Sample records for job safety analysis

  1. Job Safety Analysis College/Department/Unit

    E-Print Network [OSTI]

    Saskatchewan, University of

    Job Safety Analysis (JSA) College/Department/Unit: Title of Job Activity: Oven Location of Activity and understanding the Job Safety Analysis: Date Name (Print) Signature #12;JSA # Page 3 Basic Job Steps Possible

  2. Job Position Description Job Title: Fire Safety Assistant

    E-Print Network [OSTI]

    Moore, Paul A.

    Job Position Description Job Title: Fire Safety Assistant A. Main purpose of the job: To assist equipment. B. Primary responsibilities or key duties of the job (tasks performed regularly): 1. Perform

  3. A path analysis of relationships among job stress, job satisfaction, motivation to transfer, and transfer of learning: perceptions of occupational safety and health administration outreach trainers 

    E-Print Network [OSTI]

    Nair, Prakash Krishnan

    2009-05-15T23:59:59.000Z

    . Finally, path analysis results and mediation tests showed that: (1) the relationship between job stress and transfer was mediated by job satisfaction and motivation to transfer, (2) the relationship between time stress and transfer was mediated by job...

  4. Department of Energy Job Safety and Health Poster

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

    Job Safety & Health It's the law EMPLOYEES And their Representatives have a right to: * Participate in the worksite safety and health program, including inspections of the site; *...

  5. Automated Job Hazards Analysis

    Broader source: Energy.gov [DOE]

    AJHA Program - The Automated Job Hazard Analysis (AJHA) computer program is part of an enhanced work planning process employed at the Department of Energy's Hanford worksite. The AJHA system is routinely used to performed evaluations for medium and high risk work, and in the development of corrective maintenance work packages at the site. The tool is designed to ensure that workers are fully involved in identifying the hazards, requirements, and controls associated with tasks.

  6. Employee Job Task Analysis (EJTA) PIA, Richland Operations Office...

    Office of Environmental Management (EM)

    Job Task Analysis (EJTA) PIA, Richland Operations Office Employee Job Task Analysis (EJTA) PIA, Richland Operations Office Employee Job Task Analysis (EJTA) PIA, Richland...

  7. Biomechanical Job Analysis form Page 1 of 5 Biomechanical Job Analysis

    E-Print Network [OSTI]

    New Hampshire, University of

    Biomechanical Job Analysis form Page 1 of 5 05-20-2009 Biomechanical Job Analysis University of New and health care providers, as appropriate, the physical requirements of campus jobs (e.g., related to cases a summary list of job tasks that are essential to fulfilling job responsibilities. This list is not intended

  8. Webinar: DOE Launches JOBS and Economic Impacts of Fuel Cells (JOBS FC) Analysis Model

    Broader source: Energy.gov [DOE]

    Video recording and text version of the webinar titled, DOE Launches JOBS and Economic Impacts of Fuel Cells (JOBS FC) Analysis Model, originally presented on May 22, 2012.

  9. FAQS Job Task Analyses - Criticality Safety | Department of Energy

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011AT&T,OfficeEnd of Year 2010Salt |ExelonFAQ: RelocationCriticality Safety FAQS Job Task

  10. Department of Energy Job Safety and Health Poster

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny:Revised Finding of No53197 ThisFinalResearchAnnouncementsNevadaJob Safety &

  11. FAQS Job Task Analyses- DOE Aviation Safety Officer

    Broader source: Energy.gov [DOE]

    FAQS Job Task Analyses are performed on the Function Area Qualification Standards. The FAQS Job Task Analyses consists of: Developing a comprehensive list of tasks that define the job such as the duties and responsibilities which include determining their levels of importance and frequency. Identifying and evaluating competencies. Last step is evaluating linkage between job tasks and competencies.

  12. FAQS Job Task Analyses- Nuclear Explosive Safety Study

    Broader source: Energy.gov [DOE]

    FAQS Job Task Analyses are performed on the Function Area Qualification Standards. The FAQS Job Task Analyses consists of: Developing a comprehensive list of tasks that define the job such as the duties and responsibilities which include determining their levels of importance and frequency. Identifying and evaluating competencies. Last step is evaluating linkage between job tasks and competencies.

  13. CRAD, Nuclear Safety Delegations for Documented Safety Analysis...

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

    Safety Delegations for Documented Safety Analysis Approval - January 8, 2015 (EA CRAD 31-09, Rev. 0) CRAD, Nuclear Safety Delegations for Documented Safety Analysis Approval -...

  14. K Basin safety analysis

    SciTech Connect (OSTI)

    Porten, D.R.; Crowe, R.D.

    1994-12-16T23:59:59.000Z

    The purpose of this accident safety analysis is to document in detail, analyses whose results were reported in summary form in the K Basins Safety Analysis Report WHC-SD-SNF-SAR-001. The safety analysis addressed the potential for release of radioactive and non-radioactive hazardous material located in the K Basins and their supporting facilities. The safety analysis covers the hazards associated with normal K Basin fuel storage and handling operations, fuel encapsulation, sludge encapsulation, and canister clean-up and disposal. After a review of the Criticality Safety Evaluation of the K Basin activities, the following postulated events were evaluated: Crane failure and casks dropped into loadout pit; Design basis earthquake; Hypothetical loss of basin water accident analysis; Combustion of uranium fuel following dryout; Crane failure and cask dropped onto floor of transfer area; Spent ion exchange shipment for burial; Hydrogen deflagration in ion exchange modules and filters; Release of Chlorine; Power availability and reliability; and Ashfall.

  15. SAFETY ANALYSIS QUANTITATIVE ANALYSIS ON

    E-Print Network [OSTI]

    Wang, Yinhai

    1 TOPIC C2 SAFETY ANALYSIS AND POLICY QUANTITATIVE ANALYSIS ON ANGLE-ACCIDENT RISK AT SIGNALIZED-2700 Tel: (206) 543-9639 Fax: (206) 543-5965 Email: nihan@u.washington.edu #12;2 Quantitative Analysis on Angle-Accident Risk at Signalized Intersections Abstract: This paper demonstrates how a new modeling

  16. NREL Job Task Analysis: Crew Leader

    SciTech Connect (OSTI)

    Kurnik, C.; Woodley, C.

    2011-05-01T23:59:59.000Z

    A summary of job task analyses for the position of crew leader when conducting weatherization work on a residence.

  17. NREL Job Task Analysis: Energy Auditor

    SciTech Connect (OSTI)

    Kurnik, C.; Woodley, C.

    2011-05-01T23:59:59.000Z

    A summary of job task analyses for the position of energy auditor when evaluating a residence before and during weatherization work.

  18. NREL Job Task Analysis: Quality Control Inspector

    SciTech Connect (OSTI)

    Kurnik, C.; Woodley, C.

    2011-05-01T23:59:59.000Z

    A summary of job task analyses for the position of quality control inspector when evaluating weatherization work that has been done on a residence.

  19. Job Safety and Health Poster | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page onYouTube YouTube Note: Since the.pdfBreaking ofOil & Gas » Methane HydrateEnergyIsJasonJim Payne About UsofJob

  20. Jobs

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOnItemResearch > The Energy Materials Center atdiffusivitiesTechnologies |JobJobs

  1. Safety still Job No. 1 for PRB users

    SciTech Connect (OSTI)

    Javetski, J.

    2006-06-15T23:59:59.000Z

    A report is given of the annual meeting of the Powder River Basin Coal Users' Group (PRBCUG) held in Atlantic during Electric Power 2006. Papers were presented and discussions held on: Coal handling; boilers and combustion; and fire protection, safety and risk management. PRBCUG's plant of the year award wet to TXU Corp.'s Monticello Steam Electric Station, 120 miles east of Dallas. The Group has a re-vamped website at www.prbcoals.com. 3 photos.

  2. Corporate Analysis of DOE Safety Performance

    Broader source: Energy.gov [DOE]

    The Office of Environment, Health, Safety and Security (EHSS), Office of Analysis develops analysis tools and performance dashboards, and conducts analysis of DOE safety performance corporately and on a variety of specific environment, safety and health topics.

  3. 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

  4. B PLANT DOCUMENTED SAFETY ANALYSIS

    SciTech Connect (OSTI)

    DODD, E.N.; KERR, N.R.

    2003-08-01T23:59:59.000Z

    This document provides the documented safety analysis (DSA) and Central Plateau Remediation Project (CP) requirements that apply to surveillance and maintenance (S&M) activities at the 221-B Canyon Building and ancillary support structures (B Plant). The document replaces BHI-010582, Documented Safety Analysis for the B-Plant Facility. The B Plant is non-operational, deactivated and undergoing long term S&M prior to decontamination and decommissioning (D&D). This DSA is compliant with 10 CFR 830, Nuclear Safety Management, Subpart B, ''Safety Basis Requirements.'' The DSA was developed in accordance with U.S. Department of Energy (DOE) standard DOE-STD-1120-98, Integration of Environment, Safety, and Health into Facility Disposition Activities (DOE 1998) per Table 2 of 10 CFR 830 Appendix A, DOE Richland Operation Office (RL) direction (02-ABD-0053, Fluor Hanford Nuclear Safety Basis Strategy and Criteria) for facilities in long term S&M, and RL Direction (02-ABD-0091, ''FHI Nuclear Safety Expectations for Nuclear Facilities in Surveillance and Maintenance''). A crosswalk was prepared to identify potential inconsistencies between the previous B Plant safety analysis and DOE-STD-1120-98 guidance. In general, the safety analysis met the criteria of DOE-STD-1120-98. Some format and content changes have been made, including incorporating recent facility modifications and updating the evaluation guidelines and control selection criteria in accordance with RL direction (02-ABD-0053). The facility fire hazard analysis (FHA) and Technical Safety Requirements (TSR) are appended to this DSA as an aid to the users, to minimize editorial redundancy, and to provide an efficient basis for update.

  5. Job Analysis Template | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't YourTransport(FactDepartment ofLetter Report: I11IG002RTC3 | of EnergyJenny Hakun AboutJob

  6. Environment, Safety and Health Self-Assessment Report Fiscal Year 2010

    E-Print Network [OSTI]

    Robinson, Scott

    2011-01-01T23:59:59.000Z

    of Satellite Hazardous Waste Accumulation Areas On-the-JobArea Inspection Job Hazards Analysis Field Observations Work Outside Normal Hours Accelerator Safety Hazardous

  7. Job Hazard Analysis Step by Step Instructions for Supervisors (who are also Work Leads)

    E-Print Network [OSTI]

    Knowles, David William

    Job Hazard Analysis Step by Step Instructions for Supervisors (who are also Work Leads) Step by Step Instructions ­ Page 1 of 4 Helpful Information STEP 1. Log in to the EH&S Job Hazards Analysis to log in to the system. STEP 2. To begin reviewing the Job Hazards Analysis for your employees, select

  8. SEISMIC ANALYSIS FOR PRECLOSURE SAFETY

    SciTech Connect (OSTI)

    E.N. Lindner

    2004-12-03T23:59:59.000Z

    The purpose of this seismic preclosure safety analysis is to identify the potential seismically-initiated event sequences associated with preclosure operations of the repository at Yucca Mountain and assign appropriate design bases to provide assurance of achieving the performance objectives specified in the Code of Federal Regulations (CFR) 10 CFR Part 63 for radiological consequences. This seismic preclosure safety analysis is performed in support of the License Application for the Yucca Mountain Project. In more detail, this analysis identifies the systems, structures, and components (SSCs) that are subject to seismic design bases. This analysis assigns one of two design basis ground motion (DBGM) levels, DBGM-1 or DBGM-2, to SSCs important to safety (ITS) that are credited in the prevention or mitigation of seismically-initiated event sequences. An application of seismic margins approach is also demonstrated for SSCs assigned to DBGM-2 by showing a high confidence of a low probability of failure at a higher ground acceleration value, termed a beyond-design basis ground motion (BDBGM) level. The objective of this analysis is to meet the performance requirements of 10 CFR 63.111(a) and 10 CFR 63.111(b) for offsite and worker doses. The results of this calculation are used as inputs to the following: (1) A classification analysis of SSCs ITS by identifying potential seismically-initiated failures (loss of safety function) that could lead to undesired consequences; (2) An assignment of either DBGM-1 or DBGM-2 to each SSC ITS credited in the prevention or mitigation of a seismically-initiated event sequence; and (3) A nuclear safety design basis report that will state the seismic design requirements that are credited in this analysis. The present analysis reflects the design information available as of October 2004 and is considered preliminary. The evolving design of the repository will be re-evaluated periodically to ensure that seismic hazards are properly evaluated and identified. This document supersedes the seismic classifications, assignments, and computations in ''Seismic Analysis for Preclosure Safety'' (BSC 2004a).

  9. Job Task Analysis: Building Commissioning Professional; November 2013 - December 2014

    SciTech Connect (OSTI)

    Woodley, C.; DePascale, C.

    2015-01-01T23:59:59.000Z

    This report describes the process for and results of a comprehensive job task analysis of Building Commissioning Professionals. This study was performed by Professional Testing on behalf of the National Renewable Energy Laboratory (NREL). The competency (domains, tasks and associated knowledge) list, which defines the work performed by practitioners, was initially developed by a representative panel of practitioners during a meeting held on February 19?21, 2014 in Orlando Florida. Following the identification of the job tasks and associated knowledge and skills, a validation survey was conducted of the finding of the JTA and the results of the validation study were reviewed by a representative panel of practitioners during a conference call held on June 6, 2014. The committee finalized the JTA and examination blueprints for the Building Commissioning credential scheme based on the survey results.

  10. Job Task Analysis: Energy Manager; November 2013 - December 2014

    SciTech Connect (OSTI)

    Woodley, C. D.

    2015-01-01T23:59:59.000Z

    This report describes the process for and results of a comprehensive job task analysis of Energy Managers. This study was performed by Professional Testing on behalf of the National Renewable Energy Laboratory (NREL). The competency (domains, tasks and associated knowledge) list, which defines the work performed by practitioners, was initially developed by a representative panel of practitioners during a meeting held on January 22?24, 2014 in Orlando Florida. Following the identification of the job tasks and associated knowledge and skills, a validation survey was conducted of the finding of the JTA and the results of the validation study were reviewed by a representative panel of practitioners during a conference call held on June 2, 2014. The committee finalized the JTA and examination blueprints for the Energy Manager credential scheme based on the survey results.

  11. Job Task Analysis: Building Energy Auditor; November 2013 - December 2014

    SciTech Connect (OSTI)

    Woodley, C. D.

    2015-01-01T23:59:59.000Z

    This report describes the process for and results of a comprehensive job task analysis of Energy Auditors. This study was performed by Professional Testing on behalf of the National Renewable Energy Laboratory (NREL). The competency (domains, tasks and associated knowledge) list, which defines the work performed by practitioners, was initially developed by a representative panel of practitioners during a meeting held on February 3?5, 2014 in Orlando Florida. Following the identification of the job tasks and associated knowledge and skills, a validation survey was conducted of the finding of the JTA and the results of the validation study were reviewed by a representative panel of practitioners during a conference call held on May 29, 2014. The committee finalized the JTA and examination blueprints for the Energy Auditor credential scheme based on the survey results.

  12. Job Task Analysis: Building Operations Professional; February - December 2014

    SciTech Connect (OSTI)

    Woodley, C. D.

    2015-01-01T23:59:59.000Z

    This report describes the process for and results of a comprehensive job task analysis of Building Operations Professionals. This study was performed by Professional Testing on behalf of the National Renewable Energy Laboratory (NREL). The competency (domains, tasks and associated knowledge) list, which defines the work performed by practitioners, was initially developed by a representative panel of practitioners during a meeting held on February 10-12, 2014 in Orlando Florida. Following the identification of the job tasks and associated knowledge and skills, a validation survey was conducted of the finding of the JTA and the results of the validation study were reviewed by a representative panel of practitioners during a conference call held on May 30, 2014. The committee finalized the JTA and examination blueprints for the Building Operations Professional credential scheme based on the survey results.

  13. Safety study application guide. Safety Analysis Report Update Program

    SciTech Connect (OSTI)

    Not Available

    1993-07-01T23:59:59.000Z

    Martin Marietta Energy Systems, Inc., (Energy Systems) is committed to performing and documenting safety analyses for facilities it manages for the Department of Energy (DOE). Included are analyses of existing facilities done under the aegis of the Safety Analysis Report Upgrade Program, and analyses of new and modified facilities. A graded approach is used wherein the level of analysis and documentation for each facility is commensurate with the magnitude of the hazard(s), the complexity of the facility and the stage of the facility life cycle. Safety analysis reports (SARs) for hazard Category 1 and 2 facilities are usually detailed and extensive because these categories are associated with public health and safety risk. SARs for Category 3 are normally much less extensive because the risk to public health and safety is slight. At Energy Systems, safety studies are the name given to SARs for Category 3 (formerly {open_quotes}low{close_quotes}) facilities. Safety studies are the appropriate instrument when on-site risks are limited to irreversible consequences to a few people, and off-site consequences are limited to reversible consequences to a few people. This application guide provides detailed instructions for performing safety studies that meet the requirements of DOE Orders 5480.22, {open_quotes}Technical Safety Requirements,{close_quotes} and 5480.23, {open_quotes}Nuclear Safety Analysis Reports.{close_quotes} A seven-chapter format has been adopted for safety studies. This format allows for discussion of all the items required by DOE Order 5480.23 and for the discussions to be readily traceable to the listing in the order. The chapter titles are: (1) Introduction and Summary, (2) Site, (3) Facility Description, (4) Safety Basis, (5) Hazardous Material Management, (6) Management, Organization, and Institutional Safety Provisions, and (7) Accident Analysis.

  14. A Prediction Method for Job Runtimes on Shared Processors: Survey, Statistical Analysis and New

    E-Print Network [OSTI]

    van der Mei, Rob

    A Prediction Method for Job Runtimes on Shared Processors: Survey, Statistical Analysis and New predictions of the expected computation times of those jobs on remote hosts. Currently, there are no effective prediction methods available that cope with the ever-changing running times of jobs on a grid environment

  15. NREL Job Task Analysis: Retrofit Installer Technician | Department of

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn'tOrigin of Contamination in Many Devils Wash,Energy NREL Job Task Analysis: Retrofit Installer

  16. NREL Job Task Analysis: Retrofit Installer Technician (Revised)

    SciTech Connect (OSTI)

    Kurnik, C.; Woodley, C.

    2012-04-01T23:59:59.000Z

    A summary of job task analyses for the position of retrofit installer technician when conducting weatherization work on a residence.

  17. Hot Cell Facility (HCF) Safety Analysis Report

    SciTech Connect (OSTI)

    MITCHELL,GERRY W.; LONGLEY,SUSAN W.; PHILBIN,JEFFREY S.; MAHN,JEFFREY A.; BERRY,DONALD T.; SCHWERS,NORMAN F.; VANDERBEEK,THOMAS E.; NAEGELI,ROBERT E.

    2000-11-01T23:59:59.000Z

    This Safety Analysis Report (SAR) is prepared in compliance with the requirements of DOE Order 5480.23, Nuclear Safety Analysis Reports, and has been written to the format and content guide of DOE-STD-3009-94 Preparation Guide for U. S. Department of Energy Nonreactor Nuclear Safety Analysis Reports. The Hot Cell Facility is a Hazard Category 2 nonreactor nuclear facility, and is operated by Sandia National Laboratories for the Department of Energy. This SAR provides a description of the HCF and its operations, an assessment of the hazards and potential accidents which may occur in the facility. The potential consequences and likelihood of these accidents are analyzed and described. Using the process and criteria described in DOE-STD-3009-94, safety-related structures, systems and components are identified, and the important safety functions of each SSC are described. Additionally, information which describes the safety management programs at SNL are described in ancillary chapters of the SAR.

  18. A framework for graph-based synthesis, analysis, and visualization of HPC cluster job data.

    SciTech Connect (OSTI)

    Mayo, Jackson R.; Kegelmeyer, W. Philip, Jr.; Wong, Matthew H.; Pebay, Philippe Pierre; Gentile, Ann C.; Thompson, David C.; Roe, Diana C.; De Sapio, Vincent; Brandt, James M.

    2010-08-01T23:59:59.000Z

    The monitoring and system analysis of high performance computing (HPC) clusters is of increasing importance to the HPC community. Analysis of HPC job data can be used to characterize system usage and diagnose and examine failure modes and their effects. This analysis is not straightforward, however, due to the complex relationships that exist between jobs. These relationships are based on a number of factors, including shared compute nodes between jobs, proximity of jobs in time, etc. Graph-based techniques represent an approach that is particularly well suited to this problem, and provide an effective technique for discovering important relationships in job queuing and execution data. The efficacy of these techniques is rooted in the use of a semantic graph as a knowledge representation tool. In a semantic graph job data, represented in a combination of numerical and textual forms, can be flexibly processed into edges, with corresponding weights, expressing relationships between jobs, nodes, users, and other relevant entities. This graph-based representation permits formal manipulation by a number of analysis algorithms. This report presents a methodology and software implementation that leverages semantic graph-based techniques for the system-level monitoring and analysis of HPC clusters based on job queuing and execution data. Ontology development and graph synthesis is discussed with respect to the domain of HPC job data. The framework developed automates the synthesis of graphs from a database of job information. It also provides a front end, enabling visualization of the synthesized graphs. Additionally, an analysis engine is incorporated that provides performance analysis, graph-based clustering, and failure prediction capabilities for HPC systems.

  19. Plutonium Uranium Extraction Facility Documented Safety Analysis

    SciTech Connect (OSTI)

    DODD, E.N.

    2003-10-08T23:59:59.000Z

    This document provides the documented safety analysis (DSA) and Central Plateau Remediation Project (CP) requirements that apply to surveillance and maintenance (S&M) activities at the Plutonium-Uranium Extraction (PUREX) facility. This DSA was developed in accordance with DOE-STD-1120-98, ''Integration of Environment, Safety, and Health into Facility Disposition Activities''. Upon approval and implementation of this document, the current safety basis documents will be retired.

  20. Nuclear Criticality Safety Application Guide: Safety Analysis Report Update Program

    SciTech Connect (OSTI)

    Not Available

    1994-02-01T23:59:59.000Z

    Martin Marietta Energy Systems, Inc. (MMES) is committed to performing and documenting safety analyses for facilities it manages for the Department of Energy (DOE). Safety analyses are performed to identify hazards and potential accidents; to analyze the adequacy of measures taken to eliminate, control, or mitigate hazards; and to evaluate potential accidents and determine associated risks. Safety Analysis Reports (SARs) are prepared to document the safety analysis to ensure facilities can be operated safely and in accordance with regulations. Many of the facilities requiring a SAR process fissionable material creating the potential for a nuclear criticality accident. MMES has long had a nuclear criticality safety program that provides the technical support to fissionable material operations to ensure the safe processing and storage of fissionable materials. The guiding philosophy of the program has always been the application of the double-contingency principle, which states: {open_quotes}process designs shall incorporate sufficient factors of safety to require at least two unlikely, independent, and concurrent changes in process conditions before a criticality accident is possible.{close_quotes} At Energy Systems analyses have generally been maintained to document that no single normal or abnormal operating conditions that could reasonably be expected to occur can cause a nuclear criticality accident. This application guide provides a summary description of the MMES Nuclear Criticality Safety Program and the MMES Criticality Accident Alarm System requirements for inclusion in facility SARs. The guide also suggests a way to incorporate the analyses conducted pursuant to the double-contingency principle into the SAR. The prime objective is to minimize duplicative effort between the NCSA process and the SAR process and yet adequately describe the methodology utilized to prevent a nuclear criticality accident.

  1. FAQS Gap Analysis Qualification Card - Senior Technical Safety...

    Office of Environmental Management (EM)

    Gap Analysis Qualification Card - Senior Technical Safety Manager FAQS Gap Analysis Qualification Card - Senior Technical Safety Manager Functional Area Qualification Standard Gap...

  2. Comparison of Integrated Safety Analysis (ISA) and Probabilistic...

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

    Comparison of Integrated Safety Analysis (ISA) and Probabilistic Risk Assessment (PRA) for Fuel Cycle Facilities, 21711 Comparison of Integrated Safety Analysis (ISA) and...

  3. HANFORD SAFETY ANALYSIS & RISK ASSESSMENT HANDBOOK (SARAH)

    SciTech Connect (OSTI)

    EVANS, C B

    2004-12-21T23:59:59.000Z

    The purpose of the Hanford Safety Analysis and Risk Assessment Handbook (SARAH) is to support the development of safety basis documentation for Hazard Category 2 and 3 (HC-2 and 3) U.S. Department of Energy (DOE) nuclear facilities to meet the requirements of 10 CFR 830, ''Nuclear Safety Management''. Subpart B, ''Safety Basis Requirements.'' Consistent with DOE-STD-3009-94, Change Notice 2, ''Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses'' (STD-3009), and DOE-STD-3011-2002, ''Guidance for Preparation of Basis for Interim Operation (BIO) Documents'' (STD-3011), the Hanford SARAH describes methodology for performing a safety analysis leading to development of a Documented Safety Analysis (DSA) and derivation of Technical Safety Requirements (TSR), and provides the information necessary to ensure a consistently rigorous approach that meets DOE expectations. The DSA and TSR documents, together with the DOE-issued Safety Evaluation Report (SER), are the basic components of facility safety basis documentation. For HC-2 or 3 nuclear facilities in long-term surveillance and maintenance (S&M), for decommissioning activities, where source term has been eliminated to the point that only low-level, residual fixed contamination is present, or for environmental remediation activities outside of a facility structure, DOE-STD-1120-98, ''Integration of Environment, Safety, and Health into Facility Disposition Activities'' (STD-1120), may serve as the basis for the DSA. HC-2 and 3 environmental remediation sites also are subject to the hazard analysis methodologies of this standard.

  4. Satellite System Safety Analysis Using STPA

    E-Print Network [OSTI]

    Dunn, Nicholas Connor

    2013-01-01T23:59:59.000Z

    Traditional hazard analysis techniques based on failure models of accident causality, such as the probabilistic risk assessment (PRA) method currently used at NASA, are inadequate for analyzing safety at the system level. ...

  5. Job Safety Analysis College/Department/Unit: Mechanical Engineering

    E-Print Network [OSTI]

    Saskatchewan, University of

    ) is a supplement to the vendor supplied instruction manual, which must be followed. · If a compressed gas cylinder eference O nly #12;JSA # Mat0034 Page 2 Review Frequency: Yearly Review History Review Date Reviewed is used the applicable SOP for compressed gas must be followed. · This instrument is not suitable

  6. Using Addenda in Documented Safety Analysis Reports

    SciTech Connect (OSTI)

    Douglas S. Swanson; Michael A. Thieme

    2003-06-01T23:59:59.000Z

    This paper discusses the use of addenda to the Radioactive Waste Management Complex (RWMC) Documented Safety Analysis (DSA) located at the Idaho National Engineering and Environmental Laboratory (INEEL). Addenda were prepared for several systems and processes at the facility that lacked adequate descriptive information and hazard analysis in the DSA. They were also prepared for several new activities involving unreviewed safety questions (USQs). Ten addenda to the RWMC DSA have been prepared since the last annual update.

  7. Using Addenda in Documented Safety Analysis Reports

    SciTech Connect (OSTI)

    Swanson, D.S.; Thieme, M.A.

    2003-06-16T23:59:59.000Z

    This paper discusses the use of addenda to the Radioactive Waste Management Complex (RWMC) Documented Safety Analysis (DSA) located at the Idaho National Engineering and Environmental Laboratory (INEEL). Addenda were prepared for several systems and processes at the facility that lacked adequate descriptive information and hazard analysis in the DSA. They were also prepared for several new activities involving unreviewed safety questions (USQs). Ten addenda to the RWMC DSA have been prepared since the last annual update.

  8. Autoclave nuclear criticality safety analysis

    SciTech Connect (OSTI)

    D`Aquila, D.M. [Martin Marietta Energy Systems, Inc., Piketon, OH (United States); Tayloe, R.W. Jr. [Battelle, Columbus, OH (United States)

    1991-12-31T23:59:59.000Z

    Steam-heated autoclaves are used in gaseous diffusion uranium enrichment plants to heat large cylinders of UF{sub 6}. Nuclear criticality safety for these autoclaves is evaluated. To enhance criticality safety, systems are incorporated into the design of autoclaves to limit the amount of water present. These safety systems also increase the likelihood that any UF{sub 6} inadvertently released from a cylinder into an autoclave is not released to the environment. Up to 140 pounds of water can be held up in large autoclaves. This mass of water is sufficient to support a nuclear criticality when optimally combined with 125 pounds of UF{sub 6} enriched to 5 percent U{sup 235}. However, water in autoclaves is widely dispersed as condensed droplets and vapor, and is extremely unlikely to form a critical configuration with released UF{sub 6}.

  9. DOE's Safety Bulletin No. 2011-01, Events Beyond Design Safety Basis Analysis, March 2011

    Broader source: Energy.gov [DOE]

    PURPOSE 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.

  10. Delay Components of Job Processing in a Grid: Statistical Analysis and K. Christodoulopoulos, V. Gkamas, E. A. Varvarigos

    E-Print Network [OSTI]

    Varvarigo, Emmanouel "Manos"

    Delay Components of Job Processing in a Grid: Statistical Analysis and Modeling K}@ceid.upatras.gr Abstract The existence of good probabilistic models for the job arrival process and the delay components introduced at the different stages of job processing in a Grid environment is important for the improved

  11. SAFEGUARDS AND SECURITY INTEGRATION WITH SAFETY ANALYSIS

    SciTech Connect (OSTI)

    Hearn, J; James Lightner, J

    2007-04-13T23:59:59.000Z

    The objective of this paper is to share the Savannah River Site lessons learned on Safeguards and Security (S&S) program integration with K-Area Complex (KAC) safety basis. The KAC Documented Safety Analysis (DSA), is managed by the Washington Savannah River Company (WSRC), and the S&S program, managed by Wackenhut Services, Incorporated--Savannah River Site (WSI-SRS). WSRC and WSI-SRS developed a contractual arrangement to recognize WSI-SRS requirements in the KAC safety analysis. Design Basis Threat 2003 (DBT03) security upgrades required physical modifications and operational changes which included the availability of weapons which could potentially impact the facility safety analysis. The KAC DSA did not previously require explicit linkage to the S&S program to satisfy the safety analysis. WSI-SRS have contractual requirements with the Department of Energy (DOE) which are separate from WSRC contract requirements. The lessons learned will include a discussion on planning, analysis, approval of the controls and implementation issues.

  12. Analysis of Integrated Safety Management at the Activity Level...

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

    Integrated Safety Management at the Activity Level: Work Planning and Control, Final Report Analysis of Integrated Safety Management at the Activity Level: Work Planning and...

  13. K West integrated water treatment system subproject safety analysis document

    SciTech Connect (OSTI)

    SEMMENS, L.S.

    1999-02-24T23:59:59.000Z

    This Accident Analysis evaluates unmitigated accident scenarios, and identifies Safety Significant and Safety Class structures, systems, and components for the K West Integrated Water Treatment System.

  14. Waste Isolation Pilot Plant Safety Analysis Report

    SciTech Connect (OSTI)

    NONE

    1995-11-01T23:59:59.000Z

    The following provides a summary of the specific issues addressed in this FY-95 Annual Update as they relate to the CH TRU safety bases: Executive Summary; Site Characteristics; Principal Design and Safety Criteria; Facility Design and Operation; Hazards and Accident Analysis; Derivation of Technical Safety Requirements; Radiological and Hazardous Material Protection; Institutional Programs; Quality Assurance; and Decontamination and Decommissioning. The System Design Descriptions`` (SDDS) for the WIPP were reviewed and incorporated into Chapter 3, Principal Design and Safety Criteria and Chapter 4, Facility Design and Operation. This provides the most currently available final engineering design information on waste emplacement operations throughout the disposal phase up to the point of permanent closure. Also, the criteria which define the TRU waste to be accepted for disposal at the WIPP facility were summarized in Chapter 3 based on the WAC for the Waste Isolation Pilot Plant.`` This Safety Analysis Report (SAR) documents the safety analyses that develop and evaluate the adequacy of the Waste Isolation Pilot Plant Contact-Handled Transuranic Wastes (WIPP CH TRU) safety bases necessary to ensure the safety of workers, the public and the environment from the hazards posed by WIPP waste handling and emplacement operations during the disposal phase and hazards associated with the decommissioning and decontamination phase. The analyses of the hazards associated with the long-term (10,000 year) disposal of TRU and TRU mixed waste, and demonstration of compliance with the requirements of 40 CFR 191, Subpart B and 40 CFR 268.6 will be addressed in detail in the WIPP Final Certification Application scheduled for submittal in October 1996 (40 CFR 191) and the No-Migration Variance Petition (40 CFR 268.6) scheduled for submittal in June 1996. Section 5.4, Long-Term Waste Isolation Assessment summarizes the current status of the assessment.

  15. Hanford safety analysis and risk assessment handbook (SARAH)

    SciTech Connect (OSTI)

    GARVIN, L.J.

    2003-01-20T23:59:59.000Z

    The purpose of the Hanford Safety Analysis and Risk Assessment Handbook (SARAH) is to support the development of safety basis documentation for Hazard Category 1,2, and 3 U.S. Department of Energy (DOE) nuclear facilities. SARAH describes currently acceptable methodology for development of a Documented Safety Analysis (DSA) and derivation of technical safety requirements (TSR) based on 10 CFR 830, ''Nuclear Safety Management,'' Subpart B, ''Safety Basis Requirements,'' and provides data to ensure consistency in approach.

  16. SYNTHESIS OF SAFETY ANALYSIS AND FIRE HAZARD ANALYSIS METHODOLOGIES

    SciTech Connect (OSTI)

    Coutts, D

    2007-04-17T23:59:59.000Z

    Successful implementation of both the nuclear safety program and fire protection program is best accomplished using a coordinated process that relies on sound technical approaches. When systematically prepared, the documented safety analysis (DSA) and fire hazard analysis (FHA) can present a consistent technical basis that streamlines implementation. If not coordinated, the DSA and FHA can present inconsistent conclusions, which can create unnecessary confusion and can promulgate a negative safety perception. This paper will compare the scope, purpose, and analysis techniques for DSAs and FHAs. It will also consolidate several lessons-learned papers on this topic, which were prepared in the 1990s.

