecting Official Use Only Information. ...

  9. 2014 signed Mod to the UK SOI.pdf

    Energy Savers [EERE]

  10. Uk'e koley - No Footprint: Chickaloon Village Traditional Council

    Energy Savers [EERE]

    Chickaloon Village Traditional Council Nay'dini'aa Na'  Nay'dini'aa Na' meaning: a log across the river  Our Tribe has long been devoted to being a good steward to the environment, understanding that it is our responsibility to take care of the land that has been loaned to us for the short time we are here.  Historically harvested resources include salmon, moose, caribou, beluga whale, grizzly and black bear, dall sheep, beaver and numerous other animals and plants for food, medicine,

  11. Uk'e koley: "No Footprint"

    Energy Savers [EERE]

    Nay"dini"aa Na" Presenter: Jim Shaginoff  Nay"dini"aa Na" meaning: a log across the river  Our Tribe has long been devoted to being a good steward to the environment, understanding that it is our responsibility to take care of the land that has been loaned to us for the short time we are here.  Historically harvested resources include salmon, moose, caribou, beluga whale, grizzly and black bear, dall sheep, beaver and numerous other animals and plants for

  12. Synoptic comparison of major US and UK simulations

    SciTech Connect (OSTI)

    Henderson, D.B.; Oxenham, D.

    1994-07-01

    The six simulations considered include two from the United Kingdom: The United Kingdom Extended Air Defence Test Bed (UKEADTB) and the Air Defence Test Bed (ADTB). There are two from the Test Bed Product Office of the US Army Space and Strategic Defense Command (USASSDC) in Huntsville, Alabama: The Extended Air Defense Test Bed (EADTB) and the Extended Air Defense Simulation (EADSIM). There are two from the National Test Facility in Colorado Springs, Colorado: The Test Planning Tool (TPT) and the Human in Control Test Bed (HICTB). A seventh, the Brilliant Eyes Simulator (BESim) -- an element simulation and a close family member of the system level TPT -- is included along with TPT by noting exceptions where necessary. The comparisons are designed to be compact and comprehensible, with no table occupying more than a single page. The present report is organized with the tables on the odd numbered pages and some commentary on the facing even numbered pages. While the effort reported is extensive, it needs to be further developed as planned as the Subpanel`s next major undertaking. Analogously with simulations themselves, there remains the question of validation or accreditation. Also analogously, these depend upon the question being served. That is, the responses reported here, while extensive and interesting, need to be explicitly reviewed in the light of any given serious application. Unfortunately, and again analogously with simulations, this accreditation can not be done in the abstract or once and for all.

  13. UK Delegation Focuses on EM's Reactor 'Cocooning' Expertise During...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Regulation; Tony Handley, Magnox Ltd.; Anna Clark, Nuclear Decommissioning Authority; ... Regulation; Tony Handley, Magnox Ltd.; Anna Clark, Nuclear Decommissioning Authority; ...

  14. PostScriptum UK Ltd | Open Energy Information

    Open Energy Info (EERE)

    Product: PostScriptum is a private equity group holding a portfolio of investments in start-up and niche situations, primarily but not exclusively in the energy sector. References:...

  15. EM Delegation Tours UK Cleanup Program’s Sellafield Site

    Broader source: Energy.gov [DOE]

    A senior-level EM delegation led by Associate Principal Deputy Assistant Secretary Alice Williams visited the United Kingdom’s Sellafield nuclear site to gain insight into the cleanup projects and facilities under the jurisdiction of the UK’s Nuclear Decommissioning Authority (NDA).

  16. US and UK discuss efforts to improve technical verification of...

    National Nuclear Security Administration (NNSA)

    at a side event in conjunction with meetings of the Preparatory Committee for the 2015 Review Conference of the Parties to the Treaty on the Non-Proliferation of Nuclear Weapons. ...

  17. US, UK, France Discuss Stockpile Stewardship, Arms Control and...

    National Nuclear Security Administration (NNSA)

    Discussions included technical issues associated with the goals identified in the 2010 Non-Proliferation Treaty Review Conference Action Plan. About the photo: Policy and technical ...

  18. Sandia Energy - Sandia Researchers, UK Partners Publish Groundbreaking...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    by Dino Vournas) In a breakthrough paper published in the January 13, 2012, issue of Science magazine, researchers from Sandia's Combustion Research Facility, the University...

  19. A Deep Geothermal Exploration Well At Eastgate, Weardale, Uk...

    Open Energy Info (EERE)

    granites as targets for geothermal resources. Authors DAC Manning, PL Younger, FW Smith, JM Jones, DJ Dufton and S. Diskin Published Journal Journal of the Geological...

  20. Pascal Baron, CEA - France Christine Brown, BNFL - U.K.

    Broader source: Energy.gov (indexed) [DOE]

    likely focus attention on point A (i.e. the most vulnerable point) if other barriers (guns, gates, and guards) didn't exist in sufficient force. In that regard, we first note...

  1. MHK Projects/The Engineering Business Ltd Shetland Islands UK...

    Open Energy Info (EERE)

    60.5303, -1.26592 Project Phase Phase 1 Project Details The Engineering Business (EB) has recently completed its program to design, build, install, test and...

  2. Accurate ab initio-based adiabatic global potential energy surface for the 2{sup 2}A″ state of NH{sub 2} by extrapolation to the complete basis set limit

    SciTech Connect (OSTI)

    Li, Y. Q.; Ma, F. C.; Sun, M. T.