  17. NREL: Energy Analysis - Jobs and Economic Development Impact (JEDI) Models

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)Integrated CodesTransparency Visit | NationalWebmaster To contactK-12BSM -JEDI Jobs

  18. Job Creation Analysis in the Hydrogen and Fuel Cell Industry

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't YourTransport(FactDepartment ofLetter Report: I11IG002RTC3 | of EnergyJenny HakunJob Creation

  19. CRAD, Preliminary Documented Safety Analysis - July 25, 2014...

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

    Preliminary Documented Safety Analysis - July 25, 2014 (IEA CRAD 31-2, REV. 0) CRAD, Preliminary Documented Safety Analysis - July 25, 2014 (IEA CRAD 31-2, REV. 0) July 25, 2014...

  20. Light-water reactor safety analysis codes

    SciTech Connect (OSTI)

    Jackson, J.F.; Ransom, V.H.; Ybarrondo, L.J.; Liles, D.R.

    1980-01-01T23:59:59.000Z

    A brief review of the evolution of light-water reactor safety analysis codes is presented. Included is a summary comparison of the technical capabilities of major system codes. Three recent codes are described in more detail to serve as examples of currently used techniques. Example comparisons between calculated results using these codes and experimental data are given. Finally, a brief evaluation of current code capability and future development trends is presented.

  1. A correlational analysis of two versions of the two-factor theory of job satisfaction

    E-Print Network [OSTI]

    Metoskie, John Arthur

    1971-01-01T23:59:59.000Z

    A CORRELATIONAL AIJA! YSIS OF TiiO VERSIONS OF Ti!E TWO-FACTOR THEORY OF JOB SATISFACTION A Thesis JOHN ARTHUR METOSKIE Submitted to the Graduate College of Texas ASM University in partial fulfillment of the requirement for the degree... of MASTER OF SCIENCE December lg71 Major Subject: Psychology A CORRELATIONAL ANALYSIS OF TWO VERSIONS OF THE TWO-FACTOR THEORY OF JOB SATISFACTION A Thesis JOHN ARTHUR METOSKIE Approved as to sty1e and content by: hairman o Commit ee Head...

  2. Mechanistic facility safety and source term analysis

    SciTech Connect (OSTI)

    PLYS, M.G.

    1999-06-09T23:59:59.000Z

    A PC-based computer program was created for facility safety and source term analysis at Hanford The program has been successfully applied to mechanistic prediction of source terms from chemical reactions in underground storage tanks, hydrogen combustion in double contained receiver tanks, and proccss evaluation including the potential for runaway reactions in spent nuclear fuel processing. Model features include user-defined facility room, flow path geometry, and heat conductors, user-defined non-ideal vapor and aerosol species, pressure- and density-driven gas flows, aerosol transport and deposition, and structure to accommodate facility-specific source terms. Example applications are presented here.

  3. 242-A evaporator safety analysis report

    SciTech Connect (OSTI)

    CAMPBELL, T.A.

    1999-05-17T23:59:59.000Z

    This report provides a revised safety analysis for the upgraded 242-A Evaporator (the Evaporator). This safety analysis report (SAR) supports the operation of the Evaporator following life extension upgrades and other facility and operations upgrades (e.g., Project B-534) that were undertaken to enhance the capabilities of the Evaporator. The Evaporator has been classified as a moderate-hazard facility (Johnson 1990). The information contained in this SAR is based on information provided by 242-A Evaporator Operations, Westinghouse Hanford Company, site maintenance and operations contractor from June 1987 to October 1996, and the existing operating contractor, Waste Management Hanford (WMH) policies. Where appropriate, a discussion address the US Department of Energy (DOE) Orders applicable to a topic is provided. Operation of the facility will be compared to the operating contractor procedures using appropriate audits and appraisals. The following subsections provide introductory and background information, including a general description of the Evaporator facility and process, a description of the scope of this SAR revision,a nd a description of the basic changes made to the original SAR.

  4. Improving safety through root cause analysis

    SciTech Connect (OSTI)

    Gatlin, J.L.; Taylor, K.

    1991-01-01T23:59:59.000Z

    Operations at the US Department of Energy -- Savannah River Site (SRS) include such diverse facilities as reactors, fuel fabrication, chemical processing, coal burning power houses, analytical laboratories and research facilities. To enhance the safety of operations at SRS, a Root Cause Analysis process has been developed and is discussed in this document. Root Cause Analysis is a three-step process designed to evaluate and correct problems by identifying WHY an occurrence happened. Although this involves correction after a problem occurs, it is also used to prevent future problems by identifying the Root Causes. Root Causes are the most basic causes that can reasonably be identified, that management has control to fix and for which effective recommendations for preventing recurrence can be generated. Making corrective actions based upon Root Causes lowers the risk of future operation.

  5. Improving safety through root cause analysis

    SciTech Connect (OSTI)

    Gatlin, J.L.; Taylor, K.

    1991-12-31T23:59:59.000Z

    Operations at the US Department of Energy -- Savannah River Site (SRS) include such diverse facilities as reactors, fuel fabrication, chemical processing, coal burning power houses, analytical laboratories and research facilities. To enhance the safety of operations at SRS, a Root Cause Analysis process has been developed and is discussed in this document. Root Cause Analysis is a three-step process designed to evaluate and correct problems by identifying WHY an occurrence happened. Although this involves correction after a problem occurs, it is also used to prevent future problems by identifying the Root Causes. Root Causes are the most basic causes that can reasonably be identified, that management has control to fix and for which effective recommendations for preventing recurrence can be generated. Making corrective actions based upon Root Causes lowers the risk of future operation.

  6. Preliminary Analysis of the Jobs and Economic Impacts of Renewable Energy Projects Supported by the ..Section..1603 Treasury Grant Program

    SciTech Connect (OSTI)

    Steinberg, D.; Porro, G.; Goldberg, M.

    2012-04-01T23:59:59.000Z

    This analysis responds to a request from the Department of Energy Office of Energy Efficiency and Renewable Energy to the National Renewable Energy Laboratory (NREL) to estimate the direct and indirect jobs and economic impacts of projects supported by the Section 1603 Treasury grant program. The analysis employs the Jobs and Economic Development Impacts (JEDI) models to estimate the gross jobs, earnings, and economic output supported by the construction and operation of the large wind (greater than 1 MW) and solar photovoltaic (PV) projects funded by the Section 1603 grant program.

  7. Safety analysis of in-use vehicle wrapping cylinder

    Broader source: Energy.gov [DOE]

    The focus of this presentation is on the security analysis for wrapped cylinders used in vehicles and analyzing safety conditions and environmental effects through testing.

  8. Monthly Analysis of Electrical Safety Occurrences – July 2011

    Broader source: Energy.gov [DOE]

    An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

  9. auditable safety analysis: Topics by E-print Network

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

    of environmental and safety analysis of fusion reactors MIT - DSpace Summary: This report summarizes the progress made between October 1976 and September 1977 in studies of...

  10. Monthly Analysis of Electrical Safety Occurrences – June 2011

    Broader source: Energy.gov [DOE]

    An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

  11. Comparison of Intergrated Safety Analysis (ISA) and Probabilistic...

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

    DC 20555-0001 SUBJECT: COMPARISON OF INTEGRATED SAFETY ANALYSIS (ISA) AND PROBABILISTIC RISK ASSESSMENT (PRA) FOR FUEL CYCLE FACILITIES Dear Chairman Jaczko: During the 580 th...

  12. Job Opening Created: 27 Jun 2012 POSITION: Postdoctoral Appointee -Large-Scale Graph Analysis JOB ID: 641144

    E-Print Network [OSTI]

    Kolda, Tamara G.

    and engineering lab for national security and technology innovation. We are a world-class team of scientists, ranging from homeland defense, global security, biotechnology, and environmental preservation to energy.S. government agencies, including the Department of Energy. JOB DESCRIPTION We are seeking a postdoctoral

  13. Job announcements

    E-Print Network [OSTI]

    2010-01-01T23:59:59.000Z

    to announce a meeting, event or job offer that could be ofmembership corner Job announcements Postdoctoral Researcheris the opportunity to have job openings posted on the

  14. Tank Farms Documented Safety Analysis [Sec 1 thru 4

    SciTech Connect (OSTI)

    GOETZ, T.G.

    2003-10-24T23:59:59.000Z

    The Tank Farm Documented Safety Analysis documents the basis for the conclusion that authorized Tank Farms facility operations comply with the requirements of DOE 5480.23 and DOE 5480.22. This documented safety analysis establishes the safety basis for the tank farms by documenting the results of the hazard and accident analyses for the tank farm facilities and operations and describing the significant features and programs that prevent or mitigate the identified hazards. The documented safety analysis also establishes the envelope within which the tank farm facilities can continue to operate safely.

  15. Safety Analysis of Requirements for a Product Family Robyn R. Lutz

    E-Print Network [OSTI]

    Lutz, Robyn R.

    of this work is to de- scribe a way in which existing and well-documented safety analysis techniques (safety

  16. Safety Evaluation Report of the Waste Isolation Pilot Plant Contact Handled (CH) Waste Documented Safety Analysis

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2005-09-01T23:59:59.000Z

    This Safety Evaluation Report (SER) documents the Department of Energy’s (DOE's) review of Revision 9 of the Waste Isolation Pilot Plant Contact Handled (CH) Waste Documented Safety Analysis, DOE/WIPP-95-2065 (WIPP CH DSA), and provides the DOE Approval Authority with the basis for approving the document. It concludes that the safety basis documented in the WIPP CH DSA is comprehensive, correct, and commensurate with hazards associated with CH waste disposal operations. The WIPP CH DSA and associated technical safety requirements (TSRs) were developed in accordance with 10 CFR 830, Nuclear Safety Management, and DOE-STD-3009-94, Preparation Guide for U. S. Department of Energy Nonreactor Nuclear Safety Analysis Reports.

  17. Job announcements

    E-Print Network [OSTI]

    2012-01-01T23:59:59.000Z

    is the opportunity to have job openings posted on the IBSmembership corner Job announcements Three 2-year postdoc

  18. Job announcements

    E-Print Network [OSTI]

    2013-01-01T23:59:59.000Z

    www.biogeography.org/  To post jobs, advertisements, or long, or longer form).    job announcements  Associate/Full 

  19. Job announcements

    E-Print Network [OSTI]

    2012-01-01T23:59:59.000Z

    membership corner job announcements Center for Macroecology,the opportunity to have job openings in your lab published

  20. Job announcements

    E-Print Network [OSTI]

    2010-01-01T23:59:59.000Z

    membership corner Job announcements 3-year postdoc positionto announce a meeting, event or job offer that could be of

  1. job announcements

    E-Print Network [OSTI]

    2012-01-01T23:59:59.000Z

    the opportunity to have job openings in your lab published membership corner  job announcements  Memorial University 

  2. Preliminary Safety Analysis of the Gorleben Site: Overview - 13298

    SciTech Connect (OSTI)

    Bracke, G.; Fischer-Appelt, K. [GRS mbH, Schwertnergasse 1, 50677 Cologne (Germany)] [GRS mbH, Schwertnergasse 1, 50677 Cologne (Germany); Baltes, B. [B. Baltes, Paul Kaussen Str. 17a, 52477 Alsdorf (Germany)] [B. Baltes, Paul Kaussen Str. 17a, 52477 Alsdorf (Germany)

    2013-07-01T23:59:59.000Z

    The project preliminary safety analysis of the Gorleben site started in 2010 and is based on the safety requirements for heat generating radioactive waste released from the German Federal Ministry for Environment, natural conservation and nuclear safety. The project consists of several tasks: the database defining the geology of Gorleben and the composition of the waste to be disposed of, the safety and demonstration concept, the repository concepts, the scenario analysis, the system analysis with long-term safety assessment and the synthesis. The overall synthesis indicates presently the compatibility of a repository in Gorleben with the safety requirements. The application of the method for a site selection process is still under evaluation. (authors)

  3. JOB SAFETY ASSESSMENT ENVIRONMENTAL

    E-Print Network [OSTI]

    Hartman, Chris

    Radiation (sun) Radio Frequency/Microwave Radiation Lasers Ionizing Radiation Airborne Contaminants (fumes/Herbicide Excavation/Trenching/Shoring Asbestos Awareness/Abatement Welding/Cutting/Brazing/Soldering Powder Actuated

  4. TA-55 Final Safety Analysis Report Comparison Document and DOE Safety Evaluation Report Requirements

    SciTech Connect (OSTI)

    Alan Bond

    2001-04-01T23:59:59.000Z

    This document provides an overview of changes to the currently approved TA-55 Final Safety Analysis Report (FSAR) that are included in the upgraded FSAR. The DOE Safety Evaluation Report (SER) requirements that are incorporated into the upgraded FSAR are briefly discussed to provide the starting point in the FSAR with respect to the SER requirements.

  5. YUCCA MOUNTAIN SITE CHARACTERIZATION PROJECT EAST-WEST DRIFT SYSTEM SAFETY ANALYSIS

    SciTech Connect (OSTI)

    NA

    1999-06-08T23:59:59.000Z

    The purpose of this analysis is to systematically identify and evaluate hazards related to the design of the Yucca Mountain Project Exploratory Studies Facility (ESF) East-West Cross Drift. This analysis builds upon prior ESF System Safety Analyses and incorporates TS Main Drift scenarios, where applicable, into the East-West Drift scenarios. This System Safety Analysis (SSA) focuses on the personnel safety and health hazards associated with the engineered design of the East-West Drift. The analysis also evaluates other aspects of the East-West Drift, including purchased equipment (e.g., scientific mapping platform) or Systems/Structures/Components (SSCs) and out-of-tolerance conditions. In addition to recommending design mitigation features, the analysis identifies the potential need for procedures, training, or Job Safety Analyses (JSAs). The inclusion of this information in the SSA is intended to assist the organization(s) (e.g., constructor, Safety and Health, design) responsible for these aspects of the East-West Drift in evaluating personnel hazards and augment the information developed by these organizations. The SSA is an integral part of the systems engineering process, whereby safety is considered during planning, design, testing, and construction. A largely qualitative approach is used which incorporates operating experiences and recommendations from vendors, the constructor and the operating contractor. The risk assessment in this analysis characterizes the scenarios associated with East-West Drift SSCs in terms of relative risk and includes recommendations for mitigating all identified hazards. The priority for recommending and implementing mitigation control features is: (1) Incorporate measures to reduce risks and hazards into SSC designs. (2) Add safety features and capabilities to existing designs. (3) Develop procedures and conduct training to increase worker awareness of potential hazards, reduce exposure to hazards, and inform personnel of the actions required to avoid accidents or correct hazardous conditions. This analysis does not consider temporary construction items and, therefore, does not consider hazards associated with temporary construction items. This analysis will be reviewed and updated to reflect new East-West Drift design changes, construction modifications, and ''as built'' documentation of the East-West Drift when completed. A major difference between this analysis and previous ESF SSAs is the inclusion of hazards that arise as a result of non-accident events, (e.g., ''off-normal'' operations, adverse environmental conditions, or ''out-of-tolerance'' conditions). Non-accident events, that were not included in previous ESF SSAs, include environmental and/or toxic hazards such as leaking gases/fluids, off-gassing reactions, and excessive dust, particulates, exhaust fumes, noise, temperature, etc. which could have an adverse health effect on personnel.

  6. SNF fuel retrieval sub project safety analysis document

    SciTech Connect (OSTI)

    BERGMANN, D.W.

    1999-02-24T23:59:59.000Z

    This safety analysis is for the SNF Fuel Retrieval (FRS) Sub Project. The FRS equipment will be added to K West and K East Basins to facilitate retrieval, cleaning and repackaging the spent nuclear fuel into Multi-Canister Overpack baskets. The document includes a hazard evaluation, identifies bounding accidents, documents analyses of the accidents and establishes safety class or safety significant equipment to mitigate accidents as needed.

  7. Safety analysis report for the Waste Storage Facility. Revision 2

    SciTech Connect (OSTI)

    Bengston, S.J.

    1994-05-01T23:59:59.000Z

    This safety analysis report outlines the safety concerns associated with the Waste Storage Facility located in the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. The three main objectives of the report are: define and document a safety basis for the Waste Storage Facility activities; demonstrate how the activities will be carried out to adequately protect the workers, public, and environment; and provide a basis for review and acceptance of the identified risk that the managers, operators, and owners will assume.

  8. Documented safety analysis for 209-E Facility critical mass laboratory

    SciTech Connect (OSTI)

    DODD, E.

    2003-04-23T23:59:59.000Z

    This documented safety analysis (DSA) addresses the 209-E facility and associated requirements that apply to 200 Area Facility Deactivation (AFD) activities. The DSA was developed in accordance with DOE-STD-1120-98, ''Integration of Environment, Safety, and Health into Facility Disposition Activities''.

  9. Preparation Of Nonreactor Nuclear Facility Documented Safety Analysis

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

    2014-11-12T23:59:59.000Z

    This Department of Energy (DOE) Standard (STD), DOE-STD-3009-2014, describes a method for preparing a Documented Safety Analysis (DSA) that is acceptable to DOE for nonreactor nuclear facilities.

  10. Safety-driven early concept analysis and development

    E-Print Network [OSTI]

    Fleming, Cody Harrison

    2015-01-01T23:59:59.000Z

    As aerospace systems become increasingly complex and the roles of human operators and autonomous software continue to evolve, traditional safety-related analytical methods are becoming inadequate. Traditional hazard analysis ...

  11. Job announcements

    E-Print Network [OSTI]

    2011-01-01T23:59:59.000Z

    updates from  the IBS, more  job  advertisements,  online lheaney@fieldmuseum.org  Job announcements  2?year postdoc to announce a meeting, event or job offer that could be of 

  12. Job announcements

    E-Print Network [OSTI]

    2011-01-01T23:59:59.000Z

    membership corner  Job announcements  Postdoc position is the opportunity to have job openings posted on the to announce a meeting, event or job offer that could be of 

  13. Job announcements

    E-Print Network [OSTI]

    2011-01-01T23:59:59.000Z

    www.biogeography.org/.   Job announcements  2?year postdoc about?lund?university/jobs  where  this vacancy (NPA to announce a meeting, event or job offer that could be of 

  14. Job announcements

    E-Print Network [OSTI]

    2009-01-01T23:59:59.000Z

    membership corner Job announcements 2-year postdoc projectat http://www.bio.ku.dk/om/jobs. Ap- plication must be basedto announce a meeting, event or job offer that could be of

  15. Job announcements

    E-Print Network [OSTI]

    2010-01-01T23:59:59.000Z

    membership corner Job announcements Two PhD positions Georg-is the opportunity to have job openings posted on the

  16. Job announcements

    E-Print Network [OSTI]

    2009-01-01T23:59:59.000Z

    mation on Alan Graham’s work. Job announcements Postdoctoralto announce a meeting, event or job offer that could be of

  17. Westinghouse Hanford Company safety analysis reports and technical safety requirements upgrade program

    SciTech Connect (OSTI)

    Busche, D.M.

    1995-09-01T23:59:59.000Z

    During Fiscal Year 1992, the US Department of Energy, Richland Operations Office (RL) separately transmitted the following US Department of Energy (DOE) Orders to Westinghouse Hanford Company (WHC) for compliance: DOE 5480.21, ``Unreviewed Safety Questions,`` DOE 5480.22, ``Technical Safety Requirements,`` and DOE 5480.23, ``Nuclear Safety Analysis Reports.`` WHC has proceeded with its impact assessment and implementation process for the Orders. The Orders are closely-related and contain some requirements that are either identical, similar, or logically-related. Consequently, WHC has developed a strategy calling for an integrated implementation of the three Orders. The strategy is comprised of three primary objectives, namely: Obtain DOE approval of a single list of DOE-owned and WHC-managed Nuclear Facilities, Establish and/or upgrade the ``Safety Basis`` for each Nuclear Facility, and Establish a functional Unreviewed Safety Question (USQ) process to govern the management and preservation of the Safety Basis for each Nuclear Facility. WHC has developed policy-revision and facility-specific implementation plans to accomplish near-term tasks associated with the above strategic objectives. This plan, which as originally submitted in August 1993 and approved, provided an interpretation of the new DOE Nuclear Facility definition and an initial list of WHC-managed Nuclear Facilities. For each current existing Nuclear Facility, existing Safety Basis documents are identified and the plan/status is provided for the ISB. Plans for upgrading SARs and developing TSRs will be provided after issuance of the corresponding Rules.

  18. Job satisfaction and job performance: is the relationship spurious?

    E-Print Network [OSTI]

    Cook, Allison Laura

    2009-05-15T23:59:59.000Z

    The link between job satisfaction and job performance is one of the most studied relationships in industrial/organizational psychology. Meta-analysis (Judge, Thoresen, Bono, & Patton, 2001) has estimated the magnitude of this relationship to be ?...

  19. Safety analysis report for packaging (onsite) steel drum

    SciTech Connect (OSTI)

    McCormick, W.A.

    1998-09-29T23:59:59.000Z

    This Safety Analysis Report for Packaging (SARP) provides the analyses and evaluations necessary to demonstrate that the steel drum packaging system meets the transportation safety requirements of HNF-PRO-154, Responsibilities and Procedures for all Hazardous Material Shipments, for an onsite packaging containing Type B quantities of solid and liquid radioactive materials. The basic component of the steel drum packaging system is the 208 L (55-gal) steel drum.

  20. RISMC ADVANCED SAFETY ANALYSIS WORKING PLAN – FY 2015 – FY 2019

    SciTech Connect (OSTI)

    Szilard, Ronaldo H; Smith, Curtis L

    2014-09-01T23:59:59.000Z

    SUMMARY In this report, the Advanced Safety Analysis Program (ASAP) objectives and value proposition is described. ASAP focuses on modernization of nuclear power safety analysis (tools, methods and data); implementing state-of-the-art modeling techniques (which include, for example, enabling incorporation of more detailed physics as they become available); taking advantage of modern computing hardware; and combining probabilistic and mechanistic analyses to enable a risk informed safety analysis process. The modernized tools will maintain the current high level of safety in our nuclear power plant fleet, while providing an improved understanding of safety margins and the critical parameters that affect them. Thus, the set of tools will provide information to inform decisions on plant modifications, refurbishments, and surveillance programs, while improving economics. The set of tools will also benefit the design of new reactors, enhancing safety per unit cost of a nuclear plant. As part of the discussion, we have identified three sets of stakeholders, the nuclear industry, the Department of Energy (DOE), and associated oversight organizations. These three groups would benefit from ASAP in different ways. For example, within the DOE complex, the possible applications that are seen include the safety of experimental reactors, facility life extension, safety-by-design in future generation advanced reactors, and managing security for the storage of nuclear material. This report provides information in five areas: 1. A value proposition (“why is this important?”) that will make the case for stakeholder’s use of the ASAP research and development (R&D) products. 2. An identification of likely end users and pathway to adoption of enhanced tools by the end-users. 3. A proposed set of practical and achievable “use case” demonstrations. 4. A proposed plan to address ASAP verification and validation (V&V) needs. 5. A proposed schedule for the multi-year ASAP.

  1. Using PDSF Job Arrays

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

    Using Job Arrays Using Job Arrays Job arrays have many advantages, including reduced load on the batch system, faster job submission, and easier job management. If you find...

  2. An analysis of job placement variables of foreign national Master of Business Administration (MBA) students

    E-Print Network [OSTI]

    Scism, Darby Claire

    2005-11-01T23:59:59.000Z

    visa issues. Campus career centers need to address the unique needs and concerns of their international student population in order to most effectively assist this select group in their job search. The purpose of this study was to examine the job...

  3. Safety System Oversight Staffing Analysis (Instructions, Blank...

    Office of Environmental Management (EM)

    modifications since changes to the worksheet format may inadvertently change included formula referenced cells. SSO Alternate Staffing Analysis - Instructions SSO Alternate...

  4. FAQS Gap Analysis Qualification Card – Criticality Safety

    Broader source: Energy.gov [DOE]

    Functional Area Qualification Standard Gap Analysis Qualification Cards outline the differences between the last and latest version of the FAQ Standard.

  5. Safety Analysis Of Automated Highway Systems

    E-Print Network [OSTI]

    Leveson, Nancy G.

    1997-01-01T23:59:59.000Z

    Lee. Towards an automated fmea assis- tant. In Applicationsmodes and effects analysis (FMEA) is employed to determineof multiple failures. ) FMEA was developed Potential Part

  6. Safety Analysis for Packaging Steel Banded Wooden Shipping Containers

    SciTech Connect (OSTI)

    FERRELL, P.C.

    2000-12-05T23:59:59.000Z

    This safety analysis report for packaging describes the steel banded wooden shipping containers, which are certified as Type AF packagings. The authorized payload for these containers is unirradiated, slightly enriched, uranium ingots, billets, extrusions, and scrap materials. The amount of uranium in the containers will not exceed the LSA-II material requirements as defined in 49 CFR 173.403.

  7. Safety System Oversight Staffing Analysis- Example

    Broader source: Energy.gov [DOE]

    This Staffing Analysis calculation is completed using an Excel worksheet. Information locations are identified by titles in column or row headings and worksheet locations based on the unmodified blank. Use caution when making worksheet modifications since changes to the worksheet format may inadvertently change included formula referenced cells.

  8. Fuel Storage Facility Final Safety Analysis Report. Revision 1

    SciTech Connect (OSTI)

    Linderoth, C.E.

    1984-03-01T23:59:59.000Z

    The Fuel Storage Facility (FSF) is an integral part of the Fast Flux Test Facility. Its purpose is to provide long-term storage (20-year design life) for spent fuel core elements used to provide the fast flux environment in FFTF, and for test fuel pins, components and subassemblies that have been irradiated in the fast flux environment. This Final Safety Analysis Report (FSAR) and its supporting documentation provides a complete description and safety evaluation of the site, the plant design, operations, and potential accidents.

  9. Nuclear criticality safety tools in the Chernobyl-4 accident analysis

    SciTech Connect (OSTI)

    Landeyro, P.A.

    1988-01-01T23:59:59.000Z

    The collaboration with the Italian Safety Authority (DISP), started in July 1986, has the aim of studying, from a neutronic point of view, the possible initiator event and the accident dynamics in unit four of the Chernobly nuclear power plant. This report was produced within the framework of that collaboration. A main condition of the present work was making use of standard calculational methods employed in nuclear criticality safety analysis. This means that the neutron multiplication factor calculation should be made with the modules and the cross-section libraries of the SCALE system or in any case with some KENO IV version and the burnup calculation with the ORIGEN code.

  10. Safety analysis report for packaging (onsite) multicanister overpack cask

    SciTech Connect (OSTI)

    Edwards, W.S.

    1997-07-14T23:59:59.000Z

    This safety analysis report for packaging (SARP) documents the safety of shipments of irradiated fuel elements in the MUlticanister Overpack (MCO) and MCO Cask for a highway route controlled quantity, Type B fissile package. This SARP evaluates the package during transfers of (1) water-filled MCOs from the K Basins to the Cold Vacuum Drying Facility (CVDF) and (2) sealed and cold vacuum dried MCOs from the CVDF in the 100 K Area to the Canister Storage Building in the 200 East Area.

  11. Style, content and format guide for writing safety analysis documents. Volume 1, Safety analysis reports for DOE nuclear facilities

    SciTech Connect (OSTI)

    Not Available

    1994-06-01T23:59:59.000Z

    The purpose of Volume 1 of this 4-volume style guide is to furnish guidelines on writing and publishing Safety Analysis Reports (SARs) for DOE nuclear facilities at Sandia National Laboratories. The scope of Volume 1 encompasses not only the general guidelines for writing and publishing, but also the prescribed topics/appendices contents along with examples from typical SARs for DOE nuclear facilities.

  12. SCALE 6: Comprehensive Nuclear Safety Analysis Code System

    SciTech Connect (OSTI)

    Bowman, Stephen M [ORNL

    2011-01-01T23:59:59.000Z

    Version 6 of the Standardized Computer Analyses for Licensing Evaluation (SCALE) computer software system developed at Oak Ridge National Laboratory, released in February 2009, contains significant new capabilities and data for nuclear safety analysis and marks an important update for this software package, which is used worldwide. This paper highlights the capabilities of the SCALE system, including continuous-energy flux calculations for processing multigroup problem-dependent cross sections, ENDF/B-VII continuous-energy and multigroup nuclear cross-section data, continuous-energy Monte Carlo criticality safety calculations, Monte Carlo radiation shielding analyses with automated three-dimensional variance reduction techniques, one- and three-dimensional sensitivity and uncertainty analyses for criticality safety evaluations, two- and three-dimensional lattice physics depletion analyses, fast and accurate source terms and decay heat calculations, automated burnup credit analyses with loading curve search, and integrated three-dimensional criticality accident alarm system analyses using coupled Monte Carlo criticality and shielding calculations.

  13. Computational Methods for Sensitivity and Uncertainty Analysis in Criticality Safety

    SciTech Connect (OSTI)

    Broadhead, B.L.; Childs, R.L.; Rearden, B.T.

    1999-09-20T23:59:59.000Z

    Interest in the sensitivity methods that were developed and widely used in the 1970s (the FORSS methodology at ORNL among others) has increased recently as a result of potential use in the area of criticality safety data validation procedures to define computational bias, uncertainties and area(s) of applicability. Functional forms of the resulting sensitivity coefficients can be used as formal parameters in the determination of applicability of benchmark experiments to their corresponding industrial application areas. In order for these techniques to be generally useful to the criticality safety practitioner, the procedures governing their use had to be updated and simplified. This paper will describe the resulting sensitivity analysis tools that have been generated for potential use by the criticality safety community.

  14. PAT-1 safety analysis report addendum.

    SciTech Connect (OSTI)

    Weiner, Ruth F.; Schmale, David T.; Kalan, Robert J.; Akin, Lili A.; Miller, David Russell; Knorovsky, Gerald Albert; Yoshimura, Richard Hiroyuki; Lopez, Carlos; Harding, David Cameron; Jones, Perry L.; Morrow, Charles W.

    2010-09-01T23:59:59.000Z

    The Plutonium Air Transportable Package, Model PAT-1, is certified under Title 10, Code of Federal Regulations Part 71 by the U.S. Nuclear Regulatory Commission (NRC) per Certificate of Compliance (CoC) USA/0361B(U)F-96 (currently Revision 9). The purpose of this SAR Addendum is to incorporate plutonium (Pu) metal as a new payload for the PAT-1 package. The Pu metal is packed in an inner container (designated the T-Ampoule) that replaces the PC-1 inner container. The documentation and results from analysis contained in this addendum demonstrate that the replacement of the PC-1 and associated packaging material with the T-Ampoule and associated packaging with the addition of the plutonium metal content are not significant with respect to the design, operating characteristics, or safe performance of the containment system and prevention of criticality when the package is subjected to the tests specified in 10 CFR 71.71, 71.73 and 71.74.

  15. A Domain-Specific Safety Analysis for Digital Nuclear Plant Protection Systems

    E-Print Network [OSTI]

    A Domain-Specific Safety Analysis for Digital Nuclear Plant Protection Systems Sanghyun Yoon through safety analy- sis is strongly mandated for safety-critical systems. Nuclear plant protection. INTRODUCTION Safety-critical systems (e.g. nuclear power plants and air- planes) require rigorous quality

  16. Safety analysis report for packaging (onsite) sample pig transport system

    SciTech Connect (OSTI)

    MCCOY, J.C.

    1999-03-16T23:59:59.000Z

    This Safety Analysis Report for Packaging (SARP) provides a technical evaluation of the Sample Pig Transport System as compared to the requirements of the U.S. Department of Energy, Richland Operations Office (RL) Order 5480.1, Change 1, Chapter III. The evaluation concludes that the package is acceptable for the onsite transport of Type B, fissile excepted radioactive materials when used in accordance with this document.

  17. Management implementation plan for a safety analysis and review system

    SciTech Connect (OSTI)

    Hulburt, D.A.; Berkey, B.D.

    1981-04-01T23:59:59.000Z

    The US Department of Energy has issued an Order, DOE 5481.1, which establishes uniform requirements for the preparation and review of Safety Analysis for DOE Operations. The Management Implementation Plan specified herein establishes the administrative procedures and technical requirements for implementing DOE 5481.1 to Operations under the cognizance of the Pittsburgh Energy Technology Center. This Implementation Plan is applicable to all present and future Operations under the cognizance of PETC. The Plan identifies those Operations for which DOE 5481.1 is applicable and those Operations for which no further analysis is required because the initial determination and review has concluded that DOE 5481.1 does not apply.

  18. Reactor Accident Analysis Methodology for the Advanced Test Reactor Critical Facility Documented Safety Analysis Upgrade

    SciTech Connect (OSTI)

    Sharp, G.L.; McCracken, R.T.

    2003-05-13T23:59:59.000Z

    The regulatory requirement to develop an upgraded safety basis for a DOE Nuclear Facility was realized in January 2001 by issuance of a revision to Title 10 of the Code of Federal Regulations Section 830 (10 CFR 830). Subpart B of 10 CFR 830, ''Safety Basis Requirements,'' requires a contractor responsible for a DOE Hazard Category 1, 2, or 3 nuclear facility to either submit by April 9, 2001 the existing safety basis which already meets the requirements of Subpart B, or to submit by April 10, 2003 an upgraded facility safety basis that meets the revised requirements. 10 CFR 830 identifies Nuclear Regulatory Commission (NRC) Regulatory Guide 1.70, ''Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants'' as a safe harbor methodology for preparation of a DOE reactor documented safety analysis (DSA). The regulation also allows for use of a graded approach. This report presents the methodology that was developed for preparing the reactor accident analysis portion of the Advanced Test Reactor Critical Facility (ATRC) upgraded DSA. The methodology was approved by DOE for developing the ATRC safety basis as an appropriate application of a graded approach to the requirements of 10 CFR 830.

  19. Reactor Accident Analysis Methodology for the Advanced Test Reactor Critical Facility Documented Safety Analysis Upgrade

    SciTech Connect (OSTI)

    Gregg L. Sharp; R. T. McCracken

    2003-06-01T23:59:59.000Z

    The regulatory requirement to develop an upgraded safety basis for a DOE nuclear facility was realized in January 2001 by issuance of a revision to Title 10 of the Code of Federal Regulations Section 830 (10 CFR 830).1 Subpart B of 10 CFR 830, “Safety Basis Requirements,” requires a contractor responsible for a DOE Hazard Category 1, 2, or 3 nuclear facility to either submit by April 9, 2001 the existing safety basis which already meets the requirements of Subpart B, or to submit by April 10, 2003 an upgraded facility safety basis that meets the revised requirements.1 10 CFR 830 identifies Nuclear Regulatory Commission (NRC) Regulatory Guide 1.70, “Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants”2 as a safe harbor methodology for preparation of a DOE reactor documented safety analysis (DSA). The regulation also allows for use of a graded approach. This report presents the methodology that was developed for preparing the reactor accident analysis portion of the Advanced Test Reactor Critical Facility (ATRC) upgraded DSA. The methodology was approved by DOE for developing the ATRC safety basis as an appropriate application of a graded approach to the requirements of 10 CFR 830.

  20. Job Position Description Job Title: Office Assistant

    E-Print Network [OSTI]

    Moore, Paul A.

    Job Position Description Job Title: Office Assistant A. Main purpose of the job: To assist of Campus Operations. B. Primary responsibilities or key duties of the job (tasks performed regularly

  1. Job Position Description Job Title: Locksmith Assistant

    E-Print Network [OSTI]

    Moore, Paul A.

    Job Position Description Job Title: Locksmith Assistant A. Main purpose of the job: Assist responsibilities or key duties of the job (tasks performed regularly): 1. Perform lock changes in all facilities

  2. Job Position Description Job Title: Custodial Worker

    E-Print Network [OSTI]

    Moore, Paul A.

    Job Position Description Job Title: Custodial Worker A. Main purpose of the job: Clean academic buildings and/or residence halls. B. Primary responsibilities or key duties of the job (tasks

  3. Mixed Waste Management Facility Preliminary Safety Analysis Report. Chapters 1 to 20

    SciTech Connect (OSTI)

    Not Available

    1994-09-01T23:59:59.000Z

    This document provides information on waste management practices, occupational safety, and a site characterization of the Lawrence Livermore National Laboratory. A facility description, safety engineering analysis, mixed waste processing techniques, and auxiliary support systems are included.

  4. Safety Analysis of Requirements for a Product Family Robyn R. Lutz \\Lambda

    E-Print Network [OSTI]

    Lutz, Robyn R.

    safety analysis techniques (safety checklist, forward and backward search) can be combined to evaluate specification. The major contribution of this work is to de­ scribe a way in which existing and well­documented

  5. Multifamily Energy Auditor Job/Task Analysis and Report: September 2013

    SciTech Connect (OSTI)

    Owens, C. M.

    2013-09-01T23:59:59.000Z

    The development of job/task analyses (JTAs) is one of three components of the Guidelines for Home Energy Professionals project and will allow industry to develop training resources, quality assurance protocols, accredited training programs, and professional certifications. The Multifamily Energy Auditor JTA identifies and catalogs all of the tasks performed by multifamily energy auditors, as well as the knowledge, skills, and abilities (KSAs) needed to perform the identified tasks.

  6. Multifamily Quality Control Inspector Job/Task Analysis and Report: September 2013

    SciTech Connect (OSTI)

    Owens, C. M.

    2013-09-01T23:59:59.000Z

    The development of job/task analyses (JTAs) is one of three components of the Guidelines for Home Energy Professionals project and will allow industry to develop training resources, quality assurance protocols, accredited training programs, and professional certifications. The Multifamily Quality Control Inspector JTA identifies and catalogs all of the tasks performed by multifamily quality control inspectors, as well as the knowledge, skills, and abilities (KSAs) needed to perform the identified tasks.

  7. Multifamily Retrofit Project Manager Job/Task Analysis and Report: September 2013

    SciTech Connect (OSTI)

    Owens, C. M.

    2013-09-01T23:59:59.000Z

    The development of job/task analyses (JTAs) is one of three components of the Guidelines for Home Energy Professionals project and will allow industry to develop training resources, quality assurance protocols, accredited training programs, and professional certifications. The Multifamily Retrofit Project Manager JTA identifies and catalogs all of the tasks performed by multifamily retrofit project managers, as well as the knowledge, skills, and abilities (KSAs) needed to perform the identified tasks.

  8. Multifamily Building Operator Job/Task Analysis and Report: September 2013

    SciTech Connect (OSTI)

    Owens, C. M.

    2013-09-01T23:59:59.000Z

    The development of job/task analyses (JTAs) is one of three components of the Guidelines for Home Energy Professionals project and will allow industry to develop training resources, quality assurance protocols, accredited training programs, and professional certifications. The Multifamily Building Operator JTA identifies and catalogs all of the tasks performed by multifamily building operators, as well as the knowledge, skills, and abilities (KSAs) needed to perform the identified tasks.

  9. Hopper Job Size Charts

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

    Job Size Charts Hopper Job Size Charts Fractional Jobs The following charts show the fraction of hours used on Hopper in each of five job-core-size bins: 2014 Usage by Job Size...

  10. Edison Job Size Charts

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

    Job Size Charts Edison Job Size Charts Fraction of Hours Used per Job Size This chart shows the fraction of hours used on Edison in each of 5 job-core-size bins. 2015 Usage by Job...

  11. Page 1 of 11 Summary of a Revised Safety Impact Analysis for the Lead Shielded Container Assembly

    E-Print Network [OSTI]

    -individual from previous analyses performed to support the WIPP Documented Safety Analysis (DSA). The revised

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

    SciTech Connect (OSTI)

    Not Available

    1994-06-20T23:59:59.000Z

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

  13. Fast Flux Test Facility final safety analysis report. Amendment 73

    SciTech Connect (OSTI)

    Gantt, D.A.

    1993-08-01T23:59:59.000Z

    This report provides Final Safety Analysis Report (FSAR) Amendment 73 for incorporation into the Fast Flux Test Facility (FFTR) FSAR set. This page change incorporates Engineering Change Notices (ECNs) issued subsequent to Amendment 72 and approved for incorparoration before May 6, 1993. These changes include: Chapter 3, design criteria structures, equipment, and systems; chapter 5B, reactor coolant system; chapter 7, instrumentation and control systems; chapter 9, auxiliary systems; chapter 11, reactor refueling system; chapter 12, radiation protection and waste management; chapter 13, conduct of operations; chapter 17, technical specifications; chapter 20, FFTF criticality specifications; appendix C, local fuel failure events; and appendix Fl, operation at 680{degrees}F inlet temperature.

  14. DOE's Approach to Nuclear Facility Safety Analysis and Management

    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

  15. Safety and Security Policy Jobs

    Office of Science (SC) Website

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron4(SC) Mapping the ImpactSC Correspondence Control

  16. Job/Task Analysis: Enhancing the Commercial Building Workforce Through the Development of Foundational Materials; Preprint

    SciTech Connect (OSTI)

    Studer, D.; Kemkar, S.

    2012-09-01T23:59:59.000Z

    For many commercial building operation job categories, industry consensus has not been reached on the knowledge, skills, and abilities that practitioners should possess. The goal of this guidance is to help streamline the minimum competencies taught or tested by organizations catering to building operations and maintenance personnel while providing a basis for developing and comparing new and existing training programs in the commercial building sector. The developed JTAs will help individuals identify opportunities to enhance their professional skills, enable industry to identify an appropriately skilled workforce, and allow training providers to ensure that they are providing the highest quality product possible.

  17. Job Creation Analysis in the Hydrogen and Fuel Cell Industry | Department

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't YourTransport(FactDepartment ofLetter Report: I11IG002RTC3 | of EnergyJenny HakunJob Creationof

  18. PUB-3000 Chapter 32 | JOB HAZARDS ANALYSIS | REV'D 08/13

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What's Possible for RenewableSpeedingBiomassPPPO Website Directory PPPOLarson.Cheryl A -Chapter 32 JOB

  19. Franklin Job Completion Analysis Yun (Helen) He, Hwa-Chun Wendy Lin, and

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOEThe Bonneville Power AdministrationField8,Dist.Newof Energy Forrestal GarageD.Charge rateFranklinFranklinJob

  20. Combination of Safety and Security Analysis -Finding Security Problems That Threaten The

    E-Print Network [OSTI]

    Boyer, Edmond

    -physical Systems) of the 32nd International Conference on Computer Safety, Reliability and Security, France (2013Combination of Safety and Security Analysis - Finding Security Problems That Threaten The Safety of a System Max Steiner and Peter Liggesmeyer AG Software Engineering: Dependability, TU Kaiserslautern

  1. Documented Safety Analysis for the B695 Segment

    SciTech Connect (OSTI)

    Laycak, D

    2008-09-11T23:59:59.000Z

    This Documented Safety Analysis (DSA) was prepared for the Lawrence Livermore National Laboratory (LLNL) Building 695 (B695) Segment of the Decontamination and Waste Treatment Facility (DWTF). The report provides comprehensive information on design and operations, including safety programs and safety structures, systems and components to address the potential process-related hazards, natural phenomena, and external hazards that can affect the public, facility workers, and the environment. Consideration is given to all modes of operation, including the potential for both equipment failure and human error. The facilities known collectively as the DWTF are used by LLNL's Radioactive and Hazardous Waste Management (RHWM) Division to store and treat regulated wastes generated at LLNL. RHWM generally processes low-level radioactive waste with no, or extremely low, concentrations of transuranics (e.g., much less than 100 nCi/g). Wastes processed often contain only depleted uranium and beta- and gamma-emitting nuclides, e.g., {sup 90}Sr, {sup 137}Cs, or {sup 3}H. The mission of the B695 Segment centers on container storage, lab-packing, repacking, overpacking, bulking, sampling, waste transfer, and waste treatment. The B695 Segment is used for storage of radioactive waste (including transuranic and low-level), hazardous, nonhazardous, mixed, and other waste. Storage of hazardous and mixed waste in B695 Segment facilities is in compliance with the Resource Conservation and Recovery Act (RCRA). LLNL is operated by the Lawrence Livermore National Security, LLC, for the Department of Energy (DOE). The B695 Segment is operated by the RHWM Division of LLNL. Many operations in the B695 Segment are performed under a Resource Conservation and Recovery Act (RCRA) operation plan, similar to commercial treatment operations with best demonstrated available technologies. The buildings of the B695 Segment were designed and built considering such operations, using proven building systems, and keeping them as simple as possible while complying with industry standards and institutional requirements. No operations to be performed in the B695 Segment or building system are considered to be complex. No anticipated future change in the facility mission is expected to impact the extent of safety analysis documented in this DSA.

  2. A Conceptual Framework for Semantic Case-based Safety Analysis Olawande Daramola, Tor Stlhane

    E-Print Network [OSTI]

    .biffl}@tuwien.ac.at Abstract Hazard and Operability (HAZOP) Analysis and Fail- ure Mode and Effect Analysis (FMEA) are among-based framework for safety analy- sis, which facilitates the reuse of previous HAZOP and FMEA experiences in order application. Key words: Safety analysis, HAZOP, FMEA, ontology, requirements, case-based reasoning, natural

  3. Safety analysis report for packaging (Onsite) for the Hanford Ecorok packaging

    SciTech Connect (OSTI)

    Mercado, M.S.

    1996-02-23T23:59:59.000Z

    This safety analysis report for packaging approves the Hanford Ecorok packaging for shipping contaminated water purification filters from K Basins to the Central Waste Complex.

  4. Canister storage building (CSB) safety analysis report phase 3: Safety analysis documentation supporting CSB construction

    SciTech Connect (OSTI)

    Garvin, L.J.

    1997-04-28T23:59:59.000Z

    The Canister Storage Building (CSB) will be constructed in the 200 East Area of the U.S. Department of Energy (DOE) Hanford Site. The CSB will be used to stage and store spent nuclear fuel (SNF) removed from the Hanford Site K Basins. The objective of this chapter is to describe the characteristics of the site on which the CSB will be located. This description will support the hazard analysis and accident analyses in Chapter 3.0. The purpose of this report is to provide an evaluation of the CSB design criteria, the design's compliance with the applicable criteria, and the basis for authorization to proceed with construction of the CSB.

  5. Job or Work Formulas

    E-Print Network [OSTI]

    Bailey, Charlotte M

    2014-09-16T23:59:59.000Z

    Job or Work Problems. (Needed equations or formulas). Worker's rate = 1 total time alone. Examples: Joe completes a job in 11 hours; his rate is job/hour.

  6. Documented Safety Analysis for the Waste Storage Facilities

    SciTech Connect (OSTI)

    Laycak, D

    2008-06-16T23:59:59.000Z

    This documented safety analysis (DSA) for the Waste Storage Facilities was developed in accordance with 10 CFR 830, Subpart B, 'Safety Basis Requirements', and utilizes the methodology outlined in DOE-STD-3009-94, Change Notice 3. The Waste Storage Facilities consist of Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area portion of the DWTF complex. These two areas are combined into a single DSA, as their functions as storage for radioactive and hazardous waste are essentially identical. The B695 Segment of DWTF is addressed under a separate DSA. This DSA provides a description of the Waste Storage Facilities and the operations conducted therein; identification of hazards; analyses of the hazards, including inventories, bounding releases, consequences, and conclusions; and programmatic elements that describe the current capacity for safe operations. The mission of the Waste Storage Facilities is to safely handle, store, and treat hazardous waste, transuranic (TRU) waste, low-level waste (LLW), mixed waste, combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL (as well as small amounts from other DOE facilities).

  7. Documented Safety Analysis for the Waste Storage Facilities March 2010

    SciTech Connect (OSTI)

    Laycak, D T

    2010-03-05T23:59:59.000Z

    This Documented Safety Analysis (DSA) for the Waste Storage Facilities was developed in accordance with 10 CFR 830, Subpart B, 'Safety Basis Requirements,' and utilizes the methodology outlined in DOE-STD-3009-94, Change Notice 3. The Waste Storage Facilities consist of Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area portion of the DWTF complex. These two areas are combined into a single DSA, as their functions as storage for radioactive and hazardous waste are essentially identical. The B695 Segment of DWTF is addressed under a separate DSA. This DSA provides a description of the Waste Storage Facilities and the operations conducted therein; identification of hazards; analyses of the hazards, including inventories, bounding releases, consequences, and conclusions; and programmatic elements that describe the current capacity for safe operations. The mission of the Waste Storage Facilities is to safely handle, store, and treat hazardous waste, transuranic (TRU) waste, low-level waste (LLW), mixed waste, combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL (as well as small amounts from other DOE facilities).

  8. Simplifying documentation while approaching site closure: integrated health & safety plans as documented safety analysis

    SciTech Connect (OSTI)

    Brown, Tulanda

    2003-06-01T23:59:59.000Z

    At the Fernald Closure Project (FCP) near Cincinnati, Ohio, environmental restoration activities are supported by Documented Safety Analyses (DSAs) that combine the required project-specific Health and Safety Plans, Safety Basis Requirements (SBRs), and Process Requirements (PRs) into single Integrated Health and Safety Plans (I-HASPs). By isolating any remediation activities that deal with Enriched Restricted Materials, the SBRs and PRs assure that the hazard categories of former nuclear facilities undergoing remediation remain less than Nuclear. These integrated DSAs employ Integrated Safety Management methodology in support of simplified restoration and remediation activities that, so far, have resulted in the decontamination and demolition (D&D) of over 150 structures, including six major nuclear production plants. This paper presents the FCP method for maintaining safety basis documentation, using the D&D I-HASP as an example.

  9. Safety analysis report for packaging (onsite) doorstop samplecarrier system

    SciTech Connect (OSTI)

    Obrien, J.H.

    1997-02-24T23:59:59.000Z

    The Doorstop Sample Carrier System consists of a Type B certified N-55 overpack, U.S. Department of Transportation (DOT) specification or performance-oriented 208-L (55-gal) drum (DOT 208-L drum), and Doorstop containers. The purpose of the Doorstop Sample Carrier System is to transport samples onsite for characterization. This safety analysis report for packaging (SARP) provides the analyses and evaluation necessary to demonstrate that the Doorstop Sample Carrier System meets the requirements and acceptance criteria for both Hanford Site normal transport conditions and accident condition events for a Type B package. This SARP also establishes operational, acceptance, maintenance, and quality assurance (QA) guidelines to ensure that the method of transport for the Doorstop Sample Carrier System is performed safely in accordance with WHC-CM-2-14, Hazardous Material Packaging and Shipping.

  10. Planning Document for an NBSR Conversion Safety Analysis Report

    SciTech Connect (OSTI)

    Diamond D. J.; Baek J.; Hanson, A.L.; Cheng, L-Y.; Brown, N.; Cuadra, A.

    2013-09-25T23:59:59.000Z

    The NIST Center for Neutron Research (NCNR) is a reactor-laboratory complex providing the National Institute of Standards and Technology (NIST) and the nation with a world-class facility for the performance of neutron-based research. The heart of this facility is the National Bureau of Standards Reactor (NBSR). The NBSR is a heavy water moderated and cooled reactor operating at 20 MW. It is fueled with high-enriched uranium (HEU) fuel elements. A Global Threat Reduction Initiative (GTRI) program is underway to convert the reactor to low-enriched uranium (LEU) fuel. This program includes the qualification of the proposed fuel, uranium and molybdenum alloy foil clad in an aluminum alloy, and the development of the fabrication techniques. This report is a planning document for the conversion Safety Analysis Report (SAR) that would be submitted to, and approved by, the Nuclear Regulatory Commission (NRC) before the reactor could be converted.This report follows the recommended format and content from the NRC codified in NUREG-1537, “Guidelines for Preparing and Reviewing Applications for the Licensing of Non-power Reactors,” Chapter 18, “Highly Enriched to Low-Enriched Uranium Conversions.” The emphasis herein is on the SAR chapters that require significant changes as a result of conversion, primarily Chapter 4, Reactor Description, and Chapter 13, Safety Analysis. The document provides information on the proposed design for the LEU fuel elements and identifies what information is still missing. This document is intended to assist ongoing fuel development efforts, and to provide a platform for the development of the final conversion SAR. This report contributes directly to the reactor conversion pillar of the GTRI program, but also acts as a boundary condition for the fuel development and fuel fabrication pillars.

  11. Job Arrays

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)Integrated Codes |Is Your Home as Ready for(SC) Jetting into theJieJob Arrays Job

  12. Submitting Jobs

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of ScienceandMesa del SolStrengthening a solid ... StrengtheningLabSubmitting Jobs Submitting Jobs

  13. PDSF Job Efficiency

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

    Optimization Running Jobs Efficiently Running Jobs Efficiently Job Efficiency A job's efficiency is the ratio of its CPU time to the actual time it took to run, i.e., cputime ...

  14. Where are the Academic Jobs? Interactive Exploration of Job Advertisements in Geospatial and Topical Space

    E-Print Network [OSTI]

    Menczer, Filippo

    Data Preparation and Analysis NNature.com Job Postings Location Text Description Levels on Geospatial Map LevelsWhere are the Academic Jobs? Interactive Exploration of Job Advertisements in Geospatial of such data can: ­ provide overviews and details of complex phenomena,p p p , ­ facilitate trend analysis

  15. TESEC 2001, Genova, Italy ADVANCED TECHNIQUES FOR SAFETY ANALYSIS APPLIED TO

    E-Print Network [OSTI]

    Tronci, Enrico

    TESEC 2001, Genova, Italy 1 ADVANCED TECHNIQUES FOR SAFETY ANALYSIS APPLIED TO THE GAS TURBINE for safety analysis of complex computer based systems. Such approaches are applied to the gas turbine control and electrical power supply of the centre of ENEA CR Casaccia. The plant is based on a small gas turbine and has

  16. Optimization of Lyapunov invariants in analysis and implementation of safety-critical software systems

    E-Print Network [OSTI]

    Roozbehani, Mardavij

    2008-01-01T23:59:59.000Z

    This dissertation contributes to two major research areas in safety-critical software systems, namely, software analysis, and software implementation. In reference to the software analysis problem, the main contribution ...

  17. Quantitative Phenomena Identification and Ranking Table (QPIRT) for Reactor Safety Analysis

    E-Print Network [OSTI]

    Yurko, Joseph P.

    Next generation reactor safety analysis codes are intended to make use of advanced numerical methods and higher fidelity models with built-in sensitivity analysis (SA) and uncertainty quantification (UQ) [1]. However, due ...

  18. Interface design of VSOP'94 computer code for safety analysis

    SciTech Connect (OSTI)

    Natsir, Khairina, E-mail: yenny@batan.go.id; Andiwijayakusuma, D.; Wahanani, Nursinta Adi [Center for Development of Nuclear Informatics - National Nuclear Energy Agency, PUSPIPTEK, Serpong, Tangerang, Banten (Indonesia); Yazid, Putranto Ilham [Center for Nuclear Technology, Material and Radiometry- National Nuclear Energy Agency, Jl. Tamansari No.71, Bandung 40132 (Indonesia)

    2014-09-30T23:59:59.000Z

    Today, most software applications, also in the nuclear field, come with a graphical user interface. VSOP'94 (Very Superior Old Program), was designed to simplify the process of performing reactor simulation. VSOP is a integrated code system to simulate the life history of a nuclear reactor that is devoted in education and research. One advantage of VSOP program is its ability to calculate the neutron spectrum estimation, fuel cycle, 2-D diffusion, resonance integral, estimation of reactors fuel costs, and integrated thermal hydraulics. VSOP also can be used to comparative studies and simulation of reactor safety. However, existing VSOP is a conventional program, which was developed using Fortran 65 and have several problems in using it, for example, it is only operated on Dec Alpha mainframe platforms and provide text-based output, difficult to use, especially in data preparation and interpretation of results. We develop a GUI-VSOP, which is an interface program to facilitate the preparation of data, run the VSOP code and read the results in a more user friendly way and useable on the Personal 'Computer (PC). Modifications include the development of interfaces on preprocessing, processing and postprocessing. GUI-based interface for preprocessing aims to provide a convenience way in preparing data. Processing interface is intended to provide convenience in configuring input files and libraries and do compiling VSOP code. Postprocessing interface designed to visualized the VSOP output in table and graphic forms. GUI-VSOP expected to be useful to simplify and speed up the process and analysis of safety aspects.

  19. Criticality safety analysis on fissile materials in Fukushima reactor cores

    SciTech Connect (OSTI)

    Liu, Xudong; Lemaitre-Xavier, E.; Ahn, Joonhong [Department of Nuclear Engineering, University of California, Berkeley, Berkeley, CA 94720 (United States); Hirano, Fumio [Japan Atomic Energy Agency, Geological Isolation Research and Development Directorate, Tokai-mura, Ibaraki 319-1194 (Japan)

    2013-07-01T23:59:59.000Z

    The present study focuses on the criticality analysis for geological disposal of damaged fuels from Fukushima reactor cores. Starting from the basic understanding of behaviors of plutonium and uranium, a scenario sequence for criticality event is considered. Due to the different mobility of plutonium and uranium in geological formations, the criticality safety is considered in two parts: (1) near-field plutonium system and (2) far-field low enriched uranium (LEU) system. For the near-field plutonium system, a mathematical analysis for pure-solute transport was given, assuming a particular buffer material and waste form configuration. With the transport and decay of plutonium accounted, the critical mass of plutonium was compared with the initial load of a single canister. Our calculation leads us to the conclusion that our system with the initial loading being the average mass of plutonium in an assembly just before the accident is very unlikely to become critical over time. For the far-field LEU system, due to the uncertainties in the geological and geochemical conditions, calculations were made in a parametric space that covers the variation of material compositions and different geometries. Results show that the LEU system could not remain sub-critical within the entire parameter space assumed, although in the iron-rich rock, the neutron multiplicity is significantly reduced.

  20. Development of an auditable safety analysis in support of a radiological facility classification

    SciTech Connect (OSTI)

    Kinney, M.D. [Roy F. Weston, Inc., Rockville, MD (United States); Young, B. [Dept. of Energy, Albuquerque, NM (United States)

    1995-03-01T23:59:59.000Z

    In recent years, U.S. Department of Energy (DOE) facilities commonly have been classified as reactor, non-reactor nuclear, or nuclear facilities. Safety analysis documentation was prepared for these facilities, with few exceptions, using the requirements in either DOE Order 5481.1B, Safety Analysis and Review System; or DOE Order 5480.23, Nuclear Safety Analysis Reports. Traditionally, this has been accomplished by development of an extensive Safety Analysis Report (SAR), which identifies hazards, assesses risks of facility operation, describes and analyzes adequacy of measures taken to control hazards, and evaluates potential accidents and their associated risks. This process is complicated by analysis of secondary hazards and adequacy of backup (redundant) systems. The traditional SAR process is advantageous for DOE facilities with appreciable hazards or operational risks. SAR preparation for a low-risk facility or process can be cost-prohibitive and quite challenging because conventional safety analysis protocols may not readily be applied to a low-risk facility. The DOE Office of Environmental Restoration and Waste Management recognized this potential disadvantage and issued an EM limited technical standard, No. 5502-94, Hazard Baseline Documentation. This standard can be used for developing documentation for a facility classified as radiological, including preparation of an auditable (defensible) safety analysis. In support of the radiological facility classification process, the Uranium Mill Tailings Remedial Action (UMTRA) Project has developed an auditable safety analysis document based upon the postulation criteria and hazards analysis techniques defined in DOE Order 5480.23.

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

    SciTech Connect (OSTI)

    NONE

    1995-09-01T23:59:59.000Z

    The Baseline Safety Analysis File (BSAF) is a facility safety reference document for the Idaho National Engineering Laboratory (INEL) environmental restoration activities. The BSAF contains information and guidance for safety analysis documentation required by the U.S. Department of Energy (DOE) for environmental restoration (ER) activities, including: Characterization of potentially contaminated sites. Remedial investigations to identify and remedial actions to clean up existing and potential releases from inactive waste sites Decontamination and dismantlement of surplus facilities. The information is INEL-specific and is in the format required by DOE-EM-STD-3009-94, Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports. An author of safety analysis documentation need only write information concerning that activity and refer to BSAF for further information or copy applicable chapters and sections. The information and guidance provided are suitable for: {sm_bullet} Nuclear facilities (DOE Order 5480-23, Nuclear Safety Analysis Reports) with hazards that meet the Category 3 threshold (DOE-STD-1027-92, Hazard Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports) {sm_bullet} Radiological facilities (DOE-EM-STD-5502-94, Hazard Baseline Documentation) Nonnuclear facilities (DOE-EM-STD-5502-94) that are classified as {open_quotes}low{close_quotes} hazard facilities (DOE Order 5481.1B, Safety Analysis and Review System). Additionally, the BSAF could be used as an information source for Health and Safety Plans and for Safety Analysis Reports (SARs) for nuclear facilities with hazards equal to or greater than the Category 2 thresholds, or for nonnuclear facilities with {open_quotes}moderate{close_quotes} or {open_quotes}high{close_quotes} hazard classifications.

  2. Providing Nuclear Criticality Safety Analysis Education through Benchmark Experiment Evaluation

    SciTech Connect (OSTI)

    John D. Bess; J. Blair Briggs; David W. Nigg

    2009-11-01T23:59:59.000Z

    One of the challenges that today's new workforce of nuclear criticality safety engineers face is the opportunity to provide assessment of nuclear systems and establish safety guidelines without having received significant experience or hands-on training prior to graduation. Participation in the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and/or the International Reactor Physics Experiment Evaluation Project (IRPhEP) provides students and young professionals the opportunity to gain experience and enhance critical engineering skills.

  3. Packaging Review Guide for Reviewing Safety Analysis Reports for Packagings

    SciTech Connect (OSTI)

    DiSabatino, A; Biswas, D; DeMicco, M; Fisher, L E; Hafner, R; Haslam, J; Mok, G; Patel, C; Russell, E

    2007-04-12T23:59:59.000Z

    This Packaging Review Guide (PRG) provides guidance for Department of Energy (DOE) review and approval of packagings to transport fissile and Type B quantities of radioactive material. It fulfills, in part, the requirements of DOE Order 460.1B for the Headquarters Certifying Official to establish standards and to provide guidance for the preparation of Safety Analysis Reports for Packagings (SARPs). This PRG is intended for use by the Headquarters Certifying Official and his or her review staff, DOE Secretarial offices, operations/field offices, and applicants for DOE packaging approval. This PRG is generally organized at the section level in a format similar to that recommended in Regulatory Guide 7.9 (RG 7.9). One notable exception is the addition of Section 9 (Quality Assurance), which is not included as a separate chapter in RG 7.9. Within each section, this PRG addresses the technical and regulatory bases for the review, the manner in which the review is accomplished, and findings that are generally applicable for a package that meets the approval standards. This Packaging Review Guide (PRG) provides guidance for DOE review and approval of packagings to transport fissile and Type B quantities of radioactive material. It fulfills, in part, the requirements of DOE O 460.1B for the Headquarters Certifying Official to establish standards and to provide guidance for the preparation of Safety Analysis Reports for Packagings (SARPs). This PRG is intended for use by the Headquarters Certifying Official and his review staff, DOE Secretarial offices, operations/field offices, and applicants for DOE packaging approval. The primary objectives of this PRG are to: (1) Summarize the regulatory requirements for package approval; (2) Describe the technical review procedures by which DOE determines that these requirements have been satisfied; (3) Establish and maintain the quality and uniformity of reviews; (4) Define the base from which to evaluate proposed changes in scope and requirements of reviews; and (5) Provide the above information to DOE organizations, contractors, other government agencies, and interested members of the general public. This PRG was originally published in September 1987. Revision 1, issued in October 1988, added new review sections on quality assurance and penetrations through the containment boundary, along with a few other items. Revision 2 was published October 1999. Revision 3 of this PRG is a complete update, and supersedes Revision 2 in its entirety.

  4. A risk-informed approach to safety margins analysis

    SciTech Connect (OSTI)

    Curtis Smith; Diego Mandelli

    2013-07-01T23:59:59.000Z

    The Risk Informed Safety Margins Characterization (RISMC) Pathway is a systematic approach developed to characterize and quantify safety margins of nuclear power plant structures, systems and components. The model has been tested on the Advanced Test Reactor (ATR) at Idaho National Lab.

  5. PART I: JOB DESCRIPTION Weighted Job Questionnaire (WJQ) Custom

    E-Print Network [OSTI]

    PART I: JOB DESCRIPTION Weighted Job Questionnaire (WJQ) Custom Department Name: Position Number WEIGHTED JOB QUESTIONNAIRE (WJQ) CUSTOM PARTI: JOB DESCRIPTION 1. POSITION IDENTIFICATION Department

  6. Off-the-Job Injuries are on the Rise- and Costly

    Broader source: Energy.gov [DOE]

    Do you have an off-the-job safety program? Should you? The findings from a National Safety Council survey suggest that off-the-job injuries cost companies and society in general as much, if not more than on-the-job injuries!

  7. Software safety analysis of function block diagrams using fault trees , Junbeom Yoob,*, Sungdeok Chab

    E-Print Network [OSTI]

    the proposed approach against the one manually prepared by nuclear safety engineers. q 2004 Elsevier Ltd. AllSoftware safety analysis of function block diagrams using fault trees Younju Oha , Junbeom Yoob Institute of Science and Technology (KAIST) and AITrc/SPIC/IIRTRC, 373­1, Gusong­dong, Yuseong-gu, Daeje

  8. Application of System-Theoretic Process Analysis to Engineered Safety Features-Component Control System

    E-Print Network [OSTI]

    techniques identify. 1. Introduction Recent developments in safety-critical systems, such as nuclear powerC5.7 Application of System-Theoretic Process Analysis to Engineered Safety Features of Korea b,c Korea Atomic Energy Research Institute, 150 Deokjin, Yuseong Daejeon, 305-335, Republic

  9. Safety Analysis Using Coloured Petri Nets Seung Mo Cho, Hyoung Seok Hong, and Sung Deok Cha

    E-Print Network [OSTI]

    as an example. 1. Introduction Software control in safety-critical systems such as aerospace, military, nuclearSafety Analysis Using Coloured Petri Nets Seung Mo Cho, Hyoung Seok Hong, and Sung Deok Cha Department of Computer Science Korea Advanced Institute of Science and Technology (KAIST) 373-1, Kusong

  10. Accident Analysis and Prevention 36 (2004) 933946 Freeway safety as a function of traffic flow

    E-Print Network [OSTI]

    Detwiler, Russell

    2004-01-01T23:59:59.000Z

    Accident Analysis and Prevention 36 (2004) 933­946 Freeway safety as a function of traffic flow of strong relationships between traffic flow conditions and the likelihood of traffic accidents (crashes reserved. Keywords: Traffic safety; Accident rates; Traffic flow; Loop detectors; Speed; Traffic density

  11. Human-robot interactions: model-based risk analysis and safety case construction

    E-Print Network [OSTI]

    Guiochet, Jérémie

    Human-robot interactions: model-based risk analysis and safety case construction Quynh Anh DO HOANG potential threats related to physical human-robot interactions and to assess the associated risks that might affect safety and dependability. Because of the complexity of human-robot interactions, rigorous

  12. Internet Resources for Job Safety and Health Compiled by Tim Morse, Ph.D., at the ErgoCenter at the University of Connecticut Health Center

    E-Print Network [OSTI]

    Oliver, Douglas L.

    topics. www.epa.gov http://www.epa.gov/iaq/homes/index.html The North Carolina Occupational Safety://www.turi.org. UMass-Lowell's Center for Sustainable Production has information on changing chemical policies at http

  13. A semiotic analysis of biotechnology and food safety photographs 

    E-Print Network [OSTI]

    Norwood, Jennifer Lynn

    2006-04-12T23:59:59.000Z

    This study evaluated photographs used in Time, Newsweek, and U.S. News and World Report in stories about biotechnology and food safety issues from the years 2000 and 2001. This study implemented a semiotic methodology to ...

  14. CRAD, New Nuclear Facility Documented Safety Analysis and Technical...

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

    Technical Safety Requirements - December 2, 2014 (EA CRAD 31-07, Rev. 0) More Documents & Publications CRAD, Nuclear Reactor Facility Operations - December 4, 2014 (EA CRAD 31-08...

  15. Aspects of environmental and safety analysis of fusion reactors

    E-Print Network [OSTI]

    Kazimi, Mujid S.

    1977-01-01T23:59:59.000Z

    This report summarizes the progress made between October 1976 and September 1977 in studies of some environmental and safety considerations in fusion reactor plants. A methodology to assess the admissible occurrence rate ...