    2013-10-21

    A full three-dimensional global potential energy surface is reported first time for the title system, which is important for the photodissociation processes. It is obtained using double many-body expansion theory and an extensive set of accurate ab initio energies extrapolated to the complete basis set limit. Such a work can be recommended for dynamics studies of the N({sup 2}D) + H{sub 2} reaction, a reliable theoretical treatment of the photodissociation dynamics and as building blocks for constructing the double many-body expansion potential energy surface of larger nitrogen/hydrogen containing systems. In turn, a preliminary theoretical study of the reaction N({sup 2}D)+H{sub 2}(X{sup 1}Σ{sub g}{sup +})(ν=0,j=0)→NH(a{sup 1}Δ)+H({sup 2}S) has been carried out with the method of quasi-classical trajectory on the new potential energy surface. Integral cross sections and thermal rate constants have been calculated, providing perhaps the most reliable estimate of the integral cross sections and the rate constants known thus far for such a reaction.

  3. Cavity BPM System Tests for the ILC Energy Spectrometer (Journal...

    Office of Scientific and Technical Information (OSTI)

    London ; Orimoto, T.J. ; UC, Berkeley LBL, Berkeley Caltech ; Szalata, Z. ; SLAC ; Thomson, M. ; Cambridge U. ; Ward, D. ; Cambridge U. ; Wing, M. ; University Coll. London ...

  4. 2010 Cohort Profiles | U.S. DOE Office of Science (SC)

    Office of Science (SC) Website

    ... Institute of Technology, Cambridge, MA Chemical Engineering Iris Hood .pdf file (92KB), ... Institute of Technology, Cambridge, MA Chemical Engineering Stephan Hoyer .pdf file ...

  5. Results from a Prototype Chicane-Based Energy Spectrometer for...

    Office of Scientific and Technical Information (OSTI)

    Dubna, JINR UC, Berkeley LBL, Berkeley Caltech UC, Berkeley LBL, Berkeley Cambridge U. SLAC Cambridge U. Fermilab University Coll. London SLAC less Publication...

  6. Nujira Ltd | Open Energy Information

    Open Energy Info (EERE)

    Nujira Ltd Jump to: navigation, search Name: Nujira Ltd Place: Cambridge, United Kingdom Product: A Cambridge-based developer of power amplifier technology for the wireless...

  7. Verenium Corporation (Massachusetts) | Open Energy Information

    Open Energy Info (EERE)

    (Massachusetts) Jump to: navigation, search Name: Verenium Corporation Address: 55 Cambridge Parkway, 8th Floor Place: Cambridge, Massachusetts Zip: 02142 Region: Greater Boston...

  8. OnChip Power | Open Energy Information

    Open Energy Info (EERE)

    OnChip Power Jump to: navigation, search Name: OnChip Power Address: One Cambridge Center Place: Cambridge, Massachusetts Zip: 02142 Sector: Efficiency Product: Power supplies Year...

  9. Element Energy Ltd | Open Energy Information

    Open Energy Info (EERE)

    Element Energy Ltd Jump to: navigation, search Name: Element Energy Ltd. Place: Cambridge, England, United Kingdom Zip: CB1 2JD Product: Cambridge-based strategic energy...

  10. Fastcap Systems Corporation | Open Energy Information

    Open Energy Info (EERE)

    Corporation Jump to: navigation, search Name: Fastcap Systems Corporation Place: Cambridge, Massachusetts Zip: 2139 Sector: Carbon Product: Cambridge-based ultracapacitor...

  11. Oasys Water | Open Energy Information

    Open Energy Info (EERE)

    Oasys Water Jump to: navigation, search Name: Oasys Water Place: Cambridge, Massachusetts Product: Cambridge-based developer of Engineered Osmosis, desalination and water treatment...

  12. The united kingdom's changing requirements for spent fuel storage

    SciTech Connect (OSTI)

    Hodgson, Z.; Hambley, D.I.; Gregg, R.; Ross, D.N.

    2013-07-01

    The UK is adopting an open fuel cycle, and is necessarily moving to a regime of long term storage of spent fuel, followed by geological disposal once a geological disposal facility (GDF) is available. The earliest GDF receipt date for legacy spent fuel is assumed to be 2075. The UK is set to embark on a programme of new nuclear build to maintain a nuclear energy contribution of 16 GW. Additionally, the UK are considering a significant expansion of nuclear energy in order to meet carbon reduction targets and it is plausible to foresee a scenario where up to 75 GW from nuclear power production could be deployed in the UK by the mid 21. century. Such an expansion, could lead to spent fuel storage and its disposal being a dominant issue for the UK Government, the utilities and the public. If the UK were to transition a closed fuel cycle, then spent fuel storage should become less onerous depending on the timescales. The UK has demonstrated a preference for wet storage of spent fuel on an interim basis. The UK has adopted an approach of centralised storage, but a 16 GW new build programme and any significant expansion of this may push the UK towards distributed spent fuel storage at a number of reactors station sites across the UK.

  13. Crawford County, Pennsylvania: Energy Resources | Open Energy...

    Open Energy Info (EERE)

    Adamsville, Pennsylvania Atlantic, Pennsylvania Blooming Valley, Pennsylvania Cambridge Springs, Pennsylvania Canadohta Lake, Pennsylvania Cochranton, Pennsylvania Conneaut...