  16. Markov Modeling with Soft Aggregation for Safety and Decision Analysis

    SciTech Connect (OSTI)

    COOPER,J. ARLIN

    1999-09-01T23:59:59.000Z

    The methodology in this report improves on some of the limitations of many conventional safety assessment and decision analysis methods. A top-down mathematical approach is developed for decomposing systems and for expressing imprecise individual metrics as possibilistic or fuzzy numbers. A ''Markov-like'' model is developed that facilitates combining (aggregating) inputs into overall metrics and decision aids, also portraying the inherent uncertainty. A major goal of Markov modeling is to help convey the top-down system perspective. One of the constituent methodologies allows metrics to be weighted according to significance of the attribute and aggregated nonlinearly as to contribution. This aggregation is performed using exponential combination of the metrics, since the accumulating effect of such factors responds less and less to additional factors. This is termed ''soft'' mathematical aggregation. Dependence among the contributing factors is accounted for by incorporating subjective metrics on ''overlap'' of the factors as well as by correspondingly reducing the overall contribution of these combinations to the overall aggregation. Decisions corresponding to the meaningfulness of the results are facilitated in several ways. First, the results are compared to a soft threshold provided by a sigmoid function. Second, information is provided on input ''Importance'' and ''Sensitivity,'' in order to know where to place emphasis on considering new controls that may be necessary. Third, trends in inputs and outputs are tracked in order to obtain significant information% including cyclic information for the decision process. A practical example from the air transportation industry is used to demonstrate application of the methodology. Illustrations are given for developing a structure (along with recommended inputs and weights) for air transportation oversight at three different levels, for developing and using cycle information, for developing Importance and Sensitivity measures for soil aggregation, for developing dependence methodology, for constructing early alert logic, for tracking trends, for relating the Markov model to other (e.g., Reason) models, for developing and demonstrating rudimentary laptop software, and for developing an input/output display methodology.

  17. New Methods and Tools to Perform Safety Analysis within RISMC

    SciTech Connect (OSTI)

    Diego Mandelli; Curtis Smith; Cristian Rabiti; Andrea Alfonsi; Robert Kinoshita; Joshua Cogliati

    2013-11-01T23:59:59.000Z

    The Risk Informed Safety Margins Characterization (RISMC) Pathway uses a systematic approach developed to characterize and quantify safety margins of nuclear power plant structures, systems and components. What differentiates the RISMC approach from traditional probabilistic risk assessment (PRA) is the concept of safety margin. In PRA, a safety metric such as core damage frequency (CDF) is generally estimated using static fault-tree and event-tree models. However, it is not possible to estimate how close we are to physical safety limits (say peak clad temperature) for most accident sequences described in the PRA. In the RISMC approach, what we want to understand is not just the frequency of an event like core damage, but how close we are (or not) to this event and how we might increase our safety margin through margin management strategies in a Dynamic PRA (DPRA) fashion. This paper gives an overview of methods that are currently under development at the Idaho National Laboratory (INL) with the scope of advance the current state of the art of dynamic PRA.

  18. Job Opportunities

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOnItemResearch > The Energy Materials Center atdiffusivitiesTechnologies |Job

  19. Budget Jobs

    Office of Science (SC) Website

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron4 Self-Scrubbing:,,of Science (SC) BESAC HomeU.S.budget/about/jobs/

  20. Careers, Jobs

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOnItem NotEnergy,ARMForms About Batteriesmetal-organic frameworks |A photo of aJobs

  1. Overview of the preliminary safety analysis of the National Ignition Facility

    SciTech Connect (OSTI)

    Brereton, S.; McLouth, L.; Odell, B. [Lawrence Livermore National Lab., CA (United States)] [and others] [Lawrence Livermore National Lab., CA (United States); and others

    1997-06-01T23:59:59.000Z

    The National Ignition Facility (NIF) is a proposed U.S. Department of Energy inertial confinement laser fusion facility. The candidate sites for locating the NIF are: Los Alamos National Laboratory, Sandia National Laboratory, New Mexico, the Nevada Test Site, and Lawrence Livermore National Laboratory (LLNL), the preferred site. The NIF will operate by focusing 192 individual laser beams onto a tiny deuterium-tritium target located at the center of a spherical target chamber. The NIF has been classified as a low hazard, radiological facility on the basis of a preliminary hazards analysis and according to the DOE methodology for facility classification. This requires that a safety analysis report be prepared under DOE Order 5481.1B, Safety Analysis and Review System. A Preliminary Safety Analysis Report (PSAR) has been approved, which documents and evaluates the safety issues associated with the construction, operation, and decommissioning of the NIF. 10 refs., 6 figs., 4 tabs.

  2. Advanced Test Reactor Critical Facility safety analysis report five year currency review

    SciTech Connect (OSTI)

    Napper, P.R.; Carpenter, W.R.; Garner, R.W.

    1991-05-01T23:59:59.000Z

    By DOE-ID Order 5481.1A, a five year currency review is required of the Safety Analysis Reports of all ID or ID contractor operations having hazards of a type and magnitude not routinely encountered and/or accepted by the public. In keeping with this order, a currency review has been performed of the Advanced Test Reactor Critical Facility (ADTRC) Safety Analysis Report (SAR), Issue 003, 1990. The objectives of this currency review were to: evaluate the content, completeness, clarity of presentation and compliance with NRC Regulatory Guides and DOE Orders, etc., and evaluate the technical content of the SAR, particularly the Technical Specifications, and to evaluate the safety of continued operation of the ATRC. The reviewers concluded that although improvements may be needed in the overall content, clarity, and demonstration of compliance with current orders and regulations, the safety of the ATRC is in no way compromised and no unreviewed safety questions were identified. 6 figs., 3 tabs.

  3. SAFETY ANALYSIS AND INTEGRATION FOR ROBOTIC SYSTEMS -APPLICATION TO A

    E-Print Network [OSTI]

    Guiochet, Jérémie

    Analysis (FMEA) and Fault Tree Analysis (FTA) which identify potential unit errors resulting in hazards

  4. Development of a safety analysis system for the offshore personnel and equipment transfer process

    E-Print Network [OSTI]

    McKenna, Michael George

    1988-01-01T23:59:59.000Z

    and Effect Analysis (FMEA) was performed. With the FMEA the question "What if?" is asked for each component. For example, "What if the lifting cable fails' ?". Each component was evaluated for failure mode, failure effects on other components... swell or waves stood out as primary factors in the safety of the transfer process. Failure Mode and Effect Anal sis With component failure a recognized factor in the safety of the transfer process, more in-depth analysis was merited. The FMEA...

  5. Hazard Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports

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

    1997-12-12T23:59:59.000Z

    he purpose of this DOE Standard is to establish guidance for the preparation and review of hazard categorization and accident analyses techniques as required in DOE Order 5480.23, Nuclear Safety Analysis Reports.

  6. Job Matching and Propagation

    E-Print Network [OSTI]

    Ramey, Garey; Fujita, Shigeru

    2006-01-01T23:59:59.000Z

    the labor force who want a job. Monthly Labor Review Cogley,G. , Watson, J. , June 2000. Job destruction and propagationJ. , June 2004. Gross job ?ows over the past two business

  7. Student Job Listing JobX Student Training Guide

    E-Print Network [OSTI]

    Collett Jr., Jeffrey L.

    Student Job Listing JobX Student Training Guide Student Employment Services #12;Training Topics: 1. Introduction 2. Find a Job 3. Apply For a Job 4. Complete JobMail Subscription #12;JobX: A Total Solution JobX helps schools automate the job posting, hiring, and reporting process for students, employers

  8. Formal Safety analysis of a radiobased railroad crossing using Deductive CauseConsequence

    E-Print Network [OSTI]

    Reif, Wolfgang

    #ects analysis (FMEA) and fault tree analysis (FTA). We apply the method to a real world case study: a radio (DCCA). This technique is a formal generalization of well­known safety analysis methods like FMEA [10 by analyzed) than traditional FMEA. We show, that the results of DCCA have the same semantics as those

  9. Sodium fast reactor gaps analysis of computer codes and models for accident analysis and reactor safety.

    SciTech Connect (OSTI)

    Carbajo, Juan (Oak Ridge National Laboratory, Oak Ridge, TN); Jeong, Hae-Yong (Korea Atomic Energy Research Institute, Daejeon, Korea); Wigeland, Roald (Idaho National Laboratory, Idaho Falls, ID); Corradini, Michael (University of Wisconsin, Madison, WI); Schmidt, Rodney Cannon; Thomas, Justin (Argonne National Laboratory, Argonne, IL); Wei, Tom (Argonne National Laboratory, Argonne, IL); Sofu, Tanju (Argonne National Laboratory, Argonne, IL); Ludewig, Hans (Brookhaven National Laboratory, Upton, NY); Tobita, Yoshiharu (Japan Atomic Energy Agency, Ibaraki-ken, Japan); Ohshima, Hiroyuki (Japan Atomic Energy Agency, Ibaraki-ken, Japan); Serre, Frederic (Centre d'%C3%94etudes nucl%C3%94eaires de Cadarache %3CU%2B2013%3E CEA, France)

    2011-06-01T23:59:59.000Z

    This report summarizes the results of an expert-opinion elicitation activity designed to qualitatively assess the status and capabilities of currently available computer codes and models for accident analysis and reactor safety calculations of advanced sodium fast reactors, and identify important gaps. The twelve-member panel consisted of representatives from five U.S. National Laboratories (SNL, ANL, INL, ORNL, and BNL), the University of Wisconsin, the KAERI, the JAEA, and the CEA. The major portion of this elicitation activity occurred during a two-day meeting held on Aug. 10-11, 2010 at Argonne National Laboratory. There were two primary objectives of this work: (1) Identify computer codes currently available for SFR accident analysis and reactor safety calculations; and (2) Assess the status and capability of current US computer codes to adequately model the required accident scenarios and associated phenomena, and identify important gaps. During the review, panel members identified over 60 computer codes that are currently available in the international community to perform different aspects of SFR safety analysis for various event scenarios and accident categories. A brief description of each of these codes together with references (when available) is provided. An adaptation of the Predictive Capability Maturity Model (PCMM) for computational modeling and simulation is described for use in this work. The panel's assessment of the available US codes is presented in the form of nine tables, organized into groups of three for each of three risk categories considered: anticipated operational occurrences (AOOs), design basis accidents (DBA), and beyond design basis accidents (BDBA). A set of summary conclusions are drawn from the results obtained. At the highest level, the panel judged that current US code capabilities are adequate for licensing given reasonable margins, but expressed concern that US code development activities had stagnated and that the experienced user-base and the experimental validation base was decaying away quickly.

  10. Bioindustry Creates Green Jobs

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

    Bioindustry Creates Green Jobs Energy from abundant, renewable, domestic biomass can reduce U.S. dependence on oil, lower impacts on climate, and stimulate jobs and eco- nomic...

  11. Running jobs on Euclid

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

    Running jobs Running jobs Overview and Basic Description Euclid is a single node system with 48 processors. It supports both multiprocessing (MPI) and multithreading programming...

  12. ACCIDENT ANALYSES & CONTROL OPTIONS IN SUPPORT OF THE SLUDGE WATER SYSTEM SAFETY ANALYSIS

    SciTech Connect (OSTI)

    WILLIAMS, J.C.

    2003-11-15T23:59:59.000Z

    This report documents the accident analyses and nuclear safety control options for use in Revision 7 of HNF-SD-WM-SAR-062, ''K Basins Safety Analysis Report'' and Revision 4 of HNF-SD-SNF-TSR-001, ''Technical Safety Requirements - 100 KE and 100 KW Fuel Storage Basins''. These documents will define the authorization basis for Sludge Water System (SWS) operations. This report follows the guidance of DOE-STD-3009-94, ''Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports'', for calculating onsite and offsite consequences. The accident analysis summary is shown in Table ES-1 below. While this document describes and discusses potential control options to either mitigate or prevent the accidents discussed herein, it should be made clear that the final control selection for any accident is determined and presented in HNF-SD-WM-SAR-062.

  13. Comparison of a Traditional Probabilistic Risk Assessment Approach with Advanced Safety Analysis

    SciTech Connect (OSTI)

    Smith, Curtis L; Mandelli, Diego; Zhegang Ma

    2014-11-01T23:59:59.000Z

    As part of the Light Water Sustainability Program (LWRS) [1], the purpose of the Risk Informed Safety Margin Characterization (RISMC) [2] Pathway research and development (R&D) is to support plant decisions for risk-informed margin management with the aim to improve economics, reliability, and sustain safety of current NPPs. In this paper, we describe the RISMC analysis process illustrating how mechanistic and probabilistic approaches are combined in order to estimate a safety margin. We use the scenario of a “station blackout” (SBO) wherein offsite power and onsite power is lost, thereby causing a challenge to plant safety systems. We describe the RISMC approach, illustrate the station blackout modeling, and contrast this with traditional risk analysis modeling for this type of accident scenario. We also describe our approach we are using to represent advanced flooding analysis.

  14. Oak Ridge National Laboratory site data for safety-analysis report

    SciTech Connect (OSTI)

    Fitzpatrick, F.C.

    1982-12-01T23:59:59.000Z

    The Oak Ridge National Laboratory site data contained herein were compiled in support of the United States Department of Energy (USDOE) Oak Ridge Operations Office Order OR 5481.1. That order sets forth assignment of responsibilities for safety analysis and review responsibilities and provides guidance relative to the content and format of safety analysis reports. The information presented in this document is intended for use by reference in individual safety analysis reports where applicable to support accident analyses or the establishment of design bases of significance to safety, and it is applicable only to Oak Ridge National Laboratory facilities in Bethel and Melton Valleys. This information includes broad descriptions of the site characteristics, radioactive waste handling and monitoring practices, and the organization and operating policies at Oak Ridge National Laboratory. The historical background of the Laboratory is discussed briefly and the overall physical situation of the facilities is described in the following paragraphs.

  15. Determining Your Safety Training Requirements @ Columbia University Columbia-specific training is mandatory for numerous positions and job functions at the University. Please

    E-Print Network [OSTI]

    Jia, Songtao

    workers, post-docs, students) Laboratory Safety, Chemical Hygiene and Hazardous Waste Management Training to the Institutional Biosafety Committee (RASCAL Appendix B) or renewals of #12;existing protocols Working in such activities; refresher every 2 years or sooner if determined by EH&S Shipping non-hazardous materials with Dry

  16. A path analysis of relationships among job stress, job satisfaction, motivation to transfer, and transfer of learning: perceptions of occupational safety and health administration outreach trainers

    E-Print Network [OSTI]

    Nair, Prakash Krishnan

    2009-05-15T23:59:59.000Z

    /situational factors on transfer. Some researchers have studied the effect of individual factors such as emotional stability, learner readiness, and self-efficacy on transfer (Herold, Davis, Fedor & Parson, 2002; Holton et al., 1997; Holton et al., 2000; O...?Neill, Hansen & May, 2002). Others have studied the effect of environmental factors such as supervisor and peer support, negative and positive feedback, and workplace design on transfer (Awoniyi, Griego and Morgan, 2002; Bates & Khasawneh, 2005; Chen, Holton...

  17. A semiotic analysis of biotechnology and food safety photographs

    E-Print Network [OSTI]

    Norwood, Jennifer Lynn

    2006-04-12T23:59:59.000Z

    This study evaluated photographs used in Time, Newsweek, and U.S. News and World Report in stories about biotechnology and food safety issues from the years 2000 and 2001. This study implemented a semiotic methodology to determine if the messages...

  18. Monitoring and Managing PDSF Jobs

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

    skip the -u option, you'll get all the jobs on PDSF. Get detailed info about a specific job qstat -j jobID You can get jobID by listing your jobs as described above. See how...

  19. Process hazards analysis (PrHA) program, bridging accident analyses and operational safety

    SciTech Connect (OSTI)

    Richardson, J. A. (Jeanne A.); McKernan, S. A. (Stuart A.); Vigil, M. J. (Michael J.)

    2003-01-01T23:59:59.000Z

    Recently the Final Safety Analysis Report (FSAR) for the Plutonium Facility at Los Alamos National Laboratory, Technical Area 55 (TA-55) was revised and submitted to the US. Department of Energy (DOE). As a part of this effort, over seventy Process Hazards Analyses (PrHAs) were written and/or revised over the six years prior to the FSAR revision. TA-55 is a research, development, and production nuclear facility that primarily supports US. defense and space programs. Nuclear fuels and material research; material recovery, refining and analyses; and the casting, machining and fabrication of plutonium components are some of the activities conducted at TA-35. These operations involve a wide variety of industrial, chemical and nuclear hazards. Operational personnel along with safety analysts work as a team to prepare the PrHA. PrHAs describe the process; identi fy the hazards; and analyze hazards including determining hazard scenarios, their likelihood, and consequences. In addition, the interaction of the process to facility systems, structures and operational specific protective features are part of the PrHA. This information is rolled-up to determine bounding accidents and mitigating systems and structures. Further detailed accident analysis is performed for the bounding accidents and included in the FSAR. The FSAR is part of the Documented Safety Analysis (DSA) that defines the safety envelope for all facility operations in order to protect the worker, the public, and the environment. The DSA is in compliance with the US. Code of Federal Regulations, 10 CFR 830, Nuclear Safety Management and is approved by DOE. The DSA sets forth the bounding conditions necessary for the safe operation for the facility and is essentially a 'license to operate.' Safely of day-to-day operations is based on Hazard Control Plans (HCPs). Hazards are initially identified in the PrI-IA for the specific operation and act as input to the HCP. Specific protective features important to worker safety are incorporated so the worker can readily identify the safety parameters of the their work. System safety tools such as Preliminary Hazard Analysis, What-If Analysis, Hazard and Operability Analysis as well as other techniques as necessary provide the groundwork for both determining bounding conditions for facility safety, operational safety, and day-to-clay worker safety.

  20. STEP Intern Job Description

    Broader source: Energy.gov [DOE]

    STEP Intern Job Description, from the Tool Kit Framework: Small Town University Energy Program (STEP).

  1. National Synchrotron Light Source safety-analysis report

    SciTech Connect (OSTI)

    Batchelor, K. (ed.)

    1982-07-01T23:59:59.000Z

    This document covers all of the safety issues relating to the design and operation of the storage rings and injection system of the National Synchrotron Light Source. The building systems for fire protection, access and egress are described together with air and other gaseous control or venting systems. Details of shielding against prompt bremstrahlung radiation and synchrotron radiation are described and the administrative requirements to be satisfied for operation of a beam line at the facility are given.

  2. Factors Analysis on Safety of Indoor Air Quality

    E-Print Network [OSTI]

    Luo, Q.; Liu, Z.; Xiong, J.

    2006-01-01T23:59:59.000Z

    . Handbook on Review and Detection of Indoor Environment [M]. Beijing: Mechanical Industry Press, 2003: 1-5.(In Chinese) [2] Pan Xiaochuan. Review on Indoor Air Pollution and Its Harmfulness to Health [J]. Chin. Prev. Med., 2002,3(3):167-169 (in... of Urban Construction, Nanhua University, Hengyang, P.R.China hunanluoqinghai@163.com Abstract: Influence factors on safety of indoor air quality (IAQ) were analyzed in this paper. Some regeneration compositions resulting from potential indoor...

  3. Safety Analysis of an Airbag System using Probabilistic FMEA and Probabilistic Counterexamples

    E-Print Network [OSTI]

    Leue, Stefan

    Safety Analysis of an Airbag System using Probabilistic FMEA and Probabilistic Counterexamples H analysis (FMEA) is a technique to reason about possible system hazards that result from system or system component failures. Tradition- ally, FMEA does not take the probabilities with which these failures may

  4. Safety Analysis of an Airbag System using Probabilistic FMEA and Probabilistic Counter Examples

    E-Print Network [OSTI]

    Leue, Stefan

    Safety Analysis of an Airbag System using Probabilistic FMEA and Probabilistic Counter Examples Failure mode and effects analysis (FMEA) is a technique to reason about possible system hazards that result from system or system component failures. Traditionally, FMEA does not take the probabilities

  5. Job Description Library Create a New Job Description

    E-Print Network [OSTI]

    Pulfrey, David L.

    UBC eRecruit Job Description Library #12;Page 4 Create a New Job Description Navigation: Job Description Library>Add/Edit/Copy Job Descriptions Step 1: Use this page to enter preliminary Job Description, Location: Enter the codes associated with the department. Employment Group, Job Family, Job Code/Classification

  6. Invited Contribution to Q 76: The Use of Risk Analysis to Support Dam Safety Decisions and Management

    E-Print Network [OSTI]

    Bowles, David S.

    Decisions and Management DRAFT FOR REVIEW ONLY Portfolio Risk Assessment: A Tool for Managing Dam SafetyICOLD 20th Congress Invited Contribution to Q 76: The Use of Risk Analysis to Support Dam Safety in the Context of the Owner's Business David S. Bowles Professor and Director, Institute for Dam Safety Risk

  7. LESSONS LEARNED IN DEVELOPMENT OF THE HANFORD SWOC MASTER DOCUMENTED SAFETY ANALYSIS (MDSA) & IMPLEMENTATION VALIDATION REVIEW (IVR)

    SciTech Connect (OSTI)

    MORENO, M.R.

    2004-04-02T23:59:59.000Z

    DOE set clear expectations on a cost-effective approach for achieving compliance with the Nuclear Safety Management requirements (20 CFR 830, Nuclear Safety Rule), which ensured long-term benefit to Hanford, via issuance of a nuclear safety strategy in February 2003. To facilitate implementation of these expectations, tools were developed to streamline and standardize safety analysis and safety document development with the goal of a shorter and more predictable DOE approval cycle. A Hanford Safety Analysis and Risk Assessment Handbook (SARAH) was approved to standardize methodologies for development of safety analyses. A Microsoft Excel spreadsheet (RADIDOSE) was approved for the evaluation of radiological consequences for accident scenarios often postulated at Hanford. Standard safety management program chapters were approved for use as a means of compliance with the programmatic chapters of DOE-STD-3009, ''Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports''. An in-process review was developed between DOE and the Contractor to facilitate DOE approval and provide early course correction. The new Documented Safety Analysis (DSA) developed to address the operations of four facilities within the Solid Waste Operations Complex (SWOC) necessitated development of an Implementation Validation Review (IVR) process. The IVR process encompasses the following objectives: safety basis controls and requirements are adequately incorporated into appropriate facility documents and work instructions, facility personnel are knowledgeable of controls and requirements, and the DSA/TSR controls have been implemented. Based on DOE direction and safety analysis tools, four waste management nuclear facilities were integrated into one safety basis document. With successful completion of implementation of this safety document, lessons-learned from the in-process review, safety analysis tools and IVR process were documented for future action and consideration at other DOE sites.

  8. Job Hazards Analysis Communication

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOEThe Bonneville PowerCherries 82981-1cnHigh SchoolIn12electron beam chargesJennifer AweJoanna S. Fowler, 1998/

  9. Safety System Oversight Staffing Analysis (Instructions, Blank Sheet and

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn'tOrigin ofEnergy atLLC - FE DKT. 10-160-LNG - ORDERSTATE0-1of Energy Safety

  10. 340 Waste handling Facility Hazard Categorization and Safety Analysis

    SciTech Connect (OSTI)

    T. J. Rodovsky

    2010-10-25T23:59:59.000Z

    The analysis presented in this document provides the basis for categorizing the facility as less than Hazard Category 3.

  11. Review and Analysis of Development of "Safety by Design" Requirements

    SciTech Connect (OSTI)

    Vance, Scott A.; Hockert, John

    2009-10-20T23:59:59.000Z

    This report, the deliverable for Task 4 of the NA-243 Safeguards by Design Work Plan for Fiscal Year 2009, develops the lessons to be learned for the institutionalization of Safeguards By Design (SBD) from the Department of Energy (DOE) experience developing and implementing DOE-STD-1189, Integration of Safety into the Design Process. This experience was selected for study because of the similarity of the challenges of integrating safety and safeguards into the design process. Development of DOE-STD-1189 began in January 2006 and the standard was issued for implementation in March 2008. The process was much more time consuming than originally anticipated and might not have come to fruition had senior DOE management been less committed to its success. Potentially valuable lessons can be learned from both the content and presentation of the integration approach in DOE-STD-1189 and from the DOE experience in developing and implementing DOE-STD-1189. These lessons are important because the instutionalization of SBD does not yet appear to have the level of senior management commitment afforded development and implementation of DOE-STD-1189.

  12. Station Blackout: A case study in the interaction of mechanistic and probabilistic safety analysis

    SciTech Connect (OSTI)

    Curtis Smith; Diego Mandelli; Cristian Rabiti

    2013-11-01T23:59:59.000Z

    The ability to better characterize and quantify safety margins is important to improved decision making about nuclear power plant design, operation, and plant life extension. As research and development (R&D) in the light-water reactor (LWR) Sustainability (LWRS) Program and other collaborative efforts yield new data, sensors, and improved scientific understanding of physical processes that govern the aging and degradation of plant SSCs needs and opportunities to better optimize plant safety and performance will become known. The purpose of the Risk Informed Safety Margin Characterization (RISMC) Pathway R&D is to support plant decisions for risk-informed margin management with the aim to improve economics, reliability, and sustain safety of current NPPs. In this paper, we describe the RISMC analysis process illustrating how mechanistic and probabilistic approaches are combined in order to estimate a safety margin. We use the scenario of a “station blackout” wherein offsite power and onsite power is lost, thereby causing a challenge to plant safety systems. We describe the RISMC approach, illustrate the station blackout modeling, and contrast this with traditional risk analysis modeling for this type of accident scenario.

  13. Safety analysis report for the TRUPACT-II shipping package (condensed version). Volume 1, Rev. 14

    SciTech Connect (OSTI)

    NONE

    1994-10-01T23:59:59.000Z

    The condensed version of the TRUPACT-II Contact Handled Transuranic Waste Safety Analysis Report for Packaging (SARP) contains essential material required by TRUPACT-II users, plus additional contents (payload) information previously submitted to the U.S. Nuclear Regulatory Commission. All or part of the following sections, which are not required by users of the TRUPACT-II, are deleted from the condensed version: (i) structural analysis, (ii) thermal analysis, (iii) containment analysis, (iv) criticality analysis, (v) shielding analysis, and (vi) hypothetical accident test results.

  14. Risk-Informed Safety Margin Characterization (RISMC): Integrated Treatment of Aleatory and Epistemic Uncertainty in Safety Analysis

    SciTech Connect (OSTI)

    R. W. Youngblood

    2010-10-01T23:59:59.000Z

    The concept of “margin” has a long history in nuclear licensing and in the codification of good engineering practices. However, some traditional applications of “margin” have been carried out for surrogate scenarios (such as design basis scenarios), without regard to the actual frequencies of those scenarios, and have been carried out with in a systematically conservative fashion. This means that the effectiveness of the application of the margin concept is determined in part by the original choice of surrogates, and is limited in any case by the degree of conservatism imposed on the evaluation. In the RISMC project, which is part of the Department of Energy’s “Light Water Reactor Sustainability Program” (LWRSP), we are developing a risk-informed characterization of safety margin. Beginning with the traditional discussion of “margin” in terms of a “load” (a physical challenge to system or component function) and a “capacity” (the capability of that system or component to accommodate the challenge), we are developing the capability to characterize probabilistic load and capacity spectra, reflecting both aleatory and epistemic uncertainty in system response. For example, the probabilistic load spectrum will reflect the frequency of challenges of a particular severity. Such a characterization is required if decision-making is to be informed optimally. However, in order to enable the quantification of probabilistic load spectra, existing analysis capability needs to be extended. Accordingly, the INL is working on a next-generation safety analysis capability whose design will allow for much more efficient parameter uncertainty analysis, and will enable a much better integration of reliability-related and phenomenology-related aspects of margin.

  15. FAQS Gap Analysis Qualification Card – Nuclear Explosive Safety Study

    Broader source: Energy.gov [DOE]

    Functional Area Qualification Standard Gap Analysis Qualification Cards outline the differences between the last and latest version of the FAQ Standard.

  16. Energy Department creates Jobs Strategy Council to Focus on Job...

    Energy Savers [EERE]

    creates Jobs Strategy Council to Focus on Job Growth in Energy Economy Energy Department creates Jobs Strategy Council to Focus on Job Growth in Energy Economy January 23, 2015 -...

  17. Job Position Description Job Title: Computer Systems Assistant

    E-Print Network [OSTI]

    Moore, Paul A.

    Job Position Description Job Title: Computer Systems Assistant A. Main purpose of the job for department of Campus Operations. B. Primary responsibilities or key duties of the job (tasks performed

  18. Job Position Description A. Main Purpose of the job

    E-Print Network [OSTI]

    Moore, Paul A.

    4/5/2011 Job Position Description Job Title: A. Main Purpose of the job: B. Primary responsibilities or key duties of the job (tasks performed regularly): 1. 2. 3. 4. C. Additional duties (tasks

  19. Job Position Description Job Title: Paint Crew Team Leader

    E-Print Network [OSTI]

    Moore, Paul A.

    Job Position Description Job Title: Paint Crew Team Leader A. Main purpose of the job: Lead responsibilities or key duties of the job (tasks performed regularly): 1. Oversee other paint crew workers

  20. Job Position Description Job Title: Groundskeeper/Recycler

    E-Print Network [OSTI]

    Moore, Paul A.

    Job Position Description Job Title: Groundskeeper/Recycler A. Main purpose of the job: Perform grounds keeping and recycling duties. B. Primary responsibilities or key duties of the job

  1. PARTI: JOB DESCRIPTION Weighted Job Questionnaire (WJQ) Custom

    E-Print Network [OSTI]

    PARTI: JOB DESCRIPTION Weighted Job Questionnaire (WJQ) Custom Meeting, Event and Conference UNIVERSITY & C.U.P.E., Local 3338 WEIGHTED JOB QUESTIONNAIRE (WJQ) CUSTOM PARTI: JOB DESCRIPTION 1. POSITION

  2. YUCCA MOUNTAIN SITE CHARACTERIZATIONS PROJECT TUNNEL BORING MACHINE (TBM) SYSTEM SAFETY ANALYSIS

    SciTech Connect (OSTI)

    N /A

    1997-02-19T23:59:59.000Z

    The purpose of this analysis is to systematically identify and evaluate hazards related to the tunnel boring machine (TBM) used in the Exploratory Studies Facility (ESF) at the Yucca Mountain Site Characterization Project. This process is an integral part of the systems engineering process; whereby safety is considered during planning, design, testing, and construction. Since the TBM is an ''as built'' system, the M&O is conducting the System Safety Analysis during the construction or assembly phase of the TBM. A largely qualitative approach was used since a radiological System Safety Analysis is not required. The risk assessment in this analysis characterizes the accident scenarios associated with the TBM in terms of relative risk and includes recommendations for mitigating all identified risks. The priority for recommending and implementing mitigation control features is: (1) Incorporate measures to reduce risks and hazards into the system/subsystem/component design, (2) add safety features and capabilities to existing designs, and (3) develop procedures and conduct training to increase worker awareness of potential hazards, on methods to reduce exposure to hazards, and on the actions required to avoid accidents or correct hazardous conditions. The scope of this analysis is limited to the TBM during normal operations, excluding hazards occurring during assembly and test of the TBM or maintenance of the TBM equipment.

  3. Office of Environmental Protection, Sustainability Support, and Corporate Safety Analysis

    Broader source: Energy.gov [DOE]

    The Office of Environmental Protection, Sustainability Support and Analysis establishes environmental protection requirements and expectations for the Department to ensure protection of workers and the public and protection of the environment from the hazards associated with all Department operations.

  4. Job Scheduling Scheme for Pure Space Sharing among Rigid Jobs

    E-Print Network [OSTI]

    Feitelson, Dror

    Job Scheduling Scheme for Pure Space Sharing among Rigid Jobs Kento Aida1, Hironori Kasahara2. This paper evaluates the performance of job scheduling sche- mes for pure space sharing among rigid jobs. Conventional job scheduling schemes for the pure space sharing among rigid jobs have been achieved by First

  5. Job Search StrategiesJob Search Strategies Career Services

    E-Print Network [OSTI]

    Escher, Christine

    Job Search StrategiesJob Search Strategies Career Services Oregon State UniversityOregon State/careerhttp://oregonstate.edu/career #12;Overview of Career Services B J bN t Individual Career Counseling Drop-ins Beaver JobNet Job NACE Top ten OLMIS Four steps for the job search Job search techniquesq Tips for success #12;The

  6. Job Search: Regional/Quality Job Search Engines

    E-Print Network [OSTI]

    Carter, John

    Job Search: Regional/Quality Job Search Engines Bellevue College: http://bellevuecollege.edu/careers/sac_general.html#searchengines PNW Job Board: https://services.philanthropynw.org/jobbank/ ColorsNW Job Bank: http://jobs.colorscareers.com/c/search_results.cfm?site_id=1919 Seattle Jobs: http://www.seattlejobs.com/ WorkSource Seattle-King County: http

  7. Job Search: Regional/Quality Job Search Engines

    E-Print Network [OSTI]

    Carter, John

    Resources Job Search: Regional/Quality Job Search Engines Bellevue College: http://bellevuecollege.edu/careers/sac_general.html#searchengines PNW Job Board: https://services.philanthropynw.org/jobbank/ ColorsNW Job Bank: http://jobs.colorscareers.com/c/search_results.cfm?site_id=1919 Seattle Jobs: http://www.seattlejobs.com/ WorkSource Seattle-King County: http

  8. Job Training Assistance Programs (Tennessee)

    Broader source: Energy.gov [DOE]

    The Job Training Assistance Programs in Tennessee are a combination of three programs: The FastTrack Job Training Assistance Program (FJTAP), The Tennessee Job Skills Program (TJS), and The Job...

  9. Quality Jobs Program (Louisiana)

    Broader source: Energy.gov [DOE]

    The Quality Jobs Program provides a cash rebate to companies that create well-paid jobs and promote economic development. Benefits include a 5-6% cash rebate of annual gross payroll for new,...

  10. PDSF Interactive Batch Jobs

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

    Interactive Batch Jobs Running Interactive Batch Jobs You cannot login to the PDSF batch nodes directly but you can run an interactive session on a batch node using either qlogin...

  11. Usage by Job Size

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

    Usage by Job Size Table Usage by Job Size Table page loading animation Usage Query Interface System All Hopper Edison Carver Planck Matgen Franklin Hopper 1 Magellan Dirac Bassi...

  12. Franklin Job Launch Overview

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

    Job Launch Overview Job Launch Overview Overview and Basic Description Franklin has three basic types of nodes. Compute Nodes The 9,572 compute nodes each have a quad-core 2.3 GHz...

  13. Jobs Tax Credit (Wisconsin)

    Broader source: Energy.gov [DOE]

    Businesses relocating to Wisconsin or expanding in Wisconsin that are creating full-time employment may be eligible for The Jobs Tax Credit . Jobs created as a result of the tax credit must be...