  14. Structural Basis of Transcription: Role of the Trigger Loop in...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    II active center. Cell 119, 481-489. Allison, L. A., Moyle, M., Shales, M., and Ingles, C. J. (1985). Extensive homology among the largest subunits of eukaryotic and...

  15. Structural basis of AMPK regulation by adenine nucleotides and glycogen

    SciTech Connect (OSTI)

    Li, Xiaodan; Wang, Lili; Zhou, X. Edward; Ke, Jiyuan; de Waal, Parker W.; Gu, Xin; Tan, M. H. Eileen; Wang, Dongye; Wu, Donghai; Xu, H. Eric; Melcher, Karsten

    2014-11-21

    AMP-activated protein kinase (AMPK) is a central cellular energy sensor and regulator of energy homeostasis, and a promising drug target for the treatment of diabetes, obesity, and cancer. Here we present low-resolution crystal structures of the human α1β2γ1 holo-AMPK complex bound to its allosteric modulators AMP and the glycogen-mimic cyclodextrin, both in the phosphorylated (4.05 Å) and non-phosphorylated (4.60 Å) state. In addition, we have solved a 2.95 Å structure of the human kinase domain (KD) bound to the adjacent autoinhibitory domain (AID) and have performed extensive biochemical and mutational studies. Altogether, these studies illustrate an underlying mechanism of allosteric AMPK modulation by AMP and glycogen, whose binding changes the equilibria between alternate AID (AMP) and carbohydrate-binding module (glycogen) interactions.

  16. Molecular Basis for the Recognition of Structurally Distinct...

    Office of Scientific and Technical Information (OSTI)

    Distinct Autoinducer Mimics by the Pseudomonas aeruginosa LasR Quorum-Sensing Signaling ... of infection and host immune resistance, significant efforts have been ...

  17. Technical Cost Modeling - Life Cycle Analysis Basis for Program...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    reductions in GHG, criteria pollutants and acidification gases and * Development of LCA framework based on ISO standards and LCA technical reports such as 14040, 14044, and...

  18. The structural basis of RNA-catalyzed RNA polymerization

    SciTech Connect (OSTI)

    Shechner, David M.; Bartel, David P.

    2011-09-08

    Early life presumably required polymerase ribozymes capable of replicating RNA. Known polymerase ribozymes best approximating such replicases use as their catalytic engine an RNA-ligase ribozyme originally selected from random RNA sequences. Here we report 3.15-{angstrom} crystal structures of this ligase trapped in catalytically viable preligation states, with the 3'-hydroxyl nucleophile positioned for in-line attack on the 5'-triphosphate. Guided by metal- and solvent-mediated interactions, the 5'-triphosphate hooks into the major groove of the adjoining RNA duplex in an unanticipated conformation. Two phosphates and the nucleophile jointly coordinate an active-site metal ion. Atomic mutagenesis experiments demonstrate that active-site nucleobase and hydroxyl groups also participate directly in catalysis, collectively playing a role that in proteinaceous polymerases is performed by a second metal ion. Thus artificial ribozymes can use complex catalytic strategies that differ markedly from those of analogous biological enzymes.

  19. Review and Approval of Nuclear Facility Safety Basis Documents...

    Energy Savers [EERE]

    CHANGE NOTICE NO. 3 Date December 2005 DOE STANDARD REVIEW AND APPROVAL OF NUCLEAR FACILITY SAFETY ... Neither a reviewer nor the preparer has veto power over ultimate resolution or ...

  20. F tank draft basis determination press release 092910 _2_......

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    place. The FTF is a 22-acre site, which consists of 22 underground radioactive waste storage tanks and supporting ancillary structures. The Secretary's decision only determines...

  1. Sculpting bespoke mountains: Determining free energies with basis...

    Office of Scientific and Technical Information (OSTI)

    ; McGovern, Michael 2 ; de Pablo, Juan J. 3 + Show Author Affiliations Department of Chemical and Biomolecular Engineering, University of Notre Dame du Lac, Notre Dame,...

  2. Basis for the US Modern Grid Strategy - A Changing World

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Importance of Smart Grid to Our Nation's Energy Future Steve Pullins President, Horizon Energy Group Steve Bossart Senior Manager, National Energy Technology Laboratory Today's Electricity Grid The U.S. electricity grid is an aging infrastructure based largely on designs of the 1950s before the era of the microprocessor and it was mostly constructed in the 1960s and 1970s. Since the 1970s, the U.S. grid has been expanded as needed to meet load growth using the same vintage technologies. The U.S.

  3. Structural basis of JAZ repression of MYC transcription factors...

    Office of Scientific and Technical Information (OSTI)

    Resource Type: Journal Article Resource Relation: Journal Name: Nature; Journal Volume: ... Word Cloud More Like This Full Text Journal Articles DOI: 10.1038nature14661 Select the ...

  4. Technical Cost Modeling- Life Cycle Analysis Basis for Program Focus

    Broader source: Energy.gov [DOE]

    2012 DOE Hydrogen and Fuel Cells Program and Vehicle Technologies Program Annual Merit Review and Peer Evaluation Meeting

  5. Structural basis for inhibition of DNA replication by aphidicolin

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Baranovskiy, A. G.; Babayeva, N. D.; Suwa, Y.; Gu, J.; Pavlov, Y. I.; Tahirov, T. H.