  14. ARIES-ACT1 SAFETY DESIGN AND ANALYSIS

    SciTech Connect (OSTI)

    Paul W. Humrickhouse; Brad J. Merrill

    2015-01-01T23:59:59.000Z

    ARIES-ACT1 is a 1000 MWe tokamak design featuring advanced physics and engineering. Some relevant features include an advanced SiC blanket with PbLi as coolant and breeder, a helium cooled steel structural ring and tungsten divertors, a thin-walled, helium cooled vacuum vessel, and a room temperature water-cooled shield outside the vacuum vessel. We consider here some safety aspects of the ARIES-ACT1 design, and model a series of design-basis and beyond design-basis accidents with MELCOR. The presence of multiple coolants (PbLi, helium, and water) makes possible a variety of such accidents. We consider here a loss of flow accident (i.e. long term station blackout), an ex-vessel helium break into the cryostat, and a beyond design-basis accident in which both loss of power and a loss of the water coolant occur. In all cases we find that secondary confinement boundaries are not challenged, and the structural integrity of in-vessel components is not threatened by high temperatures; decay heat can be safely removed in all cases by passive systems.

  15. Fusion Engineering and Design 38 (1997) 189218 ARIES-RS safety design and analysis

    E-Print Network [OSTI]

    Fusion Engineering and Design 38 (1997) 189­218 ARIES-RS safety design and analysis D. Steiner *, L Polytechnic Institute, Department of En6ironmental and Energy Engineering, JEC 5049, Troy NY 12180-3590, USA assessment indicates that the dose at the site boundary will be less than 1 rem per year. Thus, no sheltering

  16. A quantitative analysis of health, safety and environment policy in France

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    A quantitative analysis of health, safety and environment policy in France Thomas Audiffrena , Jean-Marc Rallob , Franck Guarnieria , Christophe Martina a Mines ParisTech, Center for Research on Risks was introduced in France to regulate the role of occupational risk prevention specialists (OHS professionals

  17. COLLECTION OF MICRO-LEVEL SAFETY AND EFFICIENCY INDICATORS WITH AUTOMATED VIDEO ANALYSIS

    E-Print Network [OSTI]

    Lunds Universitet

    behaviour and injury accidents. A lot of research is therefore put into the work of developing methods program, Faculty of Engineering, LTH, Lund University, Sweden ABSTRACT This paper revises the theoretical and level-of-service analysis. Keywords: road safety, level-of-service, indicator, severity hierarchy

  18. Combining Functional and Structural Reasoning for Safety Analysis of Electrical Designs

    E-Print Network [OSTI]

    Snooke, Neal

    in detail. FLAME has been developed over several years, and is capable of composing an FMEA report for many Failure mode effects analysis (FMEA) of a design involves the investigation and assessment of the effects, electronic and mechanical systems are being combined in safety-critical applications. Automation of FMEA

  19. JOB DESCRIPTION POSITION DATA

    E-Print Network [OSTI]

    Harms, Kyle E.

    JOB DESCRIPTION POSITION DATA Position Number: Title Description: Title Code: Title Level: Employee: _____ Job Summary: Overview of position and its purpose. Select One Select One Select One Select One Select One Select One Select One Select One Select One Select One #12;Office of Human Resource Management Job

  20. ACADEMIC JOB SEARCH Survival Handbook

    E-Print Network [OSTI]

    Hampton, Randy

    The ACADEMIC JOB SEARCH Survival Handbook Especially for Graduate Students HOW TO: Find Job ______________________________________________________________ 1 Entering the Academic Job Market: Timelines & Job Search Where to Look for Academic Jobs_______________________________________________________ 27 #12;INTRODUCTION TO THE ACADEMIC JOB SEARCH SURVIVAL HANDBOOK Congratulations! If you are reading

  1. Waste sampling and characterization facility complex safety analysis

    SciTech Connect (OSTI)

    Meloy, R.T., Westinghouse Hanford

    1996-06-04T23:59:59.000Z

    The Waste Sampling and Characterization Facility is a `Non-Nuclear, Radiological Facility. This document demonstrates, by analysis, that WSCF can meet the chemical and radiological inventory limits for a radiological facility. It establishes control that ensures those inventories are maintained below threshold values to preserve the `Non- Nuclear, Radiological` classification.

  2. System design Active/Active HA Job Scheduler and

    E-Print Network [OSTI]

    Engelmann, Christian

    of scheduled job No loss of running job No restart of running jobs Leading to uninterruptible service overview Project goals failure of head node job submitted job runs job resubmitted job runs job done job resubmitted job runs job done job runs job done job continues job done Resubmission without checkpointing

  3. Final safety analysis report for the Ground Test Accelerator (GTA), Phase 2

    SciTech Connect (OSTI)

    NONE

    1994-10-01T23:59:59.000Z

    This document is the second volume of a 3 volume safety analysis report on the Ground Test Accelerator (GTA). The GTA program at the Los Alamos National Laboratory (LANL) is the major element of the national Neutral Particle Beam (NPB) program, which is supported by the Strategic Defense Initiative Office (SDIO). A principal goal of the national NPB program is to assess the feasibility of using hydrogen and deuterium neutral particle beams outside the Earth`s atmosphere. The main effort of the NPB program at Los Alamos concentrates on developing the GTA. The GTA is classified as a low-hazard facility, except for the cryogenic-cooling system, which is classified as a moderate-hazard facility. This volume consists of failure modes and effects analysis; accident analysis; operational safety requirements; quality assurance program; ES&H management program; environmental, safety, and health systems critical to safety; summary of waste-management program; environmental monitoring program; facility expansion, decontamination, and decommissioning; summary of emergency response plan; summary plan for employee training; summary plan for operating procedures; glossary; and appendices A and B.

  4. Receiving Basin for Offsite Fuels and the Resin Regeneration Facility Safety Analysis Report, Executive Summary

    SciTech Connect (OSTI)

    Shedrow, C.B.

    1999-11-29T23:59:59.000Z

    The Safety Analysis Report documents the safety authorization basis for the Receiving Basin for Offsite Fuels (RBOF) and the Resin Regeneration Facility (RRF) at the Savannah River Site (SRS). The present mission of the RBOF and RRF is to continue in providing a facility for the safe receipt, storage, handling, and shipping of spent nuclear fuel assemblies from power and research reactors in the United States, fuel from SRS and other Department of Energy (DOE) reactors, and foreign research reactors fuel, in support of the nonproliferation policy. The RBOF and RRF provide the capability to handle, separate, and transfer wastes generated from nuclear fuel element storage. The DOE and Westinghouse Savannah River Company, the prime operating contractor, are committed to managing these activities in such a manner that the health and safety of the offsite general public, the site worker, the facility worker, and the environment are protected.

  5. Safety analysis of B and W Standard PWR using thorium-based fuels

    SciTech Connect (OSTI)

    Uotinen, V.O.; Carroll, W.P.; Jones, H.M.; Toops, E.C.

    1980-06-01T23:59:59.000Z

    A study was performed to assess the safety and licenseability of the Babcock and Wilcox standard 205-fuel assembly PWR when it is fueled with three types of thoria-based fuels denatured (/sup 233/U//sup 238/U-Th)O/sub 2/, denatured (/sup 235//U/sup 238/U-Th)O/sub 2/, and (Th-Pu)O/sub 2/. Selected transients were analyzed using typical PWR safety analysis calculational methods. The results support the conclusion that it is feasible from a safety standpoint to utilize either of the denatured urania-thoria fuels in the standard B and W plant. In addition, it appears that the use of thoria-plutonia fuels would probably also be feasible. These tentative conclusions depend on a data that is more limited than that available for UO/sub 2/ fuels.

  6. Organizational analysis and safety for utilities with nuclear power plants: perspectives for organizational assessment. Volume 2. [PWR; BWR

    SciTech Connect (OSTI)

    Osborn, R.N.; Olson, J.; Sommers, P.E.; McLaughlin, S.D.; Jackson, M.S.; Nadel, M.V.; Scott, W.G.; Connor, P.E.; Kerwin, N.; Kennedy, J.K. Jr.

    1983-08-01T23:59:59.000Z

    This two-volume report presents the results of initial research on the feasibility of applying organizational factors in nuclear power plant (NPP) safety assessment. Volume 1 of this report contains an overview of the literature, a discussion of available safety indicators, and a series of recommendations for more systematically incorporating organizational analysis into investigations of nuclear power plant safety. The six chapters of this volume discuss the major elements in our general approach to safety in the nuclear industry. The chapters include information on organizational design and safety; organizational governance; utility environment and safety related outcomes; assessments by selected federal agencies; review of data sources in the nuclear power industry; and existing safety indicators.

  7. Technical Standards, Safety Analysis Toolbox Codes - November 2003 |

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directed offOCHCO Overview OCHCOSystems Analysis Success Stories SystemsTara TrujilloDepartment of Energy

  8. Monthly Analysis of Electrical Safety Occurrences - October 2012 |

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742Energy ChinaofSchaeferApril 1,(EAC)TABLE OFDepartment of Energy October 2011 An analysis

  9. Implementing 10 CFR 830 at the FEMP Silos: Nuclear Health and Safety Plans as Documented Safety Analysis

    SciTech Connect (OSTI)

    Fisk, Patricia; Rutherford, Lavon

    2003-06-01T23:59:59.000Z

    The objective of the Silos Project at the Fernald Closure Project (FCP) is to safely remediate high-grade uranium ore residues (Silos 1 and 2) and metal oxide residues (Silo 3). The evolution of Documented Safety Analyses (DSAs) for these facilities has reflected the changes in remediation processes. The final stage in silos DSAs is an interpretation of 10 CFR 830 Safe Harbor Requirements that combines a Health and Safety Plan with nuclear safety requirements. This paper will address the development of a Nuclear Health and Safety Plan, or N-HASP.

  10. Superconducting x-ray lithography source Phase 1 (XLS) safety analysis report

    SciTech Connect (OSTI)

    Blumberg, L. (ed.)

    1990-07-01T23:59:59.000Z

    This paper discusses safety aspects associated with the superconducting x-ray lithography source. The policy, building systems safety and storage ring systems safety are specifically addressed. (LSP)

  11. Design and Transient Analysis of Passive Safety Cooling Systems for Advanced Nuclear Reactors

    E-Print Network [OSTI]

    Galvez, Cristhian

    2011-01-01T23:59:59.000Z

    passive safety cooling systems. To develop an understandingthe passive safety cooling system and recommend an approachof Passive Safety Cooling Systems for Advanced Nuclear

  12. Documentation of Hanford Site independent review of the Hanford Waste Vitrification Plant Preliminary Safety Analysis Report. Revision 3

    SciTech Connect (OSTI)

    Herborn, D.I.

    1993-11-01T23:59:59.000Z

    Westinghouse Hanford Company (WHC) is the Integrating Contractor for the Hanford Waste Vitrification Plant (HWVP) Project, and as such is responsible for preparation of the HWVP Preliminary Safety Analysis Report (PSAR). The HWVP PSAR was prepared pursuant to the requirements for safety analyses contained in US Department of Energy (DOE) Orders 4700.1, Project Management System (DOE 1987); 5480.5, Safety of Nuclear Facilities (DOE 1986a); 5481.lB, Safety Analysis and Review System (DOE 1986b) which was superseded by DOE order 5480-23, Nuclear Safety Analysis Reports, for nuclear facilities effective April 30, 1992 (DOE 1992); and 6430.lA, General Design Criteria (DOE 1989). The WHC procedures that, in large part, implement these DOE requirements are contained in WHC-CM-4-46, Nonreactor Facility Safety Analysis Manual. This manual describes the overall WHC safety analysis process in terms of requirements for safety analyses, responsibilities of the various contributing organizations, and required reviews and approvals.

  13. Final safety analysis report for the Galileo Mission: Volume 1, Reference design document

    SciTech Connect (OSTI)

    Not Available

    1988-05-01T23:59:59.000Z

    The Galileo mission uses nuclear power sources called Radioisotope Thermoelectric Generators (RTGs) to provide the spacecraft's primary electrical power. Because these generators contain nuclear material, a Safety Analysis Report (SAR) is required. A preliminary SAR and an updated SAR were previously issued that provided an evolving status report on the safety analysis. As a result of the Challenger accident, the launch dates for both Galileo and Ulysses missions were later rescheduled for November 1989 and October 1990, respectively. The decision was made by agreement between the DOE and the NASA to have a revised safety evaluation and report (FSAR) prepared on the basis of these revised vehicle accidents and environments. The results of this latest revised safety evaluation are presented in this document (Galileo FSAR). Volume I, this document, provides the background design information required to understand the analyses presented in Volumes II and III. It contains descriptions of the RTGs, the Galileo spacecraft, the Space Shuttle, the Inertial Upper Stage (IUS), the trajectory and flight characteristics including flight contingency modes, and the launch site. There are two appendices in Volume I which provide detailed material properties for the RTG.

  14. MODEL 9977 B(M)F-96 SAFETY ANALYSIS REPORT FOR PACKAGING

    SciTech Connect (OSTI)

    Abramczyk, G; Paul Blanton, P; Kurt Eberl, K

    2006-05-18T23:59:59.000Z

    This Safety Analysis Report for Packaging (SARP) documents the analysis and testing performed on and for the 9977 Shipping Package, referred to as the General Purpose Fissile Package (GPFP). The performance evaluation presented in this SARP documents the compliance of the 9977 package with the regulatory safety requirements for Type B packages. Per 10 CFR 71.59, for the 9977 packages evaluated in this SARP, the value of ''N'' is 50, and the Transport Index based on nuclear criticality control is 1.0. The 9977 package is designed with a high degree of single containment. The 9977 complies with 10 CFR 71 (2002), Department of Energy (DOE) Order 460.1B, DOE Order 460.2, and 10 CFR 20 (2003) for As Low As Reasonably Achievable (ALARA) principles. The 9977 also satisfies the requirements of the Regulations for the Safe Transport of Radioactive Material--1996 Edition (Revised)--Requirements. IAEA Safety Standards, Safety Series No. TS-R-1 (ST-1, Rev.), International Atomic Energy Agency, Vienna, Austria (2000). The 9977 package is designed, analyzed and fabricated in accordance with Section III of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, 1992 edition.

  15. Sandia National Laboratories: Transportation Safety

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

    Experimental Testing Phenomenological Modeling Risk and Safety Assessment Cyber-Based Vulnerability Assessments Uncertainty Analysis Transportation Safety Fire Science Human...

  16. Job Title: Research Associate Position #: 016161.0001 Job Description

    E-Print Network [OSTI]

    Job Title: Research Associate Position #: 016161.0001 Job Description: Research associate sought, is helpful, because much of this job requires communication with veterinarians around the country. Applicants://www.cvmbs.colostate.edu/ns/departments/mip/ Job Opportunities for complete job description · CSU is an EO/EA/AA employer · Colorado State

  17. Work-Study Job Directory* Job Publish Request Form

    E-Print Network [OSTI]

    Guenther, Frank

    Work-Study Job Directory* Job Publish Request Form Please note: Work-Study jobs can be posted via to the Business Link. Please post Work-Study Job # ___ ___ ___ ___ ___ ___ Department-mail address students may contact: Job Description Changes (if any): Help us keep the directory up

  18. Job Position Description A. Main Purpose of the job

    E-Print Network [OSTI]

    Moore, Paul A.

    8/10/2012 Job Position Description Job Title: A. Main Purpose of the job: B. Primary responsibilities or key duties of the job (tasks performed regularly): 1. 2. 3. 4. C. Additional duties (tasks with preparation of job duties.4. #12;

  19. Writing Effective Job Descriptions What is a Job Description?

    E-Print Network [OSTI]

    Weaver, Harold A. "Hal"

    Writing Effective Job Descriptions #12;What is a Job Description? A clear explanation of a job and promoting employees) #12;Writing Effective Job Descriptions Identify what needs to be done, how work is to be performed, what equipment will be used, what working conditions are Describe the Job Define Skills

  20. A probabilistic safety analysis of UF{sub 6} handling at the Portsmouth Gaseous Diffusion Plant

    SciTech Connect (OSTI)

    Boyd, G.J.; Lewis, S.R.; Summitt, R.L. [Safety and Reliability Optimization Services (SAROS), Inc., Knoxville, TN (United States)

    1991-12-31T23:59:59.000Z

    A probabilistic safety study of UF{sub 6} handling activities at the Portsmouth Gaseous Diffusion Plant has recently been completed. The analysis provides a unique perspective on the safety of UF{sub 6} handling activities. The estimated release frequencies provide an understanding of current risks, and the examination of individual contributors yields a ranking of important plant features and operations. Aside from the probabilistic results, however, there is an even more important benefit derived from a systematic modeling of all operations. The integrated approach employed in the analysis allows the interrelationships among the equipment and the required operations to be explored in depth. This paper summarizes the methods used in the study and provides an overview of some of the technical insights that were obtained. Specific areas of possible improvement in operations are described.

  1. Certification process of safety analysis and risk management computer codes at the Savannah River Site

    SciTech Connect (OSTI)

    Ades, M.J. [Westinghouse Savannah River Co., Aiken, SC (United States); Toffer, H.; Lewis, C.J.; Crowe, R.D. [Westinghouse Hanford Co., Richland, WA (United States)

    1992-05-01T23:59:59.000Z

    The commitment by Westinghouse Savannah River Company (WSRC) to bring safety analysis and risk management codes into compliance with national and sitewide quality assurance requirements necessitated a systematic, structured approach. As a part of this effort, WSRC, in cooperation with the Westinghouse Hanford Company, has developed and implemented a certification process for the development and control of computer software. Safety analysis and risk management computer codes pertinent to reactor analyses were selected for inclusion in the certification process. As a first step, documented plans were developed for implementing verification and validation of the codes, and establishing configuration control. User qualification guidelines were determined. The plans were followed with an extensive assessment of the codes with respect to certification status. Detailed schedules and work plans were thus determined for completing certification of the codes considered. Although the software certification process discussed is specific to the application described, it is sufficiently general to provide useful insights and guidance for certification of other software.

  2. Certification process of safety analysis and risk management computer codes at the Savannah River Site

    SciTech Connect (OSTI)

    Ades, M.J. (Westinghouse Savannah River Co., Aiken, SC (United States)); Toffer, H.; Lewis, C.J.; Crowe, R.D. (Westinghouse Hanford Co., Richland, WA (United States))

    1992-01-01T23:59:59.000Z

    The commitment by Westinghouse Savannah River Company (WSRC) to bring safety analysis and risk management codes into compliance with national and sitewide quality assurance requirements necessitated a systematic, structured approach. As a part of this effort, WSRC, in cooperation with the Westinghouse Hanford Company, has developed and implemented a certification process for the development and control of computer software. Safety analysis and risk management computer codes pertinent to reactor analyses were selected for inclusion in the certification process. As a first step, documented plans were developed for implementing verification and validation of the codes, and establishing configuration control. User qualification guidelines were determined. The plans were followed with an extensive assessment of the codes with respect to certification status. Detailed schedules and work plans were thus determined for completing certification of the codes considered. Although the software certification process discussed is specific to the application described, it is sufficiently general to provide useful insights and guidance for certification of other software.

  3. Preliminary Safety Analysis Report for the Transuranic Storage Area Retrieval Enclosure at the Idaho National Engineering Laboratory. Revision 8

    SciTech Connect (OSTI)

    Not Available

    1993-03-01T23:59:59.000Z

    This Transuranic Storage Area Retrieval Enclosure Preliminary Safety Analysis Report was completed as required by DOE Order 5480.23. The purpose of this document is to construct a safety basis that supports the design and permits construction of the facility. The facility has been designed to the requirements of a Radioactive Solid Waste Facility presented in DOE Order 6430.1A.

  4. Means-ends and whole-part traceability analysis of safety requirements Jang-Soo Lee a,*, Vikash Katta b

    E-Print Network [OSTI]

    Jee, Eunkyoung

    . Most of the safety-critical systems in nuclear power plants and airplanes for example, have this typeMeans-ends and whole-part traceability analysis of safety requirements Jang-Soo Lee a,*, Vikash Katta b , Eun-Kyoung Jee c , Christian Raspotnig b a Korea Atomic Energy Research Institute, Daejeon

  5. An effective technique for the software requirements analysis of NPP safety-critical systems, based on software inspection, requirements

    E-Print Network [OSTI]

    &V) is therefore emphasized for nuclear safety. Inspection is widely believed to be an effective techniqueAn effective technique for the software requirements analysis of NPP safety-critical systems, based Seonga , Junbeom Yoob , Sung Deok Chab , Yeong Jae Yooc,1 a Department of Nuclear and Quantum Engineering

  6. Safety analysis report for packaging, onsite, long-length contaminated equipment transport system

    SciTech Connect (OSTI)

    McCormick, W.A.

    1997-05-09T23:59:59.000Z

    This safety analysis report for packaging describes the components of the long-length contaminated equipment (LLCE) transport system (TS) and provides the analyses, evaluations, and associated operational controls necessary for the safe use of the LLCE TS on the Hanford Site. The LLCE TS will provide a standardized, comprehensive approach for the disposal of approximately 98% of LLCE scheduled to be removed from the 200 Area waste tanks.

  7. Parallel Job Scheduling and Workloads

    E-Print Network [OSTI]

    Segall, Adrian

    Parallel Job Scheduling and Workloads Dror Feitelson Hebrew University #12;Parallel Jobs · A set · On multicores: probably more dynamic #12;MPP Parallel Job Scheduling · Each job is a rectangle in processorsXtime space · Given many jobs, we must schedule them to run on available processors · This is like packing

  8. Running Jobs Intermittently Slow

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

    globalscratch2). It could also happen to aplications using shared libraries, or CCM jobs on any Hopper file systems. The slowness is identified to be related to DVSGPFS...

  9. Job Openings at CEES

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

    Job Openings at the Center for Electrical Energy Storage All CEES positions are currently filled. For more information about Postdoctoral Fellowship Programs at Argonne, please...

  10. Standard review plan for reviewing safety analysis reports for dry metallic spent fuel storage casks

    SciTech Connect (OSTI)

    Not Available

    1988-01-01T23:59:59.000Z

    The Cask Standard Review Plan (CSRP) has been prepared as guidance to be used in the review of Cask Safety Analysis Reports (CSARs) for storage packages. The principal purpose of the CSRP is to assure the quality and uniformity of storage cask reviews and to present a well-defined base from which to evaluate proposed changes in the scope and requirements of reviews. The CSRP also sets forth solutions and approaches determined to be acceptable in the past by the NRC staff in dealing with a specific safety issue or safety-related design area. These solutions and approaches are presented in this form so that reviewers can take consistent and well-understood positions as the same safety issues arise in future cases. An applicant submitting a CSAR does not have to follow the solutions or approaches presented in the CSRP. However, applicants should recognize that the NRC staff has spent substantial time and effort in reviewing and developing their positions for the issues. A corresponding amount of time and effort will probably be required to review and accept new or different solutions and approaches.

  11. PART I: JOB DESCRIPTION Weighted Job Questionnaire (WJQ) Custom

    E-Print Network [OSTI]

    PART I: JOB DESCRIPTION Weighted Job Questionnaire (WJQ) Custom Department Name: Student,1412 SIMON FRASER UNIVERSITY & C.U.P.E., Local 3338 JOB DESCRIPTION 1. POSITION IDENTIFICATION Department

  12. Electronic Job Submission For faster job submission, email your jobs

    E-Print Network [OSTI]

    of hours. Large binding or folding jobs may take a few days to complete. Need it now? Call us! I'm sure we Stock 8.5x11" (for coil and comb bound books) $0.29 Stapling Binding Options Price includes clear front

  13. Job Safety Health Poster Spanish 09042014.docx

    Office of Environmental Management (EM)

    Es la Ley Empleados y sus Representantes tienen derecho a: Participar en el programa de seguridad y salud del lugar de trabajo, incluyendo las inspecciones que se realicen;...

  14. Job Safety and Health Poster in Spanish

    Broader source: Energy.gov [DOE]

    Deben tener acceso a: Las publicaciones de seguridad y salud del Departamento de Energía; El programa de seguridad y salud en su lugar de trabajo; Este aviso de seguridad y salud; Copias de su historial médico y registros de su exposición a sustancias o condiciones tóxicas y peligrosas; y Resultados de inspecciones e investigaciones de accidentes. 2014

  15. Job Safety Health Poster Spanish 09042014.docx

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33Frequently Asked Questions for DOEtheInspection15 PATRICIAJOINTWashington,Jim Brodrick

  16. Community Power Works: Good Jobs, Green Jobs Conference | Department...

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

    given by Community Power Works at the Good Jobs, Green Jobs Conference cpwgoodjobsgreenjobs-1.pdf More Documents & Publications Community Power Works Better Buildings...

  17. GREEN JOBS PROJECT Daniel Kammen

    E-Print Network [OSTI]

    Kammen, Daniel M.

    GREEN JOBS PROJECT Memo Daniel Kammen Meng Cai Karim El Alami December 2nd , 2014 #12;Contents.............................................................................................................................................3 1 Base of the Green jobs project per state ........................................................................................3 1.1 The Green jobs project from 2009

  18. NERSC Job Logs and Analytics

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

    For Users Job Logs & Analytics Job Logs & Analytics Queue Status A listing of jobs running and waiting in the queues (NERSC login required). Queue Wait Times Batch Queue Wait...

  19. Final safety analysis report for the Galileo Mission: Volume 2, Book 2: Accident model document: Appendices

    SciTech Connect (OSTI)

    Not Available

    1988-12-15T23:59:59.000Z

    This section of the Accident Model Document (AMD) presents the appendices which describe the various analyses that have been conducted for use in the Galileo Final Safety Analysis Report II, Volume II. Included in these appendices are the approaches, techniques, conditions and assumptions used in the development of the analytical models plus the detailed results of the analyses. Also included in these appendices are summaries of the accidents and their associated probabilities and environment models taken from the Shuttle Data Book (NSTS-08116), plus summaries of the several segments of the recent GPHS safety test program. The information presented in these appendices is used in Section 3.0 of the AMD to develop the Failure/Abort Sequence Trees (FASTs) and to determine the fuel releases (source terms) resulting from the potential Space Shuttle/IUS accidents throughout the missions.

  20. Languages Mentor Job description

    E-Print Network [OSTI]

    Anderson, Jim

    Blue 1 Languages Mentor Job description Department: Student Administration and Registry Location: Varies - as advised by the Outreach and Partnership Team Job title: Languages Mentor Responsible to: UK overall for e-mentoring 4 mentees (based on a rate of £6.42 per hour this amounts an average of 30 minutes

  1. Quality Jobs Investment Program (Oklahoma)

    Broader source: Energy.gov [DOE]

    The Oklahoma Quality Jobs Program allows qualifying businesses which are creating new quality jobs to receive a special incentive to locate or expand in Oklahoma.

  2. SOS8520 Organizational perspectives on safety conference of The Society for Risk Analysis Europe (SRAE) will be held June 17th

    E-Print Network [OSTI]

    Malinnikova, Eugenia

    SOS8520 Organizational perspectives on safety The 22nd conference of The Society for Risk Analysis (June 20th ­ 21st ) focusing on Organizational perspectives on safety The primary target group

  3. FAQS Qualification Card – Criticality Safety

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  4. Fusion integral experiments and analysis and the determination of design safety factors - I: Methodology

    SciTech Connect (OSTI)

    Youssef, M.Z.; Kumar, A.; Abdou, M.A. [Univ. of California, Los Angeles, CA (United States); Oyama, Y.; Maekawa, H. [Japan Atomic Energy Research Inst., Ibaraki (Japan)

    1995-09-01T23:59:59.000Z

    The role of the neutronics experimentation and analysis in fusion neutronics research and development programs is discussed. A new methodology was developed to arrive at estimates to design safety factors based on the experimental and analytical results from design-oriented integral experiments. In this methodology, and for a particular nuclear response, R, a normalized density function (NDF) is constructed from the prediction uncertainties, and their associated standard deviations, as found in the various integral experiments where that response, R, is measured. Important statistical parameters are derived from the NDF, such as the global mean prediction uncertainty, and the possible spread around it. The method of deriving safety factors from many possible NDFs based on various calculational and measuring methods (among other variants) is also described. Associated with each safety factor is a confidence level, designers may choose to have, that the calculated response, R, will not exceed (or will not fall below) the actual measured value. An illustrative example is given on how to construct the NDFs. The methodology is applied in two areas, namely the line-integrated tritium production rate and bulk shielding integral experiments. Conditions under which these factors could be derived and the validity of the method are discussed. 72 refs., 17 figs., 4 tabs.

  5. Job Application Portal Manual for the Job Application Portal

    E-Print Network [OSTI]

    Johannesson, Henrik

    Job Application Portal Manual for the Job Application Portal in the University of Gothenburg e-recruitment system #12;The University of Gothenburg 2/10 Contents The University of Gothenburg's Job Application.............................................................................................................................................. 10 #12;The University of Gothenburg 3/10 The University of Gothenburg's Job Application Portal

  6. The Job Search: From Graduate Student to Job

    E-Print Network [OSTI]

    Sheridan, Jennifer

    The Job Search: From Graduate Student to Job Applicant: Putting the Pieces Together Presented by: Tiffany Bachmann, M.A. #12;Introduction · Planning Your Job Search · When to Use a C.V. versus a Résumé = An NIH form document that is a hybrid of the C.V. and Résumé #12;Planning Your Job Search · Have I

  7. Moldable Parallel Job Scheduling Using Job Efficiency: An Iterative Approach

    E-Print Network [OSTI]

    Feitelson, Dror

    Moldable Parallel Job Scheduling Using Job Efficiency: An Iterative Approach Gerald Sabin, Matthew OH 43201, USA, {sabin, langma, saday}@cse.ohio-state.edu Abstract. Currently, job schedulers require "rigid" job submissions from users, who must specify a particular number of processors for each paral

  8. Eect of Job Size Characteristics on Job Scheduling Performance

    E-Print Network [OSTI]

    Feitelson, Dror

    Eect of Job Size Characteristics on Job Scheduling Performance Kento Aida Department an ap- propriate scheduling algorithm that schedules mul- tiple jobs on the computer system eciently. The goal of the work presented in this paper is to inves- tigate mechanisms how job size characteristics

  9. PARTI: JOB DESCRIPTION Weighted Job Questionnaire(WJQ) Custom

    E-Print Network [OSTI]

    Kavanagh, Karen L.

    PARTI: JOB DESCRIPTION Weighted Job Questionnaire(WJQ) Custom Department Name: SFU Document WEIGHTEDJOBQUESTIONNAIRE(WJQ)CUSTO PARTI: JOB DESCRIPTION 1. POSITION IDENTIFICATION Department Position Title: Customer at all times. Provides cost estimates for basic jobs and produces production reports using the Print

  10. Breach and safety analysis of spills over water from large liquefied natural gas carriers.

    SciTech Connect (OSTI)

    Hightower, Marion Michael; Luketa-Hanlin, Anay Josephine; Attaway, Stephen W.

    2008-05-01T23:59:59.000Z

    In 2004, at the request of the Department of Energy, Sandia National Laboratories (Sandia) prepared a report, ''Guidance on the Risk and Safety Analysis of Large Liquefied Natural Gas (LNG) Spills Over Water''. That report provided framework for assessing hazards and identifying approaches to minimize the consequences to people and property from an LNG spill over water. The report also presented the general scale of possible hazards from a spill from 125,000 m3 o 150,000 m3 class LNG carriers, at the time the most common LNG carrier capacity.

  11. Safety Analysis Report for Packaging: The unirradiated fuel shipping container USA/9853/AF

    SciTech Connect (OSTI)

    Not Available

    1991-10-18T23:59:59.000Z

    The HFBR Unirradiated Fuel Shipping Container was designed and fabricated at the Oak Ridge National Laboratory in 1978 for the transport of fuel for the High Flux Beam Reactor (HFBR) for Brookhaven National Laboratory. The package has been evaluated analytically, as well as the comparison to tests on similar packages, to demonstrate compliance with the applicable regulations governing packages in which radioactive and fissile materials are transported. The contents of this Safety Analysis Report for Packaging (SARP) are based on Regulatory Guide 7.9 (proposed Revision 2 - May 1986), 10 CFR Part 71, DOE Order 1540.2, DOE Order 5480.3, and 49 CFR Part 173.

  12. Preliminary Safety Analysis Report (PSAR), The NSLS 200 MeV Linear Electron Accelerator

    SciTech Connect (OSTI)

    Blumberg, L.N.; Ackerman, A.I.; Dickinson, T.; Heese, R.N.; Larson, R.A.; Neuls, C.W.; Pjerov, S.; Sheehan, J.F.

    1993-06-15T23:59:59.000Z

    The radiological, fire and electrical hazards posed by a 200 MeV electron Linear Accelerator, which the NSLS Department will install and commission within a newly assembled structure, are addressed in this Preliminary Safety Analysis Report. Although it is clear that this accelerator is intended to be the injector for a future experimental facility, we address only the Linac in the present PSAR since neither the final design nor the operating characteristics of the experimental facility are known at the present time. The fire detection and control system to be installed in the building is judged to be completely adequate in terms of the marginal hazard presented - no combustible materials other than the usual cabling associated with such a facility have been identified. Likewise, electrical hazards associated with power supplies for the beam transport magnets and accelerator components such as the accelerator klystrons and electron gun are classified as marginal in terms of potential personnel injury, cost of equipment lost, program downtime and public impact perceptions as defined in the BNL Environmental Safety and Health Manual and the probability of occurrence is deemed to be remote. No unusual features have been identified for the power supplies or electrical distribution system, and normal and customary electrical safety standards as practiced throughout the NSLS complex and the Laboratory are specified in this report. The radiation safety hazards are similarly judged to be marginal in terms of probability of occurrence and potential injury consequences since, for the low intensity operation proposed - a factor of 25 less than the maximum Linac capability specified by the vendor - the average beam power is only 0.4 watts. The shielding specifications given in this report will give adequate protection to both the general public and nonradiation workers in areas adjacent to the building as well as radiation workers within the controlled access building.

  13. Jobs | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOnItemResearch > The Energy Materials Center atdiffusivitiesTechnologies |JobJobsJobs We

  14. WEBSITE RESOURCES FOR GREEN JOBS

    E-Print Network [OSTI]

    Edwards, Paul N.

    of worldwide environmental jobs http://www.justmeans.com/index.php?action=jobsearch ­ List of environmentally jobs in the U.S. & worldwide http://www.sustainlane.com/greenjobs ­ Online community for green Green Jobs Task Force http://www.jobsinbiofuels.com/ ­ Ethanol and biofuel jobs http

  15. Jobs and Economic Development Modeling

    Broader source: Energy.gov [DOE]

    Project objective: Develop models to estimate jobs and economic impacts from geothermal project development and operation.

  16. Job Placement Manual Human Resources

    E-Print Network [OSTI]

    Habib, Ayman

    Job Placement Manual Human Resources Fall 2001 for bargaining unit positions as per the Collective;- 1 - University of Calgary Job Family Definitions General The General job family encompasses, production, light construction, or facility maintenance. Positions in this job family often support a service

  17. Job Families Booklet Human Resources

    E-Print Network [OSTI]

    Doran, Simon J.

    Job Families Booklet Human Resources University of Surrey #12;Job Families summarise the main features of roles which are similar in character and engaged in broadly similar work. There are four Job Families, which will cover the vast majority of jobs within the University. They are: · Operational

  18. Safety Bulletin

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

    in the documented safety analysis. BACKGROUND On March 11 , 2011 , the Fukushima Daiichi nuclear power station in Japan was damaged by a magnitude 9.0 earthquake and the...

  19. Los Alamos National Laboratory corregated metal pipe saw facility preliminary safety analysis report. Volume I

    SciTech Connect (OSTI)

    NONE

    1990-09-19T23:59:59.000Z

    This Preliminary Safety Analysis Report addresses site assessment, facility design and construction, and design operation of the processing systems in the Corrugated Metal Pipe Saw Facility with respect to normal and abnormal conditions. Potential hazards are identified, credible accidents relative to the operation of the facility and the process systems are analyzed, and the consequences of postulated accidents are presented. The risk associated with normal operations, abnormal operations, and natural phenomena are analyzed. The accident analysis presented shows that the impact of the facility will be acceptable for all foreseeable normal and abnormal conditions of operation. Specifically, under normal conditions the facility will have impacts within the limits posted by applicable DOE guidelines, and in accident conditions the facility will similarly meet or exceed the requirements of all applicable standards. 16 figs., 6 tabs.

  20. Probabilistic risk analysis toward cost-effective 3S (safety, safeguards, security) implementation

    SciTech Connect (OSTI)

    Suzuki, Mitsutoshi; Mochiji, Toshiro [Department of Science and Technology for Nuclear Material Management, Japan Atomic Energy Agency, 2-4 Shirane, Shirakata, Tokai-mura, Naka-gun, Ibaraki 319-1193 (Japan)

    2014-09-30T23:59:59.000Z

    Probabilistic Risk Analysis (PRA) has been introduced for several decades in safety and nuclear advanced countries have already used this methodology in their own regulatory systems. However, PRA has not been developed in safeguards and security so far because of inherent difficulties in intentional and malicious acts. In this paper, probabilistic proliferation and risk analysis based on random process is applied to hypothetical reprocessing process and physical protection system in nuclear reactor with the Markov model that was originally developed by the Proliferation Resistance and Physical Protection Working Group (PRPPWG) in Generation IV International Framework (GIF). Through the challenge to quantify the security risk with a frequency in this model, integrated risk notion among 3S to pursue the cost-effective installation of those countermeasures is discussed in a heroic manner.

  1. Exploration of high-dimensional scalar function for nuclear reactor safety analysis and visualization

    SciTech Connect (OSTI)

    Maljovec, D.; Wang, B.; Pascucci, V. [Scientific Computing and Imaging Institute, University of Utah (United States); Bremer, P. T. [Lawrence Livermore National Laboratory (United States); Pernice, M.; Mandelli, D.; Nourgaliev, R. [Idaho National Laboratory (United States)

    2013-07-01T23:59:59.000Z

    The next generation of methodologies for nuclear reactor Probabilistic Risk Assessment (PRA) explicitly accounts for the time element in modeling the probabilistic system evolution and uses numerical simulation tools to account for possible dependencies between failure events. The Monte-Carlo (MC) and the Dynamic Event Tree (DET) approaches belong to this new class of dynamic PRA methodologies. A challenge of dynamic PRA algorithms is the large amount of data they produce which may be difficult to visualize and analyze in order to extract useful information. We present a software tool that is designed to address these goals. We model a large-scale nuclear simulation dataset as a high-dimensional scalar function defined over a discrete sample of the domain. First, we provide structural analysis of such a function at multiple scales and provide insight into the relationship between the input parameters and the output. Second, we enable exploratory analysis for users, where we help the users to differentiate features from noise through multi-scale analysis on an interactive platform, based on domain knowledge and data characterization. Our analysis is performed by exploiting the topological and geometric properties of the domain, building statistical models based on its topological segmentations and providing interactive visual interfaces to facilitate such explorations. We provide a user's guide to our software tool by highlighting its analysis and visualization capabilities, along with a use case involving data from a nuclear reactor safety simulation. (authors)

  2. Exploration of High-Dimensional Scalar Function for Nuclear Reactor Safety Analysis and Visualization

    SciTech Connect (OSTI)

    Dan Maljovec; Bei Wang; Valerio Pascucci; Peer-Timo Bremer; Michael Pernice; Robert Nourgaliev

    2013-05-01T23:59:59.000Z

    The next generation of methodologies for nuclear reactor Probabilistic Risk Assessment (PRA) explicitly accounts for the time element in modeling the probabilistic system evolution and uses numerical simulation tools to account for possible dependencies between failure events. The Monte-Carlo (MC) and the Dynamic Event Tree (DET) approaches belong to this new class of dynamic PRA methodologies. A challenge of dynamic PRA algorithms is the large amount of data they produce which may be difficult to visualize and analyze in order to extract useful information. We present a software tool that is designed to address these goals. We model a large-scale nuclear simulation dataset as a high-dimensional scalar function defined over a discrete sample of the domain. First, we provide structural analysis of such a function at multiple scales and provide insight into the relationship between the input parameters and the output. Second, we enable exploratory analysis for users, where we help the users to differentiate features from noise through multi-scale analysis on an interactive platform, based on domain knowledge and data characterization. Our analysis is performed by exploiting the topological and geometric properties of the domain, building statistical models based on its topological segmentations and providing interactive visual interfaces to facilitate such explorations. We provide a user’s guide to our software tool by highlighting its analysis and visualization capabilities, along with a use case involving dataset from a nuclear reactor safety simulation.

  3. Job security, satisfaction influence work commitment

    E-Print Network [OSTI]

    Reinardy, Scott

    2012-01-01T23:59:59.000Z

    A nationwide survey of newspaper journalists found that coping control, perceptions of job quality and job security and organizational commitment are significant, positive predictors of job satisfaction....

  4. Safety analysis -- 200 Area Savannah River Plant, F-Canyon Operations. Supplement 4

    SciTech Connect (OSTI)

    Beary, M.M.; Collier, C.D.; Fairobent, L.A.; Graham, R.F.; Mason, C.L.; McDuffee, W.T.; Owen, T.L.; Walker, D.H.

    1986-02-01T23:59:59.000Z

    The F-Canyon facility is located in the 200 Separations Area and uses the Purex process to recover plutonium from reactor-irradiated uranium. The irradiated uranium is normally in the form of solid or hollow cylinders called slugs. These slugs are encased in aluminum cladding and are sent to the F-Canyon from the Savannah River Plant (SRP) reactor areas or from the Receiving Basin for Offsite Fuels (RBOF). This Safety Analysis Report (SAR) documents an analysis of the F-Canyon operations and is an update to a section of a previous SAR. The previous SAR documented an analysis of the entire 200 Separations Area operations. This SAR documents an analysis of the F-Canyon and is one of a series of documents for the Separations Area as specified in the Savannah River Implementation Plans. A substantial amount of the information supporting the conclusions of this SAR is found in the Systems Analysis. Some F-Canyon equipment has been updated during the time between the Systems Analysis and this SAR and a complete description of this equipment is included in this report. The primary purpose of the analysis was to demonstrate that the F-Canyon can be operated without undue risk to onsite or offsite populations and to the environment. In this report, risk is defined as the expected frequency of an accident, multiplied by the resulting radiological consequence in person-rem. The units of risk for radiological dose are person-rem/year. Maximum individual exposure values have also been calculated and reported.

  5. Safety analysis report vitrified high level waste type B shipping cask

    SciTech Connect (OSTI)

    NONE

    1995-03-01T23:59:59.000Z

    This Safety Analysis Report describes the design, analyses, and principle features of the Vitrified High Level Waste (VHLW) Cask. In preparing this report a detailed evaluation of the design has been performed to ensure that all safety, licensing, and operational goals for the cask and its associated Department of Energy program can be met. The functions of this report are: (1) to fully document that all functional and regulatory requirements of 10CFR71 can be met by the package; and (2) to document the design and analyses of the cask for review by the Nuclear Regulatory Commission. The VHLW Cask is the reusable shipping package designed by GNSI under Department of Energy contract DE-AC04-89AL53-689 for transportation of Vitrified High Level Waste, and to meet the requirements for certification under 10CFR71 for a Type B(U) package. The VHLW cask has been designed as packaging for transport of canisters of Vitrified High Level Waste solidified at Department of Energy facilities.

  6. Radiological Safety Analysis Computer (RSAC) Program Version 7.2 Users’ Manual

    SciTech Connect (OSTI)

    Dr. Bradley J Schrader

    2010-10-01T23:59:59.000Z

    The Radiological Safety Analysis Computer (RSAC) Program Version 7.2 (RSAC-7) is the newest version of the RSAC legacy code. It calculates the consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC-7 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates the decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated for inhalation, air immersion, ground surface, ingestion, and cloud gamma pathways. RSAC-7 can be used as a tool to evaluate accident conditions in emergency response scenarios, radiological sabotage events and to evaluate safety basis accident consequences. This users’ manual contains the mathematical models and operating instructions for RSAC-7. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-7. This program was designed for users who are familiar with radiological dose assessment methods.

  7. Radiological Safety Analysis Computer (RSAC) Program Version 7.0 Users’ Manual

    SciTech Connect (OSTI)

    Dr. Bradley J Schrader

    2009-03-01T23:59:59.000Z

    The Radiological Safety Analysis Computer (RSAC) Program Version 7.0 (RSAC-7) is the newest version of the RSAC legacy code. It calculates the consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC-7 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates the decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated for inhalation, air immersion, ground surface, ingestion, and cloud gamma pathways. RSAC-7 can be used as a tool to evaluate accident conditions in emergency response scenarios, radiological sabotage events and to evaluate safety basis accident consequences. This users’ manual contains the mathematical models and operating instructions for RSAC-7. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-7. This program was designed for users who are familiar with radiological dose assessment methods.

  8. Final safety analysis report for the Ground Test Accelerator (GTA), Phase 2

    SciTech Connect (OSTI)

    NONE

    1994-10-01T23:59:59.000Z

    This document is the first volume of a 3 volume safety analysis report on the Ground Test Accelerator (GTA). The GTA program at the Los Alamos National Laboratory (LANL) is the major element of the national Neutral Particle Beam (NPB) program, which is supported by the Strategic Defense Initiative Office (SDIO). A principal goal of the national NPB program is to assess the feasibility of using hydrogen and deuterium neutral particle beams outside the Earth`s atmosphere. The main effort of the NPB program at Los Alamos concentrates on developing the GTA. The GTA is classified as a low-hazard facility, except for the cryogenic-cooling system, which is classified as a moderate-hazard facility. This volume consists of an introduction, summary/conclusion, site description and assessment, description of facility, and description of operation.

  9. Simulation of accidental UF/sub 6/ releases in support of the safety analysis effort

    SciTech Connect (OSTI)

    Just, R.A.

    1986-01-01T23:59:59.000Z

    The safety analysis of the US uranium enrichment facilities requires that postulated accidental releases of UF/sub 6/ be simulated. In order to predict the human health consequences of a postulated UF/sub 6/ release, two types of information are needed: (1) predicted toxicant concentrations and exposure durations at pertinent locations (calculated by a dispersion model), and (2) toxicity data which support the assessment of the human health consequences of a known exposure to a mixture of UF/sub 6/ and UF/sub 6/ hydrolysis products. This report describes the development of a Gaussian dispersion model for simulating UF/sub 6/ dispersion and the plans for developing a puff dispersion model.

  10. The Front Lines of Patient Safety

    E-Print Network [OSTI]

    Soloveichik, David

    patient safety · Incident Reporting · Root Cause Analysis · FMEA · Culture of Patient Safety Survey

  11. Guidance on risk analysis and safety implications of a large liquefied natural gas (LNG) spill over water.

    SciTech Connect (OSTI)

    Wellman, Gerald William; Melof, Brian Matthew; Luketa-Hanlin, Anay Josephine; Hightower, Marion Michael; Covan, John Morgan; Gritzo, Louis Alan; Irwin, Michael James; Kaneshige, Michael Jiro; Morrow, Charles W.

    2004-12-01T23:59:59.000Z

    While recognized standards exist for the systematic safety analysis of potential spills or releases from LNG (Liquefied Natural Gas) storage terminals and facilities on land, no equivalent set of standards or guidance exists for the evaluation of the safety or consequences from LNG spills over water. Heightened security awareness and energy surety issues have increased industry's and the public's attention to these activities. The report reviews several existing studies of LNG spills with respect to their assumptions, inputs, models, and experimental data. Based on this review and further analysis, the report provides guidance on the appropriateness of models, assumptions, and risk management to address public safety and property relative to a potential LNG spill over water.

  12. Job quality in Europe

    E-Print Network [OSTI]

    Burchell, Brendan J.; Smith, Mark; Fagan, Colette; O’Brien, Catherine

    2008-01-01T23:59:59.000Z

    flexibility—can also lead to enhanced job quality (Bredgaard and Larsen, 2006; CEC, 2007b), for example, in the form of autonomy and job enlargement. So far, it is only in Finland and Sweden that the Commission finds evidence of such quality workplaces being... .50** — — 1.60** Ireland 0.58** — — — — Italy — 0.73** 0.62** — 0.65** Lithuania — 0.43** — — — Luxembourg — — — — — Latvia — 0.60** 1.38** — 1.50** Netherlands 1.57** 1.83** — 0.38** — Malta — — — — — Poland — — — — — Portugal — — — — — Sweden 1.97** 2...

  13. Hopper Job Size Charts

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC) EnvironmentalGyroSolé(tm) HarmonicbetandEnergy 2010 A selectionFileaprun JobJob

  14. Jobs @ the Library

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)Integrated Codes |Is Your Home as Ready for(SC) Jetting into theJieJobTypesJobs @

  15. Submitting PDSF Jobs

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of ScienceandMesa del SolStrengthening a solid ... StrengtheningLabSubmitting Jobs Submitting Jobs

  16. Job Vacancy Notice Job Title: Assistant Professor -Geology

    E-Print Network [OSTI]

    Johnson Jr.,, Ray

    1 Job Vacancy Notice Job Title: Assistant Professor - Geology Job ID: 6477 Location: Regular-track Assistant Professor in the general area of "hardrock" geology. The SEES community includes 14 full-time faculty members, 25 Masters and PhD candidates, and approximately 150 Geology, Environmental Science

  17. PiPe dreams? Jobs Gained, Jobs Lost

    E-Print Network [OSTI]

    Danforth, Bryan Nicholas

    PiPe dreams? Jobs Gained, Jobs Lost by the ConstruCtion of Keystone XL a rePort by Corne, and Induced) Jobs from Keystone XL 26 KXL Will Have Minor Impact on Unemployment Levels 27 Four Ways Keystone to the Keystone XL budget and expenditures, steel sourcing, and the costs of environmental damage. #12;Corne

  18. Job Tax Credit and Super Credit (Tennessee)

    Broader source: Energy.gov [DOE]

    The Job Tax Credit Program is a tax credit program for companies investing at least $500,000 and creating 25 new jobs in a 12-month period. The company creating these jobs can claim a Job Tax...

  19. Nebraska Customized Job Training Advantage (Nebraska)

    Broader source: Energy.gov [DOE]

    The Nebraska Customized Job Training Advantage is a flexible job training program with grants from $800-$4000 per qualified new job. Additional grant funding may be available for jobs created in...

  20. Job Tax Credit (South Carolina)

    Broader source: Energy.gov [DOE]

    The Job Tax Credit (JTC) is a statutory incentive offered to companies, both existing and new, that create new jobs in the state. The credit is available to companies that establish or expand...

  1. Excelsior Jobs Program (New York)

    Broader source: Energy.gov [DOE]

    The Excelsior Jobs Program provides a tax credit to businesses that make significant capital investments or create jobs in clean-tech and other strategic industries. Businesses may apply for up to...

  2. Corporate Jobs Tax Credit (Louisiana)

    Broader source: Energy.gov [DOE]

    Corporate Jobs Tax Credit is a one-time tax credit ranging from up to $225 for each net new permanent job created as the result of a new business start-up or the expansion of an existing one. ...

  3. Virginia Jobs Investment Program (Virginia)

    Broader source: Energy.gov [DOE]

    The Virginia Jobs Investment Program provides cash grants to existing businesses which seek expansion or new facility locations. The company must create a minimum of 25 net new jobs within 12...

  4. Job Creation Tax Credit (Maryland)

    Broader source: Energy.gov [DOE]

    The Job Creation Tax Credit provides a $1000 tax credit to businesses that create new jobs; the credit is 2.5% of the aggregate annual wages for all newly created full-time positions. This credit...

  5. Exploratory Nuclear Reactor Safety Analysis and Visualization via Integrated Topological and Geometric Techniques

    SciTech Connect (OSTI)

    Dan Maljovec; Bei Wang; Valerio Pascucci; Peer-Timo Bremer; Diego Mandelli; Michael Pernice; Robert Nourgaliev

    2013-10-01T23:59:59.000Z

    A recent trend in the nuclear power engineering field is the implementation of heavily computational and time consuming algorithms and codes for both design and safety analysis. In particular, the new generation of system analysis codes aim to embrace several phenomena such as thermo-hydraulic, structural behavior, and system dynamics, as well as uncertainty quantification and sensitivity analyses. The use of dynamic probabilistic risk assessment (PRA) methodologies allows a systematic approach to uncertainty quantification. Dynamic methodologies in PRA account for possible coupling between triggered or stochastic events through explicit consideration of the time element in system evolution, often through the use of dynamic system models (simulators). They are usually needed when the system has more than one failure mode, control loops, and/or hardware/process/software/human interaction. Dynamic methodologies are also capable of modeling the consequences of epistemic and aleatory uncertainties. The Monte-Carlo (MC) and the Dynamic Event Tree (DET) approaches belong to this new class of dynamic PRA methodologies. The major challenges in using MC and DET methodologies (as well as other dynamic methodologies) are the heavier computational and memory requirements compared to the classical ET analysis. This is due to the fact that each branch generated can contain time evolutions of a large number of variables (about 50,000 data channels are typically present in RELAP) and a large number of scenarios can be generated from a single initiating event (possibly on the order of hundreds or even thousands). Such large amounts of information are usually very difficult to organize in order to identify the main trends in scenario evolutions and the main risk contributors for each initiating event. This report aims to improve Dynamic PRA methodologies by tackling the two challenges mentioned above using: 1) adaptive sampling techniques to reduce computational cost of the analysis and 2) topology-based methodologies to interactively visualize multidimensional data and extract risk-informed insights. Regarding item 1) we employ learning algorithms that aim to infer/predict simulation outcome and decide the coordinate in the input space of the next sample that maximize the amount of information that can be gained from it. Such methodologies can be used to both explore and exploit the input space. The later one is especially used for safety analysis scopes to focus samples along the limit surface, i.e. the boundaries in the input space between system failure and system success. Regarding item 2) we present a software tool that is designed to analyze multi-dimensional data. We model a large-scale nuclear simulation dataset as a high-dimensional scalar function defined over a discrete sample of the domain. First, we provide structural analysis of such a function at multiple scales and provide insight into the relationship between the input parameters and the output. Second, we enable exploratory analysis for users, where we help the users to differentiate features from noise through multi-scale analysis on an interactive platform, based on domain knowledge and data characterization. Our analysis is performed by exploiting the topological and geometric properties of the domain, building statistical models based on its topological segmentations and providing interactive visual interfaces to facilitate such explorations.

  6. Methodology assessment and recommendations for the Mars science laboratory launch safety analysis.

    SciTech Connect (OSTI)

    Sturgis, Beverly Rainwater; Metzinger, Kurt Evan; Powers, Dana Auburn; Atcitty, Christopher B.; Robinson, David B; Hewson, John C.; Bixler, Nathan E.; Dodson, Brian W.; Potter, Donald L.; Kelly, John E.; MacLean, Heather J.; Bergeron, Kenneth Donald (Sala & Associates); Bessette, Gregory Carl; Lipinski, Ronald J.

    2006-09-01T23:59:59.000Z

    The Department of Energy has assigned to Sandia National Laboratories the responsibility of producing a Safety Analysis Report (SAR) for the plutonium-dioxide fueled Multi-Mission Radioisotope Thermoelectric Generator (MMRTG) proposed to be used in the Mars Science Laboratory (MSL) mission. The National Aeronautic and Space Administration (NASA) is anticipating a launch in fall of 2009, and the SAR will play a critical role in the launch approval process. As in past safety evaluations of MMRTG missions, a wide range of potential accident conditions differing widely in probability and seventy must be considered, and the resulting risk to the public will be presented in the form of probability distribution functions of health effects in terms of latent cancer fatalities. The basic descriptions of accident cases will be provided by NASA in the MSL SAR Databook for the mission, and on the basis of these descriptions, Sandia will apply a variety of sophisticated computational simulation tools to evaluate the potential release of plutonium dioxide, its transport to human populations, and the consequent health effects. The first step in carrying out this project is to evaluate the existing computational analysis tools (computer codes) for suitability to the analysis and, when appropriate, to identify areas where modifications or improvements are warranted. The overall calculation of health risks can be divided into three levels of analysis. Level A involves detailed simulations of the interactions of the MMRTG or its components with the broad range of insults (e.g., shrapnel, blast waves, fires) posed by the various accident environments. There are a number of candidate codes for this level; they are typically high resolution computational simulation tools that capture details of each type of interaction and that can predict damage and plutonium dioxide release for a range of choices of controlling parameters. Level B utilizes these detailed results to study many thousands of possible event sequences and to build up a statistical representation of the releases for each accident case. A code to carry out this process will have to be developed or adapted from previous MMRTG missions. Finally, Level C translates the release (or ''source term'') information from Level B into public risk by applying models for atmospheric transport and the health consequences of exposure to the released plutonium dioxide. A number of candidate codes for this level of analysis are available. This report surveys the range of available codes and tools for each of these levels and makes recommendations for which choices are best for the MSL mission. It also identities areas where improvements to the codes are needed. In some cases a second tier of codes may be identified to provide supporting or clarifying insight about particular issues. The main focus of the methodology assessment is to identify a suite of computational tools that can produce a high quality SAR that can be successfully reviewed by external bodies (such as the Interagency Nuclear Safety Review Panel) on the schedule established by NASA and DOE.

  7. Puget Sound Career & Job Resources

    E-Print Network [OSTI]

    Kaminsky, Werner

    Puget Sound Career & Job Resources The UW Career Center provides services to current UW students-8300; www.lwtech.edu/ #12;Puget Sound Career & Job Resources North Seattle Community College (206) 934, then Jobs & Careers ADDITIONAL RESOURCES Puget Sound Career Development Association (Professional Career

  8. JOB EVALUATION QUESTIONNAIRE ANSWER SHEET

    E-Print Network [OSTI]

    Amin, S. Massoud

    JOB EVALUATION QUESTIONNAIRE ANSWER SHEET DO NOT WRITE IN THIS SPACE N.C. Date Received Reclass New Starting Date in Class Yes No NA (NA if Temporary Job) Notice # Effective Date If Reclassified IS TO BE USED WITH THE JOB EVALUATION QUESTIONNAIRE (BA 802) ONLY FOR POSITIONS COVERED BY CIVIL SERVICE

  9. We schedule your job when we receive this completed request form. You then receive a JOB CONFIRMATION which will include job number, copy due date and job checklist.

    E-Print Network [OSTI]

    Sheridan, Jennifer

    We schedule your job when we receive this completed request form. You then receive a JOB CONFIRMATION which will include job number, copy due date and job checklist. JOB NAME Date Form Submitted pages) Copy to come by due date note due date on Job Confirmation Mini Catalog (12-24 pages) PROVIDE

  10. Processes and Procedures for Application of CFD to Nuclear Reactor Safety Analysis

    SciTech Connect (OSTI)

    Richard W. Johnson; Richard R. Schultz; Patrick J. Roache; Ismail B. Celik; William D. Pointer; Yassin A. Hassan

    2006-09-01T23:59:59.000Z

    Traditionally, nuclear reactor safety analysis has been performed using systems analysis codes such as RELAP5, which was developed at the INL. However, goals established by the Generation IV program, especially the desire to increase efficiency, has lead to an increase in operating temperatures for the reactors. This increase pushes reactor materials to operate towards their upper temperature limits relative to structural integrity. Because there will be some finite variation of the power density in the reactor core, there will be a potential for local hot spots to occur in the reactor vessel. Hence, it has become apparent that detailed analysis will be required to ensure that local ‘hot spots’ do not exceed safety limits. It is generally accepted that computational fluid dynamics (CFD) codes are intrinsically capable of simulating fluid dynamics and heat transport locally because they are based on ‘first principles.’ Indeed, CFD analysis has reached a fairly mature level of development, including the commercial level. However, CFD experts are aware that even though commercial codes are capable of simulating local fluid and thermal physics, great care must be taken in their application to avoid errors caused by such things as inappropriate grid meshing, low-order discretization schemes, lack of iterative convergence and inaccurate time-stepping. Just as important is the choice of a turbulence model for turbulent flow simulation. Turbulence models model the effects of turbulent transport of mass, momentum and energy, but are not necessarily applicable for wide ranges of flow types. Therefore, there is a well-recognized need to establish practices and procedures for the proper application of CFD to simulate flow physics accurately and establish the level of uncertainty of such computations. The present document represents contributions of CFD experts on what the basic practices, procedures and guidelines should be to aid CFD analysts to obtain accurate estimates of the flow and energy transport as applied to nuclear reactor safety. However, it is expected that these practices and procedures will require updating from time to time as research and development affect them or replace them with better procedures. The practices and procedures are categorized into five groups. These are: 1.Code Verification 2.Code and Calculation Documentation 3.Reduction of Numerical Error 4.Quantification of Numerical Uncertainty (Calculation Verification) 5.Calculation Validation. These five categories have been identified from procedures currently required of CFD simulations such as those required for publication of a paper in the ASME Journal of Fluids Engineering and from the literature such as Roache [1998]. Code verification refers to the demonstration that the equations of fluid and energy transport have been correctly coded in the CFD code. Code and calculation documentation simply means that the equations and their discretizations, etc., and boundary and initial conditions used to pose the fluid flow problem are fully described in available documentation. Reduction of numerical error refers to practices and procedures to lower numerical errors to negligible or very low levels as is reasonably possible (such as avoiding use of first-order discretizations). The quantification of numerical uncertainty is also known as calculation verification. This means that estimates are made of numerical error to allow the characterization of the numerical

  11. Plutonium Finishing Plant (PFP) Final Safety Analysis Report (FSAR) [SEC 1 THRU 11

    SciTech Connect (OSTI)

    ULLAH, M K

    2001-02-26T23:59:59.000Z

    The Plutonium Finishing Plant (PFP) is located on the US Department of Energy (DOE) Hanford Site in south central Washington State. The DOE Richland Operations (DOE-RL) Project Hanford Management Contract (PHMC) is with Fluor Hanford Inc. (FH). Westinghouse Safety Management Systems (WSMS) provides management support to the PFP facility. Since 1991, the mission of the PFP has changed from plutonium material processing to preparation for decontamination and decommissioning (D and D). The PFP is in transition between its previous mission and the proposed D and D mission. The objective of the transition is to place the facility into a stable state for long-term storage of plutonium materials before final disposition of the facility. Accordingly, this update of the Final Safety Analysis Report (FSAR) reflects the current status of the buildings, equipment, and operations during this transition. The primary product of the PFP was plutonium metal in the form of 2.2-kg, cylindrical ingots called buttoms. Plutonium nitrate was one of several chemical compounds containing plutonium that were produced as an intermediate processing product. Plutonium recovery was performed at the Plutonium Reclamation Facility (PRF) and plutonium conversion (from a nitrate form to a metal form) was performed at the Remote Mechanical C (RMC) Line as the primary processes. Plutonium oxide was also produced at the Remote Mechanical A (RMA) Line. Plutonium processed at the PFP contained both weapons-grade and fuels-grade plutonium materials. The capability existed to process both weapons-grade and fuels-grade material through the PRF and only weapons-grade material through the RMC Line although fuels-grade material was processed through the line before 1984. Amounts of these materials exist in storage throughout the facility in various residual forms left from previous years of operations.

  12. Documented Safety Analysis Addendum for the Neutron Radiography Reactor Facility Core Conversion

    SciTech Connect (OSTI)

    Boyd D. Christensen

    2009-05-01T23:59:59.000Z

    The Neutron Radiography Reactor Facility (NRAD) is a Training, Research, Isotope Production, General Atomics (TRIGA) reactor which was installed in the Idaho National Laboratory (INL) Hot Fuels Examination Facility (HFEF) at the Materials and Fuels Complex (MFC) in the mid 1970s. The facility provides researchers the capability to examine both irradiated and non-irradiated materials in support of reactor fuel and components programs through non-destructive neutron radiography examination. The facility has been used in the past as one facet of a suite of reactor fuels and component examination facilities available to researchers at the INL and throughout the DOE complex. The facility has also served various commercial research activities in addition to the DOE research and development support. The reactor was initially constructed using Fuel Lifetime Improvement Program (FLIP)- type highly enriched uranium (HEU) fuel obtained from the dismantled Puerto Rico Nuclear Center (PRNC) reactor. In accordance with international non-proliferation agreements, the NRAD core will be converted to a low enriched uranium (LEU) fuel and will continue to utilize the PRNC control rods, control rod drives, startup source, and instrument console as was previously used with the HEU core. The existing NRAD Safety Analysis Report (SAR) was created and maintained in the preferred format of the day, combining sections of both DOE-STD-3009 and Nuclear Regulatory Commission Regulatory Guide 1.70. An addendum was developed to cover the refueling and reactor operation with the LEU core. This addendum follows the existing SAR format combining required formats from both the DOE and NRC. This paper discusses the project to successfully write a compliant and approved addendum to the existing safety basis documents.

  13. Pantex Plant final safety analysis report, Zone 4 magazines. Staging or interim storage for nuclear weapons and components: Issue D

    SciTech Connect (OSTI)

    Not Available

    1993-04-01T23:59:59.000Z

    This Safety Analysis Report (SAR) contains a detailed description and evaluation of the significant environmental, safety, and health (ES&H) issues associated with the operations of the Pantex Plant modified-Richmond and steel arch construction (SAC) magazines in Zone 4. It provides (1) an overall description of the magazines, the Pantex Plant, and its surroundings; (2) a systematic evaluations of the hazards that could occur as a result of the operations performed in these magazines; (3) descriptions and analyses of the adequacy of the measures taken to eliminate, control, or mitigate the identified hazards; and (4) analyses of potential accidents and their associated risks.

  14. American Jobs Creation Act of 2004 (released in AEO2005)

    Reports and Publications (EIA)

    2005-01-01T23:59:59.000Z

    The American Jobs Creation Act of 2004 was signed into law on October 22, 2004. Most of the 650 pages of the Act are related to tax legislation. Provisions pertaining to energy are detailed in this analysis.

  15. Program Direction and Analysis Jobs

    Office of Science (SC) Website

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron4(SC) Mapping the Impact ofHome Pacific NorthwestHomePrivacy

  16. Facility Safety

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

    1996-10-24T23:59:59.000Z

    Establishes facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation.

  17. Facility Safety

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

    1995-11-16T23:59:59.000Z

    Establishes facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation.

  18. A Comparison of the Safety Analysis Process and the Generation IV Proliferation Resistance/Physical Protection Assessment Methodology

    SciTech Connect (OSTI)

    T. A. Bjornard; M. D. Zentner

    2006-05-01T23:59:59.000Z

    The Generation IV International Forum (GIF) is a vehicle for the cooperative international development of future nuclear energy systems. The Generation IV program has established primary objectives in the areas of sustainability, economics, safety and reliability, and Proliferation Resistance and Physical Protection (PR&PP). In order to help meet the latter objective a program was launched in December 2002 to develop a rigorous means to assess nuclear energy systems with respect to PR&PP. The study of Physical Protection of a facility is a relatively well established methodology, but an approach to evaluate the Proliferation Resistance of a nuclear fuel cycle is not. This paper will examine the Proliferation Resistance (PR) evaluation methodology being developed by the PR group, which is largely a new approach and compare it to generally accepted nuclear facility safety evaluation methodologies. Safety evaluation methods have been the subjects of decades of development and use. Further, safety design and analysis is fairly broadly understood, as well as being the subject of federally mandated procedures and requirements. It is therefore extremely instructive to compare and contrast the proposed new PR evaluation methodology process with that used in safety analysis. By so doing, instructive and useful conclusions can be derived from the comparison that will help to strengthen the PR methodological approach as it is developed further. From the comparison made in this paper it is evident that there are very strong parallels between the two processes. Most importantly, it is clear that the proliferation resistance aspects of nuclear energy systems are best considered beginning at the very outset of the design process. Only in this way can the designer identify and cost effectively incorporate intrinsic features that might be difficult to implement at some later stage. Also, just like safety, the process to implement proliferation resistance should be a dynamic, iterative process that continually evolves with the design.

  19. This guide will help you navigate USC's online job system, JobMate. Through JobMate you can:This guide will help you navigate USC's online job system, JobMate. Through JobMate you can:This guide will help you navigate USC's online job system, JobMate. Thr

    E-Print Network [OSTI]

    Almor, Amit

    This guide will help you navigate USC's online job system, JobMate. Through JobMate you can:This guide will help you navigate USC's online job system, JobMate. Through JobMate you can:This guide will help you navigate USC's online job system, JobMate. Through JobMate you can:This guide will help you

  20. Submersion Criticality Safety Analysis of Tungsten-Based Fuel for Nuclear Power and Propulsion Applications

    SciTech Connect (OSTI)

    A.E. Craft; R. C. O'Brien; S. D. Howe; J. C. King

    2014-07-01T23:59:59.000Z

    The Center for Space Nuclear Research (CSNR) is developing tungsten-encapsulated fuels for space nuclear applications. Aims to develop NTP fuels that are; Affordable Low impact on production and testing environment Producible on a large scale over suitable time period Higher-performance compared to previous graphite NTP fuel elements Space nuclear reactors remain subcritical before and during launch, and do not go critical until required by its mission. A properly designed reactor will remain subcritical in any launch abort scenario, where the reactor falls back to Earth and becomes submerged in terrestrial material. Submersion increases neutron reflection and thermalizes the neutrons, which typically increases the reactivity of the core. This effect is usually very significant for fast-spectrum reactors. This research provided a submersion criticality safety analysis for a representative tungsten/uranium oxide fueled reactor. Determine the submersion behavior of a reactor fueled by tungsten-based fuel. Considered fuel compositions with varying: Rhenium content (wt% rhenium in tungsten) Fuel loading fractions (UO2 vol%)

  1. Safety analysis report for the TRUPACT-II shipping package (condensed version). Volume 2, Rev. 14

    SciTech Connect (OSTI)

    NONE

    1994-10-01T23:59:59.000Z

    This appendix determines the effective G values for payload shipping categories of contact handled transuranic (CH-TRU) waste materials, based on the radiolytic G values for waste materials that are discussed in detail in Appendix 3.6.8 of the Safety Analysis Report for the TRUPACT-II Shipping Package. The effective G values take into account self-absorption of alpha decay energy inside particulate contamination and the fraction of energy absorbed by nongas-generating materials. As described in Appendix 3.6.8, an effective G value, G{sub eff}, is defined by: G{sub eff} - {Sigma}{sub M} (F{sub M} x G{sub M}) F{sub M}-fraction of energy absorbed by material maximum G value for a material where the sum is over all materials present inside a waste container. The G value itself is determined primarily by the chemical properties of the material and its temperature. The value of F is determined primarily by the size of the particles containing the radionuclides, the distribution of radioactivity on the various materials present inside the waste container, and the stopping distance of alpha particles in air, in the waste materials, or in the waste packaging materials.