    2014-11-27

    Natural tetracyclic diterpenoid aphidicolin is a potent and specific inhibitor of B-family DNA polymerases, haltering replication and possessing a strong antimitotic activity in human cancer cell lines. Clinical trials revealed limitations of aphidicolin as an antitumor drug because of its low solubility and fast clearance from human plasma. The absence of structural information hampered the improvement of aphidicolin-like inhibitors: more than 50 modifications have been generated so far, but all have lost the inhibitory and antitumor properties. Here we report the crystal structure of the catalytic core of human DNA polymerase α (Pol α) in the ternary complex with anmore » RNA-primed DNA template and aphidicolin. The inhibitor blocks binding of dCTP by docking at the Pol α active site and by rotating the template guanine. The structure provides a plausible mechanism for the selectivity of aphidicolin incorporation opposite template guanine and explains why previous modifications of aphidicolin failed to improve its affinity for Pol α. With new structural information, aphidicolin becomes an attractive lead compound for the design of novel derivatives with enhanced inhibitory properties for B-family DNA polymerases.« less

  6. The structural basis for receptor recognition of human interleukin-18

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Tsutsumi, Naotaka; Kimura, Takeshi; Arita, Kyohei; Ariyoshi, Mariko; Ohnishi, Hidenori; Yamamoto, Takahiro; Zuo, Xiaobing; Maenaka, Katsumi; Park, Enoch Y.; Kondo, Naomi; et al

    2014-12-15

    Interleukin (IL)-18 is a proinflammatory cytokine that belongs to the IL-1 family and plays an important role in inflammation. The uncontrolled release of this cytokine is associated with severe chronic inflammatory disease. IL-18 forms a signalling complex with the IL-18 receptor α (Rα) and β (Rβ) chains at the plasma membrane, which induces multiple inflammatory cytokines. Here, we present a crystal structure of human IL-18 bound to the two receptor extracellular domains. Generally, the receptors’ recognition mode for IL-18 is similar to IL-1β; however, certain notable differences were observed. The architecture of the IL-18 receptor second domain (D2) is uniquemore » among the other IL-1R family members, which presumably distinguishes them from the IL-1 receptors that exhibit a more promiscuous ligand recognition mode. The structures and associated biochemical and cellular data should aid in developing novel drugs to neutralize IL-8 activity.« less

  7. Atomic substitution reveals the structural basis for substrate...

    Office of Scientific and Technical Information (OSTI)

    by an adenine DNA glycosylase, Bacillus stearothermophilus MutY, have previously ... Language: ENGLISH Subject: 08 HYDROGEN; ADENINES; ATOMS; BACILLUS; BONDING; CLEAVAGE; DNA; ...

  8. Beyond Design Basis Events Analysis and Response Information...

    Broader source: Energy.gov (indexed) [DOE]

    Fact Finding Expert Mission of the Fukushima Dai-ichi Accident Following the Great East Japan Earthquake And Tsunami, June 16, 2011 INPO Special Report - Lessons Learned from the...

  9. Preparation of Safety Basis Documents for Transuranic (TRU) Waste...

    Office of Environmental Management (EM)

    ... and Fire C-1 D Criteria for TRU Waste Drums Requiring Venting... ranging from very low radioactive levels to ... These topics are addressed in a level of detail that ...

  10. Structural Basis of Wnt Signaling Inhibition by Dickkopf Binding...

    Office of Scientific and Technical Information (OSTI)

    Additional Journal Information: Journal Volume: 21; Journal Issue: 5; Journal ID: ISSN 1534-5807 Publisher: Elsevier Sponsoring Org: USDOE Country of Publication: Country unknown...

  11. Structural Basis for Specificity and Flexibility in a Plant 4...

    Office of Scientific and Technical Information (OSTI)

    Resource Relation: Journal Name: Structure; Journal Volume: 23; Journal Issue: (11) ; 11, 2015 Publisher: Elsevier Research Org: Advanced Photon Source (APS), Argonne National ...

  12. Microsoft Word - Final_SRS_FTF_WD_Basis_March_2012

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    ... This facility utilizes fast-response sonic anemometers, ... nuclear production reactors. Before transfer of the waste from the F Canyon to the tank farms, sodium hydroxide was ...

  13. Updated Costs (June 2011 Basis) for Selected Bituminous Baseline...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    has been eliminated in the current version. * Cases 1, 2, 13 and 14, Account 7.1 (Heat Recovery Steam Generator): The HRSG costs were re-calibrated using a series of more recent...

  14. TECHNICAL BASIS DOCUMENT NO. 1: CLIMATE AND INFILTRATION

    SciTech Connect (OSTI)

    NA

    2004-05-01

    For the past 20 years, extensive field, laboratory, and modeling investigations have been performed at Yucca Mountain, which have led to the development of a number of conceptual models of infiltration and climate for the Yucca Mountain region around the repository site (Flint, A.L. et al. 2001; Wang and Bodvarsson 2003). Evaluating the amount of infiltrating water entering the subsurface is important, because this water may affect the percolation flux, which, in turn, controls seepage into the waste emplacement drifts and radionuclide transport from the repository to the water table. Forecasting of climatic data indicates that during the next 10,000 years at Yucca Mountain, the present-day climate should persist for 400 to 600 years, followed by a warmer and much wetter monsoon climate for 900 to 1,400 years, and by a cooler and wetter glacial-transition climate for the remaining 8,000 to 8,700 years. The analysis of climatic forecasting indicates that long-term climate conditions are generally predictable from a past climate sequence, while short-term climate conditions and weather predictions may be more variable and uncertain. The use of past climate sequences to bound future climate sequences involves several types of uncertainties, such as (1) uncertainty in the timing of future climate, (2) uncertainty in the methodology of climatic forecasting, and (3) uncertainty in the earth's future physical processes. Some of the uncertainties of the climatic forecasting are epistemic (reducible) and aleatoric (irreducible). Because of the size of the model domain, INFIL treats many flow processes in a simplified manner. For example, uptake of water by roots occurs according to the ''distributed model'', in which available water in each soil layer is withdrawn in proportion to the root density in that layer, multiplied by the total evapotranspirative demand. Runoff is calculated simply as the excess of precipitation over a sum of infiltration and water storage in the root zone. More significantly, water movement throughout the soil profile is treated according to the bucket model, in which the amount of water that moves down from one layer to the next is equal to the mass of water in excess of field capacity in the upper layer. The development of a numerical model of infiltration involves a number of abstractions and simplifications to represent the complexity of environmental conditions at Yucca Mountain, such as the arid climate, mountain-type topography, heterogeneous soils and fractured rock, and irregular soil-rock interface.

  15. Development of Guidance for Analysis of Beyond Design Basis Events

    Broader source: Energy.gov [DOE]

    Presenter: Dr. James O'Brien, Director, Office of Nuclear Safety, Office of Health, Safety and Security, US Department of Energy

  16. Structural and Functional Basis for Inhibition of Erythrocyte...

    Office of Scientific and Technical Information (OSTI)

    Volume: 9; Journal Issue: (5) ; 05, 2013 Research Org: Advanced Photon Source ... Country of Publication: United States Language: ENGLISH Word Cloud More Like This Full ...

  17. Basis for radiation protection of the nuclear worker

    SciTech Connect (OSTI)

    Guevara, F.A.

    1982-01-01

    A description is given of the standards for protection of persons who work in areas that have a potential for radiation exposure. A review is given of the units of radiation exposure and dose equivalent and of the value of the maximum permissible dose limits for occupational exposure. Federal Regulations and Regulatory Guides for radiation protection are discussed. Average occupational equivalent doses experienced in several operations typical of the United States Nuclear Industry are presented and shown to be significantly lower than the maximum permissible. The concept of maintaining radiation doses to As-Low-As-Reasonably-Achievable is discussed and the practice of imposing engineering and administrative controls to provide effective radiation protection for the nuclear worker is described.

  18. Structural basis for the blockade of MATE multidrug efflux pumps

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Radchenko, Martha; Symersky, Jindrich; Nie, Rongxin; Lu, Min

    2015-08-06

    Multidrug and toxic compound extrusion (MATE) transporters underpin multidrug resistance by using the H+ or Na+ electrochemical gradient to extrude different drugs across cell membranes. MATE transporters can be further parsed into the DinF, NorM and eukaryotic subfamilies based on their amino-acid sequence similarity. Here we report the 3.0 Å resolution X-ray structures of a protonation-mimetic mutant of an H+-coupled DinF transporter, as well as of an H+-coupled DinF and a Na+-coupled NorM transporters in complexes with verapamil, a small-molecule pharmaceutical that inhibits MATE-mediated multidrug extrusion. Combining structure-inspired mutational and functional studies, we confirm the biological relevance of our crystalmore » structures, reveal the mechanistic differences among MATE transporters, and suggest how verapamil inhibits MATE-mediated multidrug efflux. Our findings offer insights into how MATE transporters extrude chemically and structurally dissimilar drugs and could inform the design of new strategies for tackling multidrug resistance.« less

  19. Theoretical Basis for the Design of a DWPF Evacuated Canister

    SciTech Connect (OSTI)

    Routt, K.R.

    2001-09-17

    This report provides the theoretical bases for use of an evacuated canister for draining a glass melter. Design recommendations are also presented to ensure satisfactory performance in future tests of the concept.

  20. NEXT GENERATION NUCLEAR PLANT LICENSING BASIS EVENT SELECTION WHITE PAPER

    SciTech Connect (OSTI)

    Mark Holbrook

    2010-09-01

    The Next Generation Nuclear Plant (NGNP) will be a licensed commercial high temperature gas-cooled reactor (HTGR) plant capable of producing the electricity and high temperature process heat for industrial markets supporting a range of end-user applications. The NGNP Project has adopted the 10 CFR 52 Combined License (COL) application process, as recommended in the Report to Congress, dated August 2008, as the foundation for the NGNP licensing strategy. NRC licensing of the NGNP plant utilizing this process will demonstrate the efficacy of licensing future HTGRs for commercial industrial applications. This white paper is one in a series of submittals that will address key generic issues of the COL priority licensing topics as part of the process for establishing HTGR regulatory requirements.

  1. Structural basis for inhibition of DNA replication by aphidicolin

    SciTech Connect (OSTI)

    Baranovskiy, A. G.; Babayeva, N. D.; Suwa, Y.; Gu, J.; Pavlov, Y. I.; Tahirov, T. H.