  2. The safety climate of a Department of Energy nuclear facility: A sociotechnical analysis

    SciTech Connect (OSTI)

    Johnson, A.E.; Harbour, J.L.

    1993-06-01T23:59:59.000Z

    Government- and public-sponsored groups are increasingly demanding greater accountability by the Department of Energy`s weapons complex. Many of these demands have focused on the development of a positive safety climate, one that not only protects workers onsite, but also the surrounding populace and environment as well. These demands are, in part, a response to findings which demonstrate a close linkage between actual organizational safety performance and the organization`s safety climate, i.e., the collective attitudes employees hold concerning the level of safety in their organization. This paper describes the approach taken in the systematic assessment of the safety climate at EG&G Rocky Flats Plant (RFP).

  3. Safety Analysis of the US Dual Coolant Liquid Lead-Lithium ITER Test Blanket Module

    SciTech Connect (OSTI)

    Merrill, Brad; Reyes, Susana; Sawan, Mohamed; Wong, Clement

    2006-07-01T23:59:59.000Z

    The US is proposing a prototype of a dual coolant liquid lead-lithium (DCLL) DEMO blanket concept for testing in the International Thermonuclear Experimental Reactor (ITER) as an ITER Test Blanket Module (TBM). Because safety considerations are an integral part of the design process to ensure that this TBM does not adversely impact the safety of ITER, a safety assessment has been conducted for this TBM and its ancillary systems as requested by the ITER project. Four events were selected by the ITER International Team (IT) to address specific reactor safety concerns, such as VV pressurization, confinement building pressure build-up, TBM decay heat removal capability, tritium and activation products release from the TBM system, and hydrogen and heat production from chemical reactions. This paper summarizes the results of this safety assessment conducted with the MELCOR computer code.

  4. Overview of New Tools to Perform Safety Analysis: BWR Station Black Out Test Case

    SciTech Connect (OSTI)

    D. Mandelli; C. Smith; T. Riley; J. Nielsen; J. Schroeder; C. Rabiti; A. Alfonsi; Cogliati; R. Kinoshita; V. Pasucci; B. Wang; D. Maljovec

    2014-06-01T23:59:59.000Z

    Dynamic Probabilistic Risk Assessment (DPRA) methodologies couple system simulator codes (e.g., RELAP, MELCOR) with simulation controller codes (e.g., RAVEN, ADAPT). While system simulator codes accurately model system dynamics deterministically, simulation controller codes introduce both deterministic (e.g., system control logic, operating procedures) and stochastic (e.g., component failures, parameter uncertainties) elements into the simulation. Typically, a DPRA is performed by: 1) sampling values of a set of parameters from the uncertainty space of interest (using the simulation controller codes), and 2) simulating the system behavior for that specific set of parameter values (using the system simulator codes). For complex systems, one of the major challenges in using DPRA methodologies is to analyze the large amount of information (i.e., large number of scenarios ) generated, where clustering techniques are typically employed to allow users to better organize and interpret the data. In this paper, we focus on the analysis of a nuclear simulation dataset that is part of the Risk Informed Safety Margin Characterization (RISMC) Boiling Water Reactor (BWR) station blackout (SBO) case study. We apply a software tool that provides the domain experts with an interactive analysis and visualization environment for understanding the structures of such high-dimensional nuclear simulation datasets. Our tool encodes traditional and topology-based clustering techniques, where the latter partitions the data points into clusters based on their uniform gradient flow behavior. We demonstrate through our case study that both types of clustering techniques complement each other in bringing enhanced structural understanding of the data.

  5. FAQS Qualification Card- Aviation Safety Officer

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  6. FAQS Qualification Card – Safety Software Quality Assurance

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  7. FAQS Qualification Card – Senior Technical Safety Manager

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  8. FAQS Qualification Card – Nuclear Explosive Safety Study

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  9. Nuclear criticality safety bounding analysis for the in-tank-precipitation (ITP) process, impacted by fissile isotopic weight fractions

    SciTech Connect (OSTI)

    Bess, C.E.

    1994-04-22T23:59:59.000Z

    The In-Tank Precipitation process (ITP) receives High Level Waste (HLW) supernatant liquid containing radionuclides in waste processing tank 48H. Sodium tetraphenylborate, NaTPB, and monosodium titanate (MST), NaTi{sub 2}O{sub 5}H, are added for removal of radioactive Cs and Sr, respectively. In addition to removal of radio-strontium, MST will also remove plutonium and uranium. The majority of the feed solutions to ITP will come from the dissolution of supernate that had been concentrated by evaporation to a crystallized salt form, commonly referred to as saltcake. The concern for criticality safety arises from the adsorption of U and Pt onto MST. If sufficient mass and optimum conditions are achieved then criticality is credible. The concentration of u and Pt from solution into the smaller volume of precipitate represents a concern for criticality. This report supplements WSRC-TR-93-171, Nuclear Criticality Safety Bounding Analysis For The In-Tank-Precipitation (ITP) Process. Criticality safety in ITP can be analyzed by two bounding conditions: (1) the minimum safe ratio of MST to fissionable material and (2) the maximum fissionable material adsorption capacity of the MST. Calculations have provided the first bounding condition and experimental analysis has established the second. This report combines these conditions with canyon facility data to evaluate the potential for criticality in the ITP process due to the adsorption of the fissionable material from solution. In addition, this report analyzes the potential impact of increased U loading onto MST. Results of this analysis demonstrate a greater safety margin for ITP operations than the previous analysis. This report further demonstrates that the potential for criticality in the ITP process due to adsorption of fissionable material by MST is not credible.

  10. DOE Updates JOBS and Economic Impacts of Fuel Cells (JOBS FC1...

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

    Updates JOBS and Economic Impacts of Fuel Cells (JOBS FC1.1) Model DOE Updates JOBS and Economic Impacts of Fuel Cells (JOBS FC1.1) Model Download the presentation slides from the...

  11. Job Dislocation Making Smart Financial Choices

    E-Print Network [OSTI]

    Job Dislocation Making Smart Financial Choices after a Job Loss #12;Who We Are FINRA FINRA.workforceatm.org. #12;Job Dislocation MAKING SMART FINANCIAL CHOICES AFTER A JOB LOSS You may not be able to control in the event of unemployment; protect yourself when getting financial advice during a period of job dislocation

  12. Beyond Academia: How to Find a Job

    E-Print Network [OSTI]

    Kaminsky, Werner

    Beyond Academia: How to Find a Job A critical piece of the job search process is knowing where and how to search for positions. This handout describes many different ways to find jobs outside academia by the job-hunter, asking for proof of what the job- hunter can do Contacts: Using a friend or business

  13. Analysis of improvements in system efficiency and safety at highway-railroad-pedestrian grade crossings

    E-Print Network [OSTI]

    Tydlacka, Jonathan Michael

    2013-02-22T23:59:59.000Z

    The purpose of this project was to perform micro-simulation analyses on intersections near Highway-Railroad Grade Crossings to determine if controlling mean train speed and train speed variability would improve safety and reduce delays. The first...

  14. Fusion Engineering and Design 80 (2006) 111137 ARIES-AT safety design and analysis

    E-Print Network [OSTI]

    that mobilize in-vessel inventories (e.g., tritium and tokamak dust) and bypass primary confinement (LOCA) and loss of flow accident (LOFA); Inventories; Safety; Environment studies 1. Background

  15. NASA/TM-2007-214856 Safety and Performance Analysis of the

    E-Print Network [OSTI]

    Muñoz, César A.

    Hanover, MD 21076-1320 #12;National Aeronautics and Space Administration Langley Research Center Hampton Hanover, MD 21076-1320 Springfield, VA 22161-2171 (301) 621-0390 (703) 605-6000 #12;Safety and Performance

  16. Department of Mathematics: Math Jobs

    E-Print Network [OSTI]

    Below we have attempted to collect a number of links to information on finding jobs in mathematics. Good luck! Seeking Employment in the Mathematical ...

  17. Finding a Job in Mathematics

    E-Print Network [OSTI]

    Below we have attempted to collect a number of links to information on finding jobs ... (Purdue); The National Security Agency is reputed to be the world's largest ...

  18. Submitting Batch Jobs on Franklin

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

    Pacific Time, 256 nodes are reserved for debugging and interactive use. See also, running Interactive Jobs. Sample Batch Scripts The following batch script requests 8 cores on...

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

    SciTech Connect (OSTI)

    CARRELL, R D

    2002-07-16T23:59:59.000Z

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

  20. Statistical Analysis of Occupational Safety Data of Voluntary Protection Program (VPP) and Non-VPP Sites

    Broader source: Energy.gov [DOE]

    The Voluntary Protection Program (VPP) was originally developed by Occupational Safety and Health Administration (OSHA) in 1982 to foster greater ownership of safety and health in the workplace. The Department of Energy (DOE) adopted VPP in 1992; currently 23 sites across the DOE complex participate in the program. As its name implies, it is a voluntary program; i.e. not required by laws or regulations.

  1. High Energy Physics Jobs

    Office of Science (SC) Website

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron4 Self-Scrubbing:,,ofOpportunitieshighlights/ The Office ofabout/jobs/

  2. Integrated Support Center Jobs

    Office of Science (SC) Website

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron4 Self-Scrubbing:,,ofOpportunitieshighlights/ Theisc/about/jobs/ Below is

  3. Nuclear Physics Jobs

    Office of Science (SC) Website

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron4(SC) Mapping the Impact of ResearchNPNSBabout/jobs/ Below is a list

  4. Operations Program Management Jobs

    Office of Science (SC) Website

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron4(SC) Mapping the Impact of ResearchNPNSBabout/jobs/CeO2

  5. Sandia Energy - Job Listing

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Scienceand RequirementsCoatingsUltra-High-VoltagePowerUpdates Techno-Economic Modeling ToolsJob

  6. Pending Jobs by Group

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)IntegratedSpeeding access toTestPhysicsParticipantsPartnersC.Payroll CheckPending Jobs

  7. Training Worksheet Job Aid

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of ScienceandMesa del SolStrengthening a solidSynthesisAppliances » TopToursTraining Worksheet Job Aid

  8. Using PDSF Job Arrays

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of ScienceandMesa del SolStrengthening aTurbulence mayUndergraduateAboutUserHadoop UsingUsingUsing Job

  9. Running Jobs on Edison

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Scienceand Requirements RecentlyElectronicResourcesjobs Running jobs Quick Instructions for Hopper

  10. Running Jobs on Franklin

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Scienceand Requirements RecentlyElectronicResourcesjobs Running jobs Quick Instructions for

  11. Running Jobs on Hopper

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Scienceand Requirements RecentlyElectronicResourcesjobs Running jobs Quick Instructions for Queues

  12. Running Large Scale Jobs

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Scienceand Requirements RecentlyElectronicResourcesjobs Running jobs Quick Instructions forRunning

  13. Running jobs on Euclid

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Scienceand Requirements RecentlyElectronicResourcesjobs Running jobs Quick Instructions

  14. CBFO Job Opportunities

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOnItem NotEnergy,ARMForms About Batteries BatteriesCAES Home Home AboutCBFO Job

  15. Careers: Job Description

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOnItem NotEnergy,ARMForms About Batteriesmetal-organic frameworks |A photo of aJobsOak

  16. Franklin Completed Jobs

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC) Environmental Assessments (EA)Budget(DANCE) TargetForms &Francis G.Completed Jobs

  17. Franklin Job Launch Overview

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC) Environmental Assessments (EA)Budget(DANCE) TargetForms &FrancisEmailFileJob

  18. Edison Job Size Charts

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625govInstrumentstdmadapInactiveVisitingContract ManagementDiscoveringESnet UpdateEarth WeekAlamosEdisonEdisonJob Size

  19. Ensemble_Jobs.pptx

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625govInstrumentstdmadapInactiveVisitingContractElectron-StateEnergyHeavyDepartmentebba Sign InEnsemble Jobs forFor

  20. Monitoring Jobs on Hopper

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)Integrated Codes |IsLove Your1 SECTIONES2008-54174 This manuscriptMonitoring Jobs

  1. Monitoring jobs with qs

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)Integrated Codes |IsLove Your1 SECTIONES2008-54174 This manuscriptMonitoringJobs »

  2. Monitoring your job

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)Integrated Codes |IsLove Your1 SECTIONES2008-54174 This manuscriptMonitoringJobs

  3. Subject: Integrated Safety Analysis: Why It Is Appropriate for Fuel Recycling Facilities Project Number: 689Nuclear Energy Institute (NEI) Letter, 9/10/10

    Broader source: Energy.gov [DOE]

    Enclosed for your review is a Nuclear Energy Institute white paper on the use of Integrated Safety Analysis (ISA) at U.S. Nuclear Regulatory Commission-licensed recycling facilities. This paper is...

  4. Jobs masonry in LHCb with elastic Grid Jobs

    E-Print Network [OSTI]

    Stagni, F

    2015-01-01T23:59:59.000Z

    In any distributed computing infrastructure, a job is normally forbidden to run for an indefinite amount of time. This limitation is implemented using different technologies, the most common one being the CPU time limit implemented by batch queues. It is therefore important to have a good estimate of how much CPU work a job will require: otherwise, it might be killed by the batch system, or by whatever system is controlling the jobs' execution. In many modern interwares, the jobs are actually executed by pilot jobs, that can use the whole available time in running multiple consecutive jobs. If at some point the available time in a pilot is too short for the execution of any job, it should be released, while it could have been used efficiently by a shorter job. Within LHCbDIRAC, the LHCb extension of the DIRAC interware, we developed a simple way to fully exploit computing capabilities available to a pilot, even for resources with limited time capabilities, by adding elasticity to production MonteCarlo (MC) si...

  5. Major Business Facility Job Tax Credit (Virginia)

    Broader source: Energy.gov [DOE]

    The Major Business Facility Job Tax Credit is a program administered by the Virginia Department of Taxation. The credit provides $1,000 per job over a 25 or 50-job threshold, which varies by...

  6. The Jobs Development Act (Rhode Island)

    Broader source: Energy.gov [DOE]

    The Jobs Development Act provides an incremental reduction in the corporate income tax rate (9%) to companies creating jobs in Rhode Island. For every ten new jobs created for companies with fewer...

  7. LOCH: Open Access Facilitator Job Description (DRAFT) 

    E-Print Network [OSTI]

    McMahon, Jacqueline

    2015-03-23T23:59:59.000Z

    DRAFT Job Description for an Open Access Facilitator job in the University of Edinburgh's College of Humanities and Social Sciences. This draft job description is being made available as part of the Jisc-funded LOCH Project....

  8. Virginia Enterprise Zone Job Creation Grant (Virginia)

    Broader source: Energy.gov [DOE]

    The Virginia Enterprise Zone Job Creation Grant provides cash grants to businesses located in Enterprise zones that create permanent new jobs over a four-job threshold. State incentives are...

  9. BNL | Center for Functional Nanomaterials (CFN) | Jobs

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

    Current Job Openings at the Center for Functional Nanomaterials The CFN Jobs List is currently unavailable. You may search for CFN positions in the Lab's job list. About CFN The...

  10. JOB DESCRIPTION Requisition ID 4206BR

    E-Print Network [OSTI]

    general office and administrative policies. · May supervise lower level staff members. · Schedules in accordance with established procedures. · Performs research and/or statistical analyses and assistsJOB DESCRIPTION Requisition ID 4206BR ASU Job Title Administrative Secretary Job Title

  11. Peer review of the National Transportation Safety Board structural analysis of the I-35W bridge collapse.

    SciTech Connect (OSTI)

    Gwinn, Kenneth West; Redmond, James Michael; Wellman, Gerald William

    2008-10-01T23:59:59.000Z

    The Engineering Sciences Center at Sandia National Laboratories provided an independent peer review of the structural analysis supporting the National Transportation Safety Board investigation of the August 1, 2007 collapse of the I-35W Bridge in Minneapolis. The purpose of the review was to provide an impartial critique of the analysis approach, assumptions, solution techniques, and conclusions. Subsequent to reviewing numerous supporting documents, a SNL team of staff and management visited NTSB to participate in analysis briefings, discussions with investigators, and examination of critical elements of the bridge wreckage. This report summarizes the opinion of the review team that the NTSB analysis effort was appropriate and provides compelling supporting evidence for the NTSB probable cause conclusion.

  12. Application of a Comprehensive Sensitivity Analysis Method on the Safety Assessment of TRU Waste Disposal in Japan

    SciTech Connect (OSTI)

    Takao Ohi; Manabu Inagaki; Tomoyuki Sone; Morihiro Mihara; Takeshi Ebashi [JAEA, 4-33 Muramatsu, Tokai-mura, Ibaraki-ken, 319-1194 (Japan); Hiroyasu Takase [Quintessa K. K, Queen's Tower A 7-707, 2-3-1 Minatomirai Nishi-ku, Yokohama, Kanagawaken, 220-6007 (Japan); Kiyoshi Oyamada [JGC Corporation, 2-3-1 Minatomirai Nishi-ku, Yokohama, Kanagawa-ken, 220-6001 (Japan); Kunihiko Nakajima [NESI Inc., 4-33 Muramatsu, Tokai-mura, Ibaraki-ken, 319-1112 (Japan)

    2007-07-01T23:59:59.000Z

    A comprehensive sensitivity analysis method has been developed with the aim of providing quantitative information in an efficient manner. This methodology is composed of the following two components: (1) a statistical method with random sampling of independent parameters, which identifies important parameters and extracts threshold values of parameters and/or combinations yielding a 'successful condition' where maximum dose does not exceed a target value, (2) A nuclide migration model that as far as possible incorporates a comprehensive set of phenomena occurring within the repository. This approach was applied as part of a safety assessment of the geological disposal of transuranic (TRU) waste in Japan (TRU-2). It was shown that the concept of TRU waste disposal is robust from the point of view of safety. (authors)

  13. Clean Energy Jobs Plan Introduction

    E-Print Network [OSTI]

    times as many jobs per dollar as gas, oil or coal. And dollars invested in clean energy tend to stay. Investment in clean technology is also growing. Clean tech investment in California reached $3.3 billionClean Energy Jobs Plan Introduction When I was governor, California was the world leader

  14. Jobs & Dollars BIG RETURNS from

    E-Print Network [OSTI]

    . That's more than twice as many jobs as the oil and gas and road construction industries combined nation's economy, supplying important natural resources and millions of jobs. Destroying estuaries destroys economic value Over the past century, human use and development have severely stressed

  15. Engineering Scheme Mentor Job description

    E-Print Network [OSTI]

    Anderson, Jim

    1 Engineering Scheme Mentor Job description Department: Student Administration and Registry and Outreach Team Job title: Engineering Scheme Mentor Responsible to: UK Student Recruitment and Outreach Team Payment and benefits: £100 overall for e-mentoring plus £6.42 per additional hour Duration: Activities

  16. Experience with Remote Job Execution

    SciTech Connect (OSTI)

    Lynch, Vickie E [ORNL; Cobb, John W [ORNL; Green, Mark L [ORNL; Kohl, James Arthur [ORNL; Miller, Stephen D [ORNL; Ren, Shelly [ORNL; Smith, Bradford C [ORNL; Vazhkudai, Sudharshan S [ORNL

    2008-01-01T23:59:59.000Z

    The Neutron Science Portal at Oak Ridge National Laboratory submits jobs to the TeraGrid for remote job execution. The TeraGrid is a network of high performance computers supported by the US National Science Foundation. There are eleven partner facilities with over a petaflop of peak computing performance and sixty petabytes of long-term storage. Globus is installed on a local machine and used for job submission. The graphical user interface is produced by java coding that reads an XML file. After submission, the status of the job is displayed in a Job Information Service window which queries globus for the status. The output folder produced in the scratch directory of the TeraGrid machine is returned to the portal with globus-url-copy command that uses the gridftp servers on the TeraGrid machines. This folder is copied from the stage-in directory of the community account to the user's results directory where the output can be plotted using the portal's visualization services. The primary problem with remote job execution is diagnosing execution problems. We have daily tests of submitting multiple remote jobs from the portal. When these jobs fail on a computer, it is difficult to diagnose the problem from the globus output. Successes and problems will be presented.

  17. Bioindustry Creates Green Jobs | Department of Energy

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

    Bioindustry Creates Green Jobs Bioindustry Creates Green Jobs Energy from abundant, renewable, domestic biomass can reduce U.S. dependence on oil, lower impacts on climate, and...

  18. Benefits Summary - Temporary Job Classification | Argonne National...

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

    Temporary Job Classification Download a summary of benefits offered to employees in the temporary job classification (at least 6 months term and 20 hoursweek). 2015 Long Term...

  19. NERSC Seeks New Director - Job Position Posted

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

    Seeks New Director - Job Position Posted NERSC Seeks New Director - Job Position Posted February 19, 2012 by Francesca Verdier (0 Comments) Current NERSC Director Kathy Yelick was...

  20. RESEARCH SAFETY RADIATION SAFETY

    E-Print Network [OSTI]

    and Communications Manager (951) 827-6303 janette.ducut@ucr.edu Beiwei Tu, MS, CIH, CSP Safety and Industrial Hygiene

  1. Model-Based Quantitative Safety Analysis of Matlab Simulink / Stateflow Models

    E-Print Network [OSTI]

    Leue, Stefan

    ISO 26262 [Int11] for the automotive domain or DO-178C [sta12] for the avionics domain recommend is widely used to design systems in the automotive and avionics domains. ISO 26262 and DO-178C require (FMEA) [Int91] or Fault Tree Anal- ysis (FTA) [U.S81]. This gives rise to the question how safety

  2. Component Failure Behaviour: Patterns and Reuse in Automated System Safety Analysis

    E-Print Network [OSTI]

    Boyer, Edmond

    Trees and Failure Modes and Effects Analyses (FMEAs) can be automatically derived from a topological of failure patterns in conjunction with automated fault tree and FMEA synthesis algorithms can help on safety is universal, the issue is perhaps more urgent in the automotive industry which currently

  3. Water/sand flooded and immersed critical experiment and analysis performed in support of the TOPAZ-II Safety Program

    SciTech Connect (OSTI)

    Glushkov, E.S.; Ponomarev-Stepnoi, N.N.; Bubelev, V.G.; Garin, V.P.; Gomin, E.A.; Kompanietz, G.V.; Krutoy, A.M.; Lobynstev, V.A.; Maiorov, L.V.; Polyakov, D.N. [RRC Kurchatov Institute, Moscow (Russian Federation)] [and others

    1994-11-01T23:59:59.000Z

    Presented is a brief description of the Narciss-M2 critical assemblies, which simulate accidental water/wet-sand immersion of the TOPAZ-II reactor as well as water-flooding of core cavities. Experimental results obtained from these critical assemblies, including experiments with several fuel elements removed from the core, are shown. These configurations with several extracted fuel elements simulate a proposed fuel-out anticriticality-device modification to the TOPAZ-II reactor. Preliminary computational analysis of these experiments using the Monte Carlo neutron-transport method is outlined. Nuclear criticality safety of the TOPAZ-II reactor with an incorporated anticriticality unit is demonstrated.

  4. Facility Safety

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

    2013-06-21T23:59:59.000Z

    DOE-STD-1104 contains the Department's method and criteria for reviewing and approving nuclear facility's documented safety analysis (DSA). This review and approval formally document the basis for DOE, concluding that a facility can be operated safely in a manner that adequately protects workers, the public, and the environment. Therefore, it is appropriate to formally require implementation of the review methodology and criteria contained in DOE-STD-1104.

  5. Expectations on Documented Safety Analysis for Deactivated Inactive Nuclear Facilities in a State of Long Term Surveillance & Maintenance or Decommissioning

    SciTech Connect (OSTI)

    JACKSON, M.W.

    2002-05-01T23:59:59.000Z

    DOE promulgated 10 CFR 830 ''Nuclear Safety Management'' on October 10, 2000. Section 204 of the Rule requires that contractors at DOE hazard category 1, 2, and 3 nuclear facilities develop a ''Documented Safety Analysis'' (DSA) that summarizes the work to be performed, the associated hazards, and hazard controls necessary to protect workers, the public, and the environment. Table 2 of Appendix A to the rule has been provided to ensure that DSAs are prepared in accordance with one of the available predetermined ''safe harbor'' approaches. The table presents various acceptable safe harbor DSAs for different nuclear facility operations ranging from nuclear reactors to decommissioning activities. The safe harbor permitted for decommissioning of a nuclear facility encompasses methods described in DOE-STD-1 120-98, ''Integration of Environment, Safety and Health into Facility Disposition Activities,'' and provisions in 29 CFR 1910.120 or 29 CFR 1926.65 (HAZWOPER). Additionally, an evaluation of public safety impacts and development of necessary controls is required when the facility being decommissioned contains radiological inventory or contamination exceeding the Rule's definition for low-level residual fixed radioactivity. This document discusses a cost-effective DSA approach that is based on the concepts of DOE-STD-I 120 and meets the 10 CFR 830 safe harbor requirements for both transition surveillance and maintenance as well as decommissioning. This DSA approach provides continuity for inactive Hanford nuclear facilities that will eventually transition into decommissioning. It also uses a graded approach that meets the expectations of DOE-STD-3011 and addresses HAZWOPER requirements to provide a sound basis for worker protection, particularly where intrusive work is being conducted.

  6. nees@UCLA Safety nees@UCLA Safety Handbook revision 04, 7/31/2012 1

    E-Print Network [OSTI]

    Grether, Gregory

    /9/2009 -Add a detailed Accident Analysis section -Add OSHA Action Plan section with link to UCLA EH................................................................................................................ 10 3.2 Accident Analysis ...................................................................................... 13 3.7 Job Hazard Analysis Plan.................................

  7. Challenges in the Modeling and Quantitative Analysis of Safety-Critical Automotive Systems!

    E-Print Network [OSTI]

    Leue, Stefan

    ! Probabilistic FMEA! Probabilistic Analysis of System Architectures! ! Conclusion! 3! #12;ISO 26262: Road! ,,identify Failures"! - Qualitative FMEA! ! - Qualitative Fault Tree Analysis! ! - Event Tree Analysis! Quantitative Methods! ,,predict frequency of failures"! - Quantitative FMEA! ! - Quantitative Fault Tree

  8. Design and Transient Analysis of Passive Safety Cooling Systems for Advanced Nuclear Reactors

    E-Print Network [OSTI]

    Galvez, Cristhian

    2011-01-01T23:59:59.000Z

    L. J. Hamilton Nuclear Reactor Analysis John Wiley and Sons,R. J. Neuhold, Introductury Nuclear Reactor Dynamics. ANSL. J. Hamilton Nuclear Reactor Analysis John Wiley and Sons,

  9. Safety analysis--200 Area Savannah River Site: Separations Area operations Building 211-H Outside Facilities. Supplement 11, Revision 1

    SciTech Connect (OSTI)

    Not Available

    1993-01-01T23:59:59.000Z

    The H-Area Outside Facilities are located in the 200-H Separations Area and are comprised of a number of processes, utilities, and services that support the separations function. Included are enriched uranium loadout, bulk chemical storage, water handling, acid recovery, general purpose evaporation, and segregated solvent facilities. In addition, services for water, electricity, and steam are provided. This Safety Analysis Report (SAR) documents an analysis of the H-Area Outside Facilities and is one of a series of documents for the Separations Area as specified in the SR Implementation Plan for DOE order 5481.1A. The primary purpose of the analysis was to demonstrate that the facility can be operated without undue risk to onsite or offsite populations, to the environment, and to operating personnel. In this report, risks are defined as the expected frequencies of accidents, multiplied by the resulting radiological consequences in person-rem. Following the summary description of facility and operations is the site evaluation including the unique features of the H-Area Outside Facilities. The facility and process design are described in Chapter 3.0 and a description of operations and their impact is given in Chapter 4.0. The accident analysis in Chapter 5.0 is followed by a list of safety related structures and systems (Chapter 6.0) and a description of the Quality Assurance program (Chapter 7.0). The accident analysis in this report focuses on estimating the risk from accidents as a result of operation of the facilities. The operations were evaluated on the basis of three considerations: potential radiological hazards, potential chemical toxicity hazards, and potential conditions uniquely different from normal industrial practice.

  10. FAQS Job Task Analyses- Industrial Hygiene

    Broader source: Energy.gov [DOE]

    FAQS Job Task Analyses are performed on the Function Area Qualification Standards. The FAQS Job Task Analyses consists of: Developing a comprehensive list of tasks that define the job such as the duties and responsibilities which include determining their levels of importance and frequency. Identifying and evaluating competencies. Last step is evaluating linkage between job tasks and competencies.

  11. FAQS Job Task Analyses- General Technical Base

    Broader source: Energy.gov [DOE]

    FAQS Job Task Analyses are performed on the Function Area Qualification Standards. The FAQS Job Task Analyses consists of: Developing a comprehensive list of tasks that define the job such as the duties and responsibilities which include determining their levels of importance and frequency. Identifying and evaluating competencies. Last step is evaluating linkage between job tasks and competencies.

  12. FAQS Job Task Analyses- DOE Aviation Manager

    Broader source: Energy.gov [DOE]

    FAQS Job Task Analyses are performed on the Function Area Qualification Standards. The FAQS Job Task Analyses consists of: Developing a comprehensive list of tasks that define the job such as the duties and responsibilities which include determining their levels of importance and frequency. Identifying and evaluating competencies. Last step is evaluating linkage between job tasks and competencies.

  13. FAQS Job Task Analyses- Quality Assurance

    Broader source: Energy.gov [DOE]

    FAQS Job Task Analyses are performed on the Function Area Qualification Standards. The FAQS Job Task Analyses consists of: Developing a comprehensive list of tasks that define the job such as the duties and responsibilities which include determining their levels of importance and frequency. Identifying and evaluating competencies. Last step is evaluating linkage between job tasks and competencies.

  14. JOB INFORMATION AND EARNINGS HISTORY General Information

    E-Print Network [OSTI]

    Guenther, Frank

    JOB INFORMATION AND EARNINGS HISTORY General Information Student Job Information and Earnings information for each job held by a student. This information can be accessed either through the Student to view all students hired under that mail code. By clicking on a student's specific job number, you

  15. Streiffer's Job Market Sampler Table of Contents

    E-Print Network [OSTI]

    Streiffer, Robert

    Streiffer's Job Market Sampler Table of Contents · Cover letters addressing a variety of jobs Dean Sigman, I am writing to apply for position number 8, advertised in Jobs for Philosophers, volume. Respectfully yours, Robert Streiffer (rstreiff@mit.edu) #12;Cover letter for a job listing which

  16. Job Interview: Disability-Related Questions

    E-Print Network [OSTI]

    Sheridan, Jennifer

    Job Interview: Disability-Related Questions (What IS and IS NOT ok to ask in a job interview for the job (such as education, training, experience, skills, or licenses) and perform the essential functions of the job. But how can the employer find this out without violating the sometimes confusing rules of the ADA

  17. A Job Seeker's Guide About this Guide

    E-Print Network [OSTI]

    Butler, Laurie J.

    A Job Seeker's Guide About this Guide This guide is designed to assist you in your job search. Included in this guide are many helpful tips that you can use throughout your job search process. In this guide, you will learn how to: Apply job search strategies Write and format a resume Conduct yourself

  18. Student Job Review Questionnaire / Periodic Survey

    E-Print Network [OSTI]

    Amin, S. Massoud

    Student Job Review Questionnaire / Periodic Survey FOR OHR USE ONLY No Change Date Received JRQ Number Notice Number Job Family Title Job Family Number New Pay Rate/Range Certifiable Yes No Effective Date Approved for Notice Letter Date Notice Mailed Job Review Questionnaire (JRQ) (Student Request

  19. SCHEDULING INTERVIEWS FOR A JOB FAIR

    E-Print Network [OSTI]

    Bartholdi III, John J.

    SCHEDULING INTERVIEWS FOR A JOB FAIR John J. Bartholdi, III Kevin L. McCroan April 4, 1989; revised April 3, 2003 Abstract We describe the design and use of a program to schedule job interviews for law firms and students at a job fair. It has been used to manage the Southeastern Public Interest Job

  20. MANAGING JOB LOSS and FINANCIAL STRESS

    E-Print Network [OSTI]

    MANAGING JOB LOSS and FINANCIAL STRESS a Personal and Family Guide CENTER ON THE FAMILY #12;2 Managing Job Loss and Financial Stress The issues associated with losing one's job or having hours cut also have other assistance (e.g., job placement, resume preparation, retraining), of which you should

  1. Safety Analysis Report for Packaging (SARP) of the Oak Ridge National Laboratory TRU Californium Shipping Container

    SciTech Connect (OSTI)

    Box, W.D.; Shappert, L.B.; Seagren, R.D.; Klima, B.B.; Jurgensen, M.C.; Hammond, C.R.; Watson, C.D.

    1980-01-01T23:59:59.000Z

    An analytical evaluation of the Oak Ridge National Laboratory TRU Californium Shipping Container was made in order to demonstrate its compliance with the regulations governing off-site shipment of packages that contain radioactive material. The evaluation encompassed five primary categories: structural integrity, thermal resistance, radiation shielding, nuclear criticality safety, and quality assurance. The results of this evaluation demonstrate that the container complies with the applicable regulations.

  2. Packaging review guide for reviewing safety analysis reports for packagings: Revision 1

    SciTech Connect (OSTI)

    Fisher, L.E.; Chou, C.K.; Lloyd, W.R.; Mount, M.E.; Nelson, T.A.; Schwartz, M.W.; Witte, M.C.