    2014-11-27

    Natural tetracyclic diterpenoid aphidicolin is a potent and specific inhibitor of B-family DNA polymerases, haltering replication and possessing a strong antimitotic activity in human cancer cell lines. Clinical trials revealed limitations of aphidicolin as an antitumor drug because of its low solubility and fast clearance from human plasma. The absence of structural information hampered the improvement of aphidicolin-like inhibitors: more than 50 modifications have been generated so far, but all have lost the inhibitory and antitumor properties. Here we report the crystal structure of the catalytic core of human DNA polymerase α (Pol α) in the ternary complex with an RNA-primed DNA template and aphidicolin. The inhibitor blocks binding of dCTP by docking at the Pol α active site and by rotating the template guanine. The structure provides a plausible mechanism for the selectivity of aphidicolin incorporation opposite template guanine and explains why previous modifications of aphidicolin failed to improve its affinity for Pol α. With new structural information, aphidicolin becomes an attractive lead compound for the design of novel derivatives with enhanced inhibitory properties for B-family DNA polymerases.

  2. Structural basis for DNA binding by replication initiator Mcm10

    SciTech Connect (OSTI)

    Warren, Eric M.; Vaithiyalingam, Sivaraja; Haworth, Justin; Greer, Briana; Bielinsky, Anja-Katrin; Chazin, Walter J.; Eichman, Brandt F.

    2009-06-30

    Mcm10 is an essential eukaryotic DNA replication protein required for assembly and progression of the replication fork. The highly conserved internal domain (Mcm10-ID) has been shown to physically interact with single-stranded (ss) DNA, DNA polymerase alpha, and proliferating cell nuclear antigen (PCNA). The crystal structure of Xenopus laevis Mcm10-ID presented here reveals a DNA binding architecture composed of an oligonucleotide/oligosaccharide-fold followed in tandem by a variant and highly basic zinc finger. NMR chemical shift perturbation and mutational studies of DNA binding activity in vitro reveal how Mcm10 uses this unique surface to engage ssDNA. Corresponding mutations in Saccharomyces cerevisiae result in increased sensitivity to replication stress, demonstrating the functional importance of DNA binding by this region of Mcm10 to replication. In addition, mapping Mcm10 mutations known to disrupt PCNA, polymerase alpha, and DNA interactions onto the crystal structure provides insight into how Mcm10 might coordinate protein and DNA binding within the replisome.

  3. Structural basis for the blockade of MATE multidrug efflux pumps

    SciTech Connect (OSTI)

    Radchenko, Martha; Symersky, Jindrich; Nie, Rongxin; Lu, Min

    2015-08-06

    Multidrug and toxic compound extrusion (MATE) transporters underpin multidrug resistance by using the H+ or Na+ electrochemical gradient to extrude different drugs across cell membranes. MATE transporters can be further parsed into the DinF, NorM and eukaryotic subfamilies based on their amino-acid sequence similarity. Here we report the 3.0 Å resolution X-ray structures of a protonation-mimetic mutant of an H+-coupled DinF transporter, as well as of an H+-coupled DinF and a Na+-coupled NorM transporters in complexes with verapamil, a small-molecule pharmaceutical that inhibits MATE-mediated multidrug extrusion. Combining structure-inspired mutational and functional studies, we confirm the biological relevance of our crystal structures, reveal the mechanistic differences among MATE transporters, and suggest how verapamil inhibits MATE-mediated multidrug efflux. Our findings offer insights into how MATE transporters extrude chemically and structurally dissimilar drugs and could inform the design of new strategies for tackling multidrug resistance.

  4. The structural basis for receptor recognition of human interleukin-18

    SciTech Connect (OSTI)

    Tsutsumi, Naotaka; Kimura, Takeshi; Arita, Kyohei; Ariyoshi, Mariko; Ohnishi, Hidenori; Yamamoto, Takahiro; Zuo, Xiaobing; Maenaka, Katsumi; Park, Enoch Y.; Kondo, Naomi; Shirakawa, Masahiro; Tochio, Hidehito; Kato, Zenichiro

    2014-12-15

    Interleukin (IL)-18 is a proinflammatory cytokine that belongs to the IL-1 family and plays an important role in inflammation. The uncontrolled release of this cytokine is associated with severe chronic inflammatory disease. IL-18 forms a signalling complex with the IL-18 receptor α (Rα) and β (Rβ) chains at the plasma membrane, which induces multiple inflammatory cytokines. Here, we present a crystal structure of human IL-18 bound to the two receptor extracellular domains. Generally, the receptors’ recognition mode for IL-18 is similar to IL-1β; however, certain notable differences were observed. The architecture of the IL-18 receptor second domain (D2) is unique among the other IL-1R family members, which presumably distinguishes them from the IL-1 receptors that exhibit a more promiscuous ligand recognition mode. The structures and associated biochemical and cellular data should aid in developing novel drugs to neutralize IL-8 activity.

  5. Initial technical basis for late washing filter cleaning

    SciTech Connect (OSTI)

    Morrissey, M.F.; Dworjanyn, L.O.

    1992-07-23

    Bench scale filter cleaning tests at the Savannah River Technology Center have shown that cross-flow filter elements can be cleaned between late wash filtration runs and restored to original clean water flux conditions. The most effective cleaning technique was high flow axial recirculation, followed by flushing with caustic solution. Simple flushing with oxalic acid and caustic is less effective and is not recommended because of adverse experience in ITP filter cleaning and uncertainty in the.nature of radiolysis by-product contaminants.

  6. Basis for the US Modern Grid Strategy - A Changing World

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    cusp of upgrading our electric grid with some major investments in Advanced Metering Infrastructure, distributed generation, wind turbine farms, and a few Demand Response programs. ...

  7. Structural basis of AMPK regulation by adenine nucleotides and glycogen

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Li, Xiaodan; Wang, Lili; Zhou, X. Edward; Ke, Jiyuan; de Waal, Parker W.; Gu, Xin; Tan, M. H. Eileen; Wang, Dongye; Wu, Donghai; Xu, H. Eric; et al

    2014-11-21

    AMP-activated protein kinase (AMPK) is a central cellular energy sensor and regulator of energy homeostasis, and a promising drug target for the treatment of diabetes, obesity, and cancer. Here we present low-resolution crystal structures of the human α1β2γ1 holo-AMPK complex bound to its allosteric modulators AMP and the glycogen-mimic cyclodextrin, both in the phosphorylated (4.05 Å) and non-phosphorylated (4.60 Å) state. In addition, we have solved a 2.95 Å structure of the human kinase domain (KD) bound to the adjacent autoinhibitory domain (AID) and have performed extensive biochemical and mutational studies. Altogether, these studies illustrate an underlying mechanism of allostericmore » AMPK modulation by AMP and glycogen, whose binding changes the equilibria between alternate AID (AMP) and carbohydrate-binding module (glycogen) interactions.« less

  8. Enterprise Assessments Review of the Delegation of Safety Basis...

    Office of Environmental Management (EM)

    ... Nuclear Security Administration NPO NNSA Production ... Field Office SRFO Savannah River Field Office DOE-SR ... Waste Isolation Pilot Plant Carlsbad Field Office ...

  9. Breckinridge Project, initial effort. Report II. Breckinridge Project design basis

    SciTech Connect (OSTI)

    1982-01-01

    The Breckinridge Project is a pioneer endeavor involving the engineering, construction, and operation of a commercial facility that will convert 23,000 tons per day of run-of-mine, high-sulfur coal into 50,000 barrels per day of liquid hydrocarbons equivalent to those produced from crude oil. The Initial Effort, now complete, was executed under Cooperative Agreement No. DE-FC05-80OR20717 between the Department of Energy and the Participants, Ashland Synthetic Fuels, Inc., and Airco Energy Company, Inc. The Initial Effort produced a preliminary design, capital estimate, and economic analysis of the commercial plant, as well as a plan for the design, construction, and operation of that plant. The extensive and rigorous attention given to environmental, socioeconomic, safety, and health considerations is indicative of the high priority these issues will continue to receive throughout the life of the project. The Breckinridge Energy Company, a partnership of several major corporations, is being formed to finance, own, and manage the Breckinridge Project. Report II is intended for the reader who is primarily interested in less detailed discussion of the coal liquefaction process and Breckinridge facility than presented in the eleven volumes of Reports IV and V. The overview section describes the project goals and briefly introduces the coal liquefaction process. The report continues with a discussion of the history of the project and the H-COAL process from its concept to the proposed commercialization technology. The report describes the site, the Breckinridge Facility, and concludes with a summary of the eleven reports that contain the deliverable documentation of the Initial Effort or Development Phase of the project.

  10. Enterprise Assessments Review of the Delegation of Safety Basis...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    approval authority (SBAA) within the DOE Offices of Science (SC), Nuclear Energy (NE), and Environmental Management (EM), and the National Nuclear Security Administration (NNSA). ...

  11. A BASIS FOR MODIFYING THE TANK 12 COMPOSITE SAMPLING DESIGN

    SciTech Connect (OSTI)

    Shine, G.

    2014-11-25

    The SRR sampling campaign to obtain residual solids material from the Savannah River Site (SRS) Tank Farm Tank 12 primary vessel resulted in obtaining appreciable material in all 6 planned source samples from the mound strata but only in 5 of the 6 planned source samples from the floor stratum. Consequently, the design of the compositing scheme presented in the Tank 12 Sampling and Analysis Plan, Pavletich (2014a), must be revised. Analytical Development of SRNL statistically evaluated the sampling uncertainty associated with using various compositing arrays and splitting one or more samples for compositing. The variance of the simple mean of composite sample concentrations is a reasonable standard to investigate the impact of the following sampling options. Composite Sample Design Option (a). Assign only 1 source sample from the floor stratum and 1 source sample from each of the mound strata to each of the composite samples. Each source sample contributes material to only 1 composite sample. Two source samples from the floor stratum would not be used. Composite Sample Design Option (b). Assign 2 source samples from the floor stratum and 1 source sample from each of the mound strata to each composite sample. This infers that one source sample from the floor must be used twice, with 2 composite samples sharing material from this particular source sample. All five source samples from the floor would be used. Composite Sample Design Option (c). Assign 3 source samples from the floor stratum and 1 source sample from each of the mound strata to each composite sample. This infers that several of the source samples from the floor stratum must be assigned to more than one composite sample. All 5 source samples from the floor would be used. Using fewer than 12 source samples will increase the sampling variability over that of the Basic Composite Sample Design, Pavletich (2013). Considering the impact to the variance of the simple mean of the composite sample concentrations, the recommendation is to construct each sample composite using four or five source samples. Although the variance using 5 source samples per composite sample (Composite Sample Design Option (c)) was slightly less than the variance using 4 source samples per composite sample (Composite Sample Design Option (b)), there is no practical difference between those variances. This does not consider that the measurement error variance, which is the same for all composite sample design options considered in this report, will further dilute any differences. Composite Sample Design Option (a) had the largest variance for the mean concentration in the three composite samples and should be avoided. These results are consistent with Pavletich (2014b) which utilizes a low elevation and a high elevation mound source sample and two floor source samples for each composite sample. Utilizing the four source samples per composite design, Pavletich (2014b) utilizes aliquots of Floor Sample 4 for two composite samples.