    1988-10-01T23:59:59.000Z

    The Department of Energy (DOE) has established procedures for obtaining certification of packagings used by DOE and its contractors for the transport of radioactive materials. The principal purpose of this document is to assure the quality and uniformity of PCS reviews and to present a well-defined base from which to evaluate proposed changes in the scope and requirements of reviews. The Packaging Review Guide (PRG) also sets forth solutions and approaches determined to be acceptable in the past in dealing with a specific safety issue or safety-related design area. These solutions and approaches are presented in this form so that reviewers can take consistent and well-understood positions as the same safety issues arise in future cases. An applicant submitting a SARP does not have to follow the solutions or approaches presented. It is also a purpose of the PRG to make information about DOE certification policy and procedures widely available to DOE field offices, DOE contractors, federal agencies, and interested members of the public. 77 refs., 16 figs., 15 tabs.

  3. Safety analysis report for packaging, Oak Ridge Y-12 Plant, model DC-1 package with HEU oxide contents. Change pages for Rev.1

    SciTech Connect (OSTI)

    NONE

    1995-01-18T23:59:59.000Z

    This Safety Analysis Report for Packaging for the Oak Ridge Y-12 Plant for the Model DC-1 package with highly enriched uranium (HEU) oxide contents has been prepared in accordance with governing regulations form the Nuclear Regulatory Commission and the Department of Transportation and orders from the Department of energy. The fundamental safety requirements addressed by these regulations and orders pertain to the containment of radioactive material, radiation shielding, and nuclear subcriticality. This report demonstrates how these requirements are met.

  4. Safety analysis report for the use of hazardous production materials in photovoltaic applications at the National Renewable Energy Laboratory

    SciTech Connect (OSTI)

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

    1992-07-01T23:59:59.000Z

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

  5. Museum Educator Volunteer Job Description

    E-Print Network [OSTI]

    Pulfrey, David L.

    Museum Educator Volunteer Job Description The Beaty Biodiversity Museum, a new museum housing UBC's rich biological collections, is dedicated to enhancing to the public. Volunteer Museum Educators play a vital role in the museum mission

  6. Job Development Credit (South Carolina)

    Broader source: Energy.gov [DOE]

    A Job Development Credit (JDC) is a performance-based incentive that rebates a portion of new employees' withholding taxes that can be used to address the specific needs of individual companies....

  7. Vermont Sustainable Jobs Fund (Vermont)

    Broader source: Energy.gov [DOE]

    The Vermont Sustainable Job Fund offers grants, loans, and technical assistance. VSJF's grant-making depends on the funds it raised and its strategic market development focus. Grant proposals are...

  8. Preliminary systems-interaction results from the Digraph Matrix Analysis of the Watts Bar Nuclear Power Plant safety-injection systems

    SciTech Connect (OSTI)

    Sacks, I.J.; Ashmore, B.C.; Champney, J.M.; Alesso, H.P.

    1983-06-01T23:59:59.000Z

    This report provides preliminary results generated by a Digraph Matrix Analysis (DMA) for a Systems Interaction analysis performed on the Safety Injection System of the Tennessee Valley Authority Watts Bar Nuclear Power Plant. An overview of DMA is provided along with a brief description of the computer codes used in DMA.

  9. An overview of modeling methods for thermal mixing and stratification in large enclosures for reactor safety analysis

    SciTech Connect (OSTI)

    Haihua Zhao; Per F. Peterson

    2010-10-01T23:59:59.000Z

    Thermal mixing and stratification phenomena play major roles in the safety of reactor systems with large enclosures, such as containment safety in current fleet of LWRs, long-term passive containment cooling in Gen III+ plants including AP-1000 and ESBWR, the cold and hot pool mixing in pool type sodium cooled fast reactor systems (SFR), and reactor cavity cooling system behavior in high temperature gas cooled reactors (HTGR), etc. Depending on the fidelity requirement and computational resources, 0-D steady state models (heat transfer correlations), 0-D lumped parameter based transient models, 1-D physical-based coarse grain models, and 3-D CFD models are available. Current major system analysis codes either have no models or only 0-D models for thermal stratification and mixing, which can only give highly approximate results for simple cases. While 3-D CFD methods can be used to analyze simple configurations, these methods require very fine grid resolution to resolve thin substructures such as jets and wall boundaries. Due to prohibitive computational expenses for long transients in very large volumes, 3-D CFD simulations remain impractical for system analyses. For mixing in stably stratified large enclosures, UC Berkeley developed 1-D models basing on Zuber’s hierarchical two-tiered scaling analysis (HTTSA) method where the ambient fluid volume is represented by 1-D transient partial differential equations and substructures such as free or wall jets are modeled with 1-D integral models. This allows very large reductions in computational effort compared to 3-D CFD modeling. This paper will present an overview on important thermal mixing and stratification phenomena in large enclosures for different reactors, major modeling methods and their advantages and limits, potential paths to improve simulation capability and reduce analysis uncertainty in this area for advanced reactor system analysis tools.

  10. Technical Letter Report: Evaluation and Analysis of a Few International Periodic Safety Review Summary Reports

    SciTech Connect (OSTI)

    Chopra, Omesh K. [Argonne National Lab., IL (United States). Environmental Science Division; Diercks, Dwight R. [Argonne National Lab., IL (United States). Nuclear Engineering Division; Ma, David Chia-Chiun [Argonne National Lab., IL (United States). Environmental Science Division; Garud, Yogendra S. [Argonne National Lab., IL (United States). Environmental Science Division

    2013-12-17T23:59:59.000Z

    At the request of the United States (U.S.) government, the International Atomic Energy Agency (IAEA) assembled a team of 20 senior safety experts to review the regulatory framework for the safety of operating nuclear power plants in the United States. This review focused on the effectiveness of the regulatory functions implemented by the NRC and on its commitment to nuclear safety and continuous improvement. One suggestion resulting from that review was that the U.S. Nuclear Regulatory Commission (NRC) incorporate lessons learned from periodic safety reviews (PSRs) performed in other countries as an input to the NRC’s assessment processes. In the U.S., commercial nuclear power plants (NPPs) are granted an initial 40-year operating license, which may be renewed for additional 20-year periods, subject to complying with regulatory requirements. The NRC has established a framework through its inspection, and operational experience processes to ensure the safe operation of licensed nuclear facilities on an ongoing basis. In contrast, most other countries do not impose a specific time limit on the operating licenses for NPPs, they instead require that the utility operating the plant perform PSRs, typically at approximately 10-year intervals, to assure continued safe operation until the next assessment. The staff contracted with Argonne National Laboratory (Argonne) to perform a pilot review of selected translated PSR assessment reports and related documentation from foreign nuclear regulatory authorities to identify any potential new regulatory insights regarding license renewal-related topics and NPP operating experience (OpE). A total of 14 PSR assessment documents from 9 countries were reviewed. For all of the countries except France, individual reports were provided for each of the plants reviewed. In the case of France, three reports were provided that reviewed the performance assessment of thirty-four 900-MWe reactors of similar design commissioned between 1978 and 1988. All of the reports reviewed were the regulator’s assessment of the PSR findings rather than the original PSR report, and all but one were English translations from the original language. In these reviews, it was found that most of the countries base their regulatory guidance to some extent (and often to a large extent) on U.S. design codes and standards, NRC regulatory guidance, and U.S. industry guidance. In addition, many of the observed operational technical issues and OpE events reported for U.S. reactors are also cited in the PSR reports. The PSR reports also identified a number of potential technical material/component performance issues and OpE events that are not commonly reported for U.S. plants.

  11. Combining Formal Methods and Safety Analysis -The ForMoSA Approach

    E-Print Network [OSTI]

    Reif, Wolfgang

    techniques [13, 20] like failure modes and effects analysis (FMEA) or fault tree analysis (FTA). The combina in which a component may fail. The leaves of all fault trees are failure modes. The starting column of FMEA

  12. Formal Support for Quantitative Analysis of Residual Risks in Safety-Critical Systems

    E-Print Network [OSTI]

    and Effects Analysis (FMEA) and Fault-Tree Analy- sis (FTA) [16]. However, many of these techniques become

  13. SAFETY ANALYSIS OF A RADIO-BASED CROSSING CONTROL SYSTEM USING FORMAL

    E-Print Network [OSTI]

    Reif, Wolfgang

    ), failure mode and e#11;ects anal- ysis (FMEA) (Reifer 1979), or hazard and oper- ability analysis (HAZOP

  14. Modeling and Analysis of Safety-Critical Cyber Physical Systems using State/Event Fault Trees

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    . Keywords: reliability modeling, risk analysis, attack trees, fault tree, State/Event Fault Tree 1 to their ability to capture qualitative and quantitative analysis aspects they can be seen as state of the art and it is not possible to do a quantitative analysis of them in case of statistical depend basic events. In [6] Kaiser et

  15. Assessment of the Value, Impact, and Validity of the Jobs and Economic Development Impacts (JEDI) Suite of Models

    SciTech Connect (OSTI)

    Billman, L.; Keyser, D.

    2013-08-01T23:59:59.000Z

    The Jobs and Economic Development Impacts (JEDI) models, developed by the National Renewable Energy Laboratory (NREL) for the U.S. Department of Energy (DOE) Office of Energy Efficiency and Renewable Energy (EERE), use input-output methodology to estimate gross (not net) jobs and economic impacts of building and operating selected types of renewable electricity generation and fuel plants. This analysis provides the DOE with an assessment of the value, impact, and validity of the JEDI suite of models. While the models produce estimates of jobs, earnings, and economic output, this analysis focuses only on jobs estimates. This validation report includes an introduction to JEDI models, an analysis of the value and impact of the JEDI models, and an analysis of the validity of job estimates generated by JEDI model through comparison to other modeled estimates and comparison to empirical, observed jobs data as reported or estimated for a commercial project, a state, or a region.

  16. An OSHA based approach to safety analysis for nonradiological hazardous materials

    SciTech Connect (OSTI)

    Yurconic, M.

    1992-08-01T23:59:59.000Z

    The PNL method for chemical hazard classification defines major hazards by means of a list of hazardous substances (or chemical groups) with associated trigger quantities. In addition, the functional characteristics of the facility being classified is also be factored into the classification. In this way, installations defined as major hazard will only be those which have the potential for causing very serious incidents both on and off site. Because of the diversity of operations involving chemicals, it may not be possible to restrict major hazard facilities to certain types of operations. However, this hazard classification method recognizes that in the industrial sector major hazards are most commonly associated with activities involving very large quantities of chemicals and inherently energetic processes. These include operations like petrochemical plants, chemical production, LPG storage, explosives manufacturing, and facilities which use chlorine, ammonia, or other highly toxic gases in bulk quantities. The basis for this methodology is derived from concepts used by OSHA in its proposed chemical process safety standard, the Dow Fire and Explosion Index Hazard Classification Guide, and the International Labor Office`s program on chemical safety. For the purpose of identifying major hazard facilities, this method uses two sorting criteria, (1) facility function and processes and (2) quantity of substances to identify facilities requiringclassification. Then, a measure of chemical energy potential (material factor) is used to identify high hazard class facilities.

  17. An OSHA based approach to safety analysis for nonradiological hazardous materials

    SciTech Connect (OSTI)

    Yurconic, M.

    1992-08-01T23:59:59.000Z

    The PNL method for chemical hazard classification defines major hazards by means of a list of hazardous substances (or chemical groups) with associated trigger quantities. In addition, the functional characteristics of the facility being classified is also be factored into the classification. In this way, installations defined as major hazard will only be those which have the potential for causing very serious incidents both on and off site. Because of the diversity of operations involving chemicals, it may not be possible to restrict major hazard facilities to certain types of operations. However, this hazard classification method recognizes that in the industrial sector major hazards are most commonly associated with activities involving very large quantities of chemicals and inherently energetic processes. These include operations like petrochemical plants, chemical production, LPG storage, explosives manufacturing, and facilities which use chlorine, ammonia, or other highly toxic gases in bulk quantities. The basis for this methodology is derived from concepts used by OSHA in its proposed chemical process safety standard, the Dow Fire and Explosion Index Hazard Classification Guide, and the International Labor Office's program on chemical safety. For the purpose of identifying major hazard facilities, this method uses two sorting criteria, (1) facility function and processes and (2) quantity of substances to identify facilities requiringclassification. Then, a measure of chemical energy potential (material factor) is used to identify high hazard class facilities.

  18. Preliminary safety analysis report for the Auxiliary Hot Cell Facility, Sandia National Laboratories, Albuquerque, New Mexico

    SciTech Connect (OSTI)

    OSCAR,DEBBY S.; WALKER,SHARON ANN; HUNTER,REGINA LEE; WALKER,CHERYL A.

    1999-12-01T23:59:59.000Z

    The Auxiliary Hot Cell Facility (AHCF) at Sandia National Laboratories, New Mexico (SNL/NM) will be a Hazard Category 3 nuclear facility used to characterize, treat, and repackage radioactive and mixed material and waste for reuse, recycling, or ultimate disposal. A significant upgrade to a previous facility, the Temporary Hot Cell, will be implemented to perform this mission. The following major features will be added: a permanent shield wall; eight floor silos; new roof portals in the hot-cell roof; an upgraded ventilation system; and upgraded hot-cell jib crane; and video cameras to record operations and facilitate remote-handled operations. No safety-class systems, structures, and components will be present in the AHCF. There will be five safety-significant SSCs: hot cell structure, permanent shield wall, shield plugs, ventilation system, and HEPA filters. The type and quantity of radionuclides that could be located in the AHCF are defined primarily by SNL/NM's legacy materials, which include radioactive, transuranic, and mixed waste. The risk to the public or the environment presented by the AHCF is minor due to the inventory limitations of the Hazard Category 3 classification. Potential doses at the exclusion boundary are well below the evaluation guidelines of 25 rem. Potential for worker exposure is limited by the passive design features incorporated in the AHCF and by SNL's radiation protection program. There is no potential for exposure of the public to chemical hazards above the Emergency Response Protection Guidelines Level 2.

  19. The American Jobs Act | Department of Energy

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directed offOCHCO Overview OCHCOSystems Analysis Success StoriesInvestigations andThe American Jobs Act The

  20. RDS - A systematic approach towards system thermal hydraulics input code development for a comprehensive deterministic safety analysis

    SciTech Connect (OSTI)

    Salim, Mohd Faiz, E-mail: mohdfaizs@tnb.com.my [Nuclear Energy Department, Tenaga Nasional Berhad, Level 32, Dua Sentral, 50470 Kuala Lumpur (Malaysia); Roslan, Ridha [Nuclear Installation Division, Atomic Energy Licensing Board, Batu 24, Jalan Dengkil, 43800 Dengkil, Selangor (Malaysia); Ibrahim, Mohd Rizal Mamat [Technical Support Division, Malaysian Nuclear Agency, Bangi, 43000 Kajang, Selangor (Malaysia)

    2014-02-12T23:59:59.000Z

    Deterministic Safety Analysis (DSA) is one of the mandatory requirements conducted for Nuclear Power Plant licensing process, with the aim of ensuring safety compliance with relevant regulatory acceptance criteria. DSA is a technique whereby a set of conservative deterministic rules and requirements are applied for the design and operation of facilities or activities. Computer codes are normally used to assist in performing all required analysis under DSA. To ensure a comprehensive analysis, the conduct of DSA should follow a systematic approach. One of the methodologies proposed is the Standardized and Consolidated Reference Experimental (and Calculated) Database (SCRED) developed by University of Pisa. Based on this methodology, the use of Reference Data Set (RDS) as a pre-requisite reference document for developing input nodalization was proposed. This paper shall describe the application of RDS with the purpose of assessing its effectiveness. Two RDS documents were developed for an Integral Test Facility of LOBI-MOD2 and associated Test A1-83. Data and information from various reports and drawings were referred in preparing the RDS. The results showed that by developing RDS, it has made possible to consolidate all relevant information in one single document. This is beneficial as it enables preservation of information, promotes quality assurance, allows traceability, facilitates continuous improvement, promotes solving of contradictions and finally assisting in developing thermal hydraulic input regardless of whichever code selected. However, some disadvantages were also recognized such as the need for experience in making engineering judgments, language barrier in accessing foreign information and limitation of resources. Some possible improvements are suggested to overcome these challenges.

  1. Thermal reactor safety

    SciTech Connect (OSTI)

    Not Available

    1980-06-01T23:59:59.000Z

    Information is presented concerning new trends in licensing; seismic considerations and system structural behavior; TMI-2 risk assessment and thermal hydraulics; statistical assessment of potential accidents and verification of computational methods; issues with respect to improved safety; human factors in nuclear power plant operation; diagnostics and activities in support of recovery; LOCA transient analysis; unresolved safety issues and other safety considerations; and fission product transport.

  2. Creating a Job Posting All job openings at the University are posted on-line through Jobs@UVa. Postings for University Staff

    E-Print Network [OSTI]

    Brodie III, Edmund D.

    Creating a Job Posting All job openings at the University are posted on-line through Jobs to posting. Hiring Managers will access the Jobs@UVa system to create a job posting and submit it through, your job posting will be received by an HR Consultant who will contact you to discuss the specifics

  3. Regulatory analysis for the resolution of generic issue 57: Effects of Fire Protection System Actuation on Safety-Related Equipment

    SciTech Connect (OSTI)

    Woods, H.W.

    1993-10-01T23:59:59.000Z

    Actuation of Fire Protection Systems (FPS) in Nuclear Power Plants have resulted in adverse interactions with equipment important to safety. Precursor operational experience has shown that 37% of all FPS actuations damaged some equipment, and 20% of all FPS actuations have resulted in a plant transient and reactor trip. On an average 0.17 FPS actuations per reactor year have been experienced in nuclear power plants in this country. This report presents the regulatory analysis for GI-57, ``Effects of Fire Protection System Actuation on Safety-Related Equipment``. The risk reduction estimates, cost/benefit analyses, and other insights gained during this effort have shown that implementation of the recommendations contained in this report can significantly reduce risk, and that these improvements can be warranted in accordance with the backfit rule, 10 CFR 50.109(a)(3). However, plant specific analyses are required in order to identify such improvements. Generic analyses can not serve to identify improvements that could be warranted for individual, specific plants. Plant specific analyses of the type needed for this purpose are underway as part of the Individual Plant Examination of External Events (IPEEE) program.

  4. Safety Analysis Report for the use of hazardous production materials in photovoltaic applications at the National Renewable Energy Laboratory

    SciTech Connect (OSTI)

    Crandall, R.S.; Nelson, B.P. (National Renewable Energy Lab., Golden, CO (United States)); Moskowitz, P.D.; Fthenakis, V.M. (Brookhaven National Lab., Upton, NY (United States))

    1992-07-01T23:59:59.000Z

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

  5. Parallel computation safety analysis irradiation targets fission product molybdenum in neutronic aspect using the successive over-relaxation algorithm

    SciTech Connect (OSTI)

    Susmikanti, Mike, E-mail: mike@batan.go.id [Center for Development of Nuclear Informatics, National Nuclear Energy Agency, PUSPIPTEK, Tangerang (Indonesia); Dewayatna, Winter, E-mail: winter@batan.go.id [Center for Nuclear Fuel Technology, National Nuclear Energy Agency, PUSPIPTEK, Tangerang (Indonesia); Sulistyo, Yos, E-mail: soj@batan.go.id [Center for Nuclear Equipment and Engineering, National Nuclear Energy Agency, PUSPIPTEK, Tangerang (Indonesia)

    2014-09-30T23:59:59.000Z

    One of the research activities in support of commercial radioisotope production program is a safety research on target FPM (Fission Product Molybdenum) irradiation. FPM targets form a tube made of stainless steel which contains nuclear-grade high-enrichment uranium. The FPM irradiation tube is intended to obtain fission products. Fission materials such as Mo{sup 99} used widely the form of kits in the medical world. The neutronics problem is solved using first-order perturbation theory derived from the diffusion equation for four groups. In contrast, Mo isotopes have longer half-lives, about 3 days (66 hours), so the delivery of radioisotopes to consumer centers and storage is possible though still limited. The production of this isotope potentially gives significant economic value. The criticality and flux in multigroup diffusion model was calculated for various irradiation positions and uranium contents. This model involves complex computation, with large and sparse matrix system. Several parallel algorithms have been developed for the sparse and large matrix solution. In this paper, a successive over-relaxation (SOR) algorithm was implemented for the calculation of reactivity coefficients which can be done in parallel. Previous works performed reactivity calculations serially with Gauss-Seidel iteratives. The parallel method can be used to solve multigroup diffusion equation system and calculate the criticality and reactivity coefficients. In this research a computer code was developed to exploit parallel processing to perform reactivity calculations which were to be used in safety analysis. The parallel processing in the multicore computer system allows the calculation to be performed more quickly. This code was applied for the safety limits calculation of irradiated FPM targets containing highly enriched uranium. The results of calculations neutron show that for uranium contents of 1.7676 g and 6.1866 g (× 10{sup 6} cm{sup ?1}) in a tube, their delta reactivities are the still within safety limits; however, for 7.9542 g and 8.838 g (× 10{sup 6} cm{sup ?1}) the limits were exceeded.

  6. Jobs and Renewable Energy Project

    SciTech Connect (OSTI)

    Sterzinger, George

    2006-12-19T23:59:59.000Z

    Early in 2002, REPP developed the Jobs Calculator, a tool that calculates the number of direct jobs resulting from renewable energy development under RPS (Renewable Portfolio Standard) legislation or other programs to accelerate renewable energy development. The calculator is based on a survey of current industry practices to assess the number and type of jobs that will result from the enactment of a RPS. This project built upon and significantly enhanced the initial Jobs Calculator model by (1) expanding the survey to include other renewable technologies (the original model was limited to wind, solar PV and biomass co-firing technologies); (2) more precisely calculating the economic development benefits related to renewable energy development; (3) completing and regularly updating the survey of the commercially active renewable energy firms to determine kinds and number of jobs directly created; and (4) developing and implementing a technology to locate where the economic activity related to each type of renewable technology is likely to occur. REPP worked directly with groups in the State of Nevada to interpret the results and develop policies to capture as much of the economic benefits as possible for the state through technology selection, training program options, and outreach to manufacturing groups.

  7. Simulations of argon accident scenarios in the ATLAS experimental cavern a safety analysis

    E-Print Network [OSTI]

    Balda, F

    2002-01-01T23:59:59.000Z

    Some characteristic accidents in the ATLAS experimental cavern (UX15) are simulated by means of STAR-CD, a code using the "Finite-Volume" method. These accidents involve different liquid argon leaks from the barrel cryostat of the detector, thus causing the dispersion of the argon into the Muon Chamber region and the evaporation of the liquid. The subsequent temperature gradients and distribution of argon concentrations, as well as their evolution in time are simulated and discussed, with the purpose of analysing the dangers related to asphyxiation and to contact with cryogenic fluids for the working personnel. A summary of the theory that stands behind the code is also given. In order to validate the models, an experimental test on a liquid argon spill performed earlier is simulated, showing that the program is able to output reliable results. At the end, some safety-related recommendations are listed.

  8. Economic Impacts Associated With Commercializing Fuel Cell Electric Vehicles in California: An Analysis of the California Road Map Using the JOBS H2 Model

    Broader source: Energy.gov [DOE]

    Report by Argonne National Laboratory summarizing an analysis of the economic impacts associated with commercializing fuel cell electric vehicles (FCEVs) in California.

  9. Water/sand flooded and immersed critical experiment and analysis performed in support of the TOPAZ-II safety program

    SciTech Connect (OSTI)

    Glushkov, E.S.; Ponomarev-Stepnoi, N.N.; Bubelev, V.G.; Garin, V.P.; Gomin, E.A.; Kompanietz, G.V.; Krutov, A.M.; Lobynstev, V.A.; Maiorov, L.V.; Polyakov, D.N.; Chunyaev, E.I. [RRC Kurchatov Institute, Moscow 123182 (Russian Federation); Marshall, A.C. [International Nuclear Safety, Sandia National Laboratories, Albuquerque, New Mexico 87185 (United States); Sapir, J.L.; Pelowitz, D.B. [Reactor Design and Analysis Group, Los Alamos National Laboratory, Los Alamos, New Mexico 87545 (United States)

    1995-01-20T23:59:59.000Z

    Presented is a brief description of the Narciss-M2 critical assemblies, which simulate accidental water/wet-sand immersion of the TOPAZ-II reactor as well as water-flooding of core cavities. Experimental results obtained from these critical assemblies, including experiments with several fuel elements removed from the core, are shown. These configurations with several extracted fuel elements simulate a proposed fuel-out anticriticality-device modification to the TOPAZ-II reactor. Preliminary computational analysis of these experiments using the Monte Carlo neutron-transport method is outlined. Nuclear criticality safety of the TOPAZ-II reactor with an incorporated anticriticality unit is demonstrated. {copyright} {ital 1995} {ital American} {ital Institute} {ital of} {ital Physics}

  10. Implementation of Revision 19 of the TRUPACT-II Safety Analysis Report at Rocky Flats Environmental Technology Site

    SciTech Connect (OSTI)

    D'Amico, E.; O'Leary, J.; Bell, S.; Djordjevic, S.; Givens, C,; Shokes, T.; Thompson, S.; Stahl, S.

    2003-02-25T23:59:59.000Z

    The U.S. Nuclear Regulatory Commission on July 27, 2001 approved Revision 19 of the TRUPACT-II Safety Analysis Report (SAR) and the associated TRUPACT-II Authorized Methods for Payload Control (TRAMPAC). Key initiatives in Revision 19 included matrix depletion, unlimited mixing of shipping categories, a flammability assessment methodology, and an alternative methodology for the determination of flammable gas generation rates. All U.S. Department of Energy (DOE) sites shipping transuranic (TRU) waste to the Waste Isolation Pilot Plant (WIPP) were required to implement Revision 19 methodology into their characterization and waste transportation programs by May 20, 2002. An implementation process was demonstrated by the Rocky Flats Environmental Technology Site (RFETS) in Golden, Colorado. The three-part process used by RFETS included revision of the site-specific TRAMPAC, an evaluation of the contact-handled TRU waste inventory against the regulations in Revision 19, and design and development of software to facilitate future inventory analyses.

  11. Formal Safety analysis of a radio-based railroad crossing using Deductive Cause-Consequence

    E-Print Network [OSTI]

    Reif, Wolfgang

    and effects analysis (FMEA) and fault tree analysis (FTA). We apply the method to a real world case study like FMEA [10], FMECA [4] and FTA [3]. The logical framework of DCCA may be used to rigorously verify of what can by analyzed) than traditional FMEA. We show, that the results of DCCA have the same semantics

  12. Analyzing and minimizing the impact of opportunity cost in QoS-aware job scheduling.

    SciTech Connect (OSTI)

    Islam, M.; Balaji, P.; Sabin, G.; Sadayappan, P. (Mathematics and Computer Science); (Ohio State Univ.)

    2007-01-01T23:59:59.000Z

    Quality of service (QoS) mechanisms allowing users to request for turn-around time guarantees for their jobs have recently generated much interest. In our previous work we had designed a framework, QoPS, to allow for such QoS. This framework provides an admission control mechanism that only accepts jobs whose requested deadlines can be met and, once accepted, guarantees these deadlines. However, the framework is completely blind to the revenue these jobs can fetch for the supercomputer center. By accepting a job, the supercomputer center might relinquish its capability to accept some future arriving (and potentially more expensive) jobs. In other words, while each job pays an explicit price to the system for running it, the system may also be viewed as paying an implicit opportunity cost by accepting the job. Thus, accepting a job is profitable only when the job's price is higher than its opportunity cost. In this paper we analyze the impact such opportunity cost can have on the overall revenue of the supercomputer center and attempt to minimize it through predictive techniques. Specifically, we propose two extensions to QoPS, Value-aware QoPS (VQoPS) and Dynamic Value-aware QoPS (DVQoPS), to provide such capabilities. We present detailed analysis of these schemes and demonstrate using simulation that they not only achieve several factors improvement in system revenue, but also good service differentiation as a much desired side-effect.

  13. Job Description Job Title: ORE Marine Research Engineer

    E-Print Network [OSTI]

    Frandsen, Jannette B.

    Job Summary Regular, Full-Time, RCUH Non-Civil Service position with the Ocean & Resource Engineering for a new ocean engineering research and development laboratory focused on ocean observing including sensor. EXPERIENCE: At least seven (7) years of post-graduate experience in ocean engineering design, fabrication

  14. 2013 Annual Workforce Analysis and Staffing Plan Report- Office of Health, Safety and Security

    Broader source: Energy.gov [DOE]

    Managers perform an annual workforce analysis of their organization and develop staffing plans that identify technical capabilities and positions they need to ensure safe operation of defense nuclear facilities.

  15. 2013 Annual Workforce Analysis and Staffing Plan Report- Chief of Nuclear Safety

    Broader source: Energy.gov [DOE]

    Managers perform an annual workforce analysis of their organization and develop staffing plans that identify technical capabilities and positions they need to ensure safe operation of defense nuclear facilities.

  16. 2014 Annual Workforce Analysis and Staffing Plan Report- Chief of Nuclear Safety

    Broader source: Energy.gov [DOE]

    Managers perform an annual workforce analysis of their organization and develop staffing plans that identify technical capabilities and positions they need to ensure safe operation of defense nuclear facilities.

  17. 2012 Annual Workforce Analysis and Staffing Plan Report- Chief of Nuclear Safety

    Broader source: Energy.gov [DOE]

    Managers perform an annual workforce analysis of their organization and develop staffing plans that identify technical capabilities and positions they need to ensure safe operation of defense nuclear facilities.

  18. 2011 Annual Workforce Analysis and Staffing Plan Report- Office of Health, Safety and Security

    Broader source: Energy.gov [DOE]

    Managers perform an annual workforce analysis of their organization and develop staffing plans that identify technical capabilities and positions they need to ensure safe operation of defense nuclear facilities.

  19. 2010 Annual Workforce Analysis and Staffing Plan Report- Office of Health, Safety and Security

    Broader source: Energy.gov [DOE]

    Managers perform an annual workforce analysis of their organization and develop staffing plans that identify technical capabilities and positions they need to ensure safe operation of defense nuclear facilities.

  20. 2012 Annual Workforce Analysis and Staffing Plan Report- Office of Health, Safety and Security

    Broader source: Energy.gov [DOE]

    Managers perform an annual workforce analysis of their organization and develop staffing plans that identify technical capabilities and positions they need to ensure safe operation of defense nuclear facilities.

  1. 2014 Annual Workforce Analysis and Staffing Plan Report- Office of Environment, Health, Safety and Security

    Broader source: Energy.gov [DOE]

    Managers perform an annual workforce analysis of their organization and develop staffing plans that identify technical capabilities and positions they need to ensure safe operation of defense nuclear facilities.

  2. Job descriptions are essential for: Organizing work units

    E-Print Network [OSTI]

    Thomas, David D.

    Job and useful descriptions. 1. Provide an overview of unit program 2. Identify the major job functions 3 requirements 6. Add appropriate disclaimer statements Supervisory Job Aid Revised May 2011 Writing a Job

  3. Documenting Targeted Behaviors Associated with Pedestrian Safety

    E-Print Network [OSTI]

    Cooper, Jill F.; Schneider, Robert J.; Ryan, Sherry; Co, Sean

    2013-01-01T23:59:59.000Z

    Intersections. Accident Analysis and Prevention, Vol. 39,Pedestrian Safety. Accident Analysis and Prevention, Vol.Conflicts Technique. Accident Analysis and Prevention, Vol.

  4. Job Training Incentive Program (New Mexico)

    Broader source: Energy.gov [DOE]

    This program funds classroom and on-the-job training for newly-created jobs in expanding or relocating businesses for up to six months. The program reimburses 40-75% of employee wages. Custom...

  5. Geothermal Development Job Types and Impacts

    Broader source: Energy.gov [DOE]

    Development of geothermal power plants and direct-use applications creates a variety of jobs. And the resulting job creation and economic activity within the geothermal industry positively impacts...

  6. Rural Job Tax Credit Program (Florida)

    Broader source: Energy.gov [DOE]

    The Rural Job Tax Credit Program is an incentive for businesses located within one of the 36-designated Qualified Rural Areas to create new jobs. The tax credit ranges from $1000 to $1500 per...

  7. Job Development Investment Grant (North Carolina)

    Broader source: Energy.gov [DOE]

    The Job Development Investment Grant awards cash grants to new and expanding businesses that will provide economic benefit to that state. Grants are based on job creation and investment commitment...

  8. Jobs and Investment Tax Credit (Maine)

    Broader source: Energy.gov [DOE]

    The Jobs and Investment Tax Credit is available to businesses that create at least 100 new jobs within two years and invest at least $5 million in one year. The credit is limited to tax liability...

  9. Job Creation Tax Credits Program (Pennsylvania)

    Broader source: Energy.gov [DOE]

    The Job Creation Tax Credits Program can be used to offset business tax liabilities and is available to businesses that create 25 or more jobs or increase employment by 20% within three years of a...

  10. Benefit-Cost Analysis of Heavy Haul Railway Track Upgrade for Safety and Efficiency X. Liu, M.R. Saat, C.P.L. Barkan

    E-Print Network [OSTI]

    Barkan, Christopher P.L.

    1 Benefit-Cost Analysis of Heavy Haul Railway Track Upgrade for Safety and Efficiency X. Liu, M of train accident on North American heavy-haul railroads and reducing their occurrence and severity is an ongoing objective of both industry and government. Upgrading track quality is one possible derailment

  11. Proceedings of: X Convegno Tecnologie e Sistemi Energetici Complessi, (TESEC), June 2001, Genova, Italy ADVANCED TECHNIQUES FOR SAFETY ANALYSIS APPLIED TO

    E-Print Network [OSTI]

    Tronci, Enrico

    , Italy 1 ADVANCED TECHNIQUES FOR SAFETY ANALYSIS APPLIED TO THE GAS TURBINE CONTROL SYSTEM OF ICARO CO of complex computer based systems. Such approaches are applied to the gas turbine control system of ICARO co of the centre of ENEA CR Casaccia. The plant is based on a small gas turbine and has been specifically designed

  12. PGDP (Paducah Gaseous Diffusion Plant)-UF/sub 6/ handling, sampling, analysis and associated QC/QA and safety related procedures

    SciTech Connect (OSTI)

    Harris, R.L. (comp.)

    1987-05-22T23:59:59.000Z

    This document is a compilation of Paducah Gaseous Diffusion Plant procedures on UF/sub 6/ handling, sampling, and analysis, along with associated