  12. Structural basis for bifunctional peptide recognition at human...

    Office of Scientific and Technical Information (OSTI)

    Raimund ; Fromme, Petra ; Tourw, Dirk ; Schiller, Peter W. ; Roth, Bryan L. ; Ballet, Steven ; Katritch, Vsevolod ; Stevens, Raymond C. ; Cherezov , Vadim 1 ; UNC) 2 ;...

  13. Technical Cost Modeling- Life Cycle Analysis Basis for Program Focus

    Broader source: Energy.gov [DOE]

    2010 DOE Vehicle Technologies and Hydrogen Programs Annual Merit Review and Peer Evaluation Meeting, June 7-11, 2010 -- Washington D.C.

  14. Technical Cost Modeling- Life Cycle Analysis Basis for Program Focus

    Broader source: Energy.gov [DOE]

    2011 DOE Hydrogen and Fuel Cells Program, and Vehicle Technologies Program Annual Merit Review and Peer Evaluation

  15. Perspective on Beyond Design Basis Event Analysis and Response

    Broader source: Energy.gov [DOE]

    Presenter: John Schwenker, Nuclear Safety Manager for Liquid Operations, Savannah River Remediation, LLC, Savannah River Site

  16. Homogeneous charge engines -- Basis of cyclic variations. Final report

    SciTech Connect (OSTI)

    Whitelaw, J.H.

    1997-06-30

    The objectives of the Grant required investigations of cyclic variations in a homogeneous-charge engine initially with gas combustion and the air from ranging from near quiescent to the incorporation of swirl and tumble by valve inserts. Later experiments were performed with unleaded gasoline. The measurements included local velocity and cylinder pressure through the four strokes of a single-cylinder engine, under motored and firing conditions and with examination of the flame kernel growth by combinations of photography and flame-ionization gauges. In all cases, the measurements of in-cylinder characteristics were linked to performance as measured in terms of speed and its variability, load and emissions. The experiments progressed to consider deviations from homogeneous charge and included consideration of stratified charge with local injection of a rich mixture in the vicinity of the spark gap so as to establish a flame kernel which would propagate securely into an overall weak mixture.

  17. Elucidating the Molecular Basis and Regulation of Chromium (VI...

    Office of Scientific and Technical Information (OSTI)

    by Shewanella oneidensis MR-1. We have identified and characterized (in the case of DNA-binding response regulator SO2426 and a putative azoreductase SO3585) the genes and ...

  18. Elucidating the Molecular Basis and Regulation of Chromium (VI...

    Office of Scientific and Technical Information (OSTI)

    developed proteomic technology, in particular liquid chromatographymass spectrometry (LC-MS), in conjunction with conventional protein purification and characterization techniques. ...

  19. An accurate and efficient computational protocol for obtaining the complete basis set limits of the binding energies of water clusters at the MP2 and CCSD(T) levels of theory: Application to (H?O)m, m=2-6, 8, 11, 16 and 17

    SciTech Connect (OSTI)

    Miliordos, Evangelos; Xantheas, Sotiris S.

    2015-06-21

    We report MP2 and CCSD(T) binding energies with basis sets up to pentuple zeta quality for the m = 2-6, 8 clusters. Or best CCSD(T)/CBS estimates are -4.99 kcal/mol (dimer), -15.77 kcal/mol (trimer), -27.39 kcal/mol (tetramer), -35.9 0.3 kcal/mol (pentamer), -46.2 0.3 kcal/mol (prism hexamer), -45.9 0.3 kcal/mol (cage hexamer), -45.4 0.3 kcal/mol (book hexamer), -44.3 0.3 kcal/mol (ring hexamer), -73.0 0.5 kcal/mol (D2d octamer) and -72.9 0.5 kcal/mol (S4 octamer). We have found that the percentage of both the uncorrected (dimer) and BSSE-corrected (dimerCPe) binding energies recovered with respect to the CBS limit falls into a narrow range for each basis set for all clusters and in addition this range was found to decrease upon increasing the basis set. Relatively accurate estimates (within < 0.5%) of the CBS limits can be obtained when using the 2/3, 1/3 (for the AVDZ set) or the , (for the AVTZ, AVQZ and AV5Z sets) mixing ratio between dimere and dimerCPe. Based on those findings we propose an accurate and efficient computational protocol that can be used to estimate accurate binding energies of clusters at the MP2 (for up to 100 molecules) and CCSD(T) (for up to 30 molecules) levels of theory. This work was supported by the US Department of Energy, Office of Science, Office of Basic Energy Sciences, Division of Chemical Sciences, Geosciences and Biosciences. Pacific Northwest National Laboratory (PNNL) is a multi program national laboratory operated for DOE by Battelle. This research also used resources of the National Energy Research Scientific Computing Center, which is supported by the Office of Science of the U.S. Department of Energy under Contract No. AC02-05CH11231.

  20. A Resurgent Cauldron In The Early Paleozoic Of Wales, Uk | Open...

    Open Energy Info (EERE)

    that the Ordovician succession of North Wales is more complete than recorded in the literature, and that Caledonian structures were largely predetermined by Caradocian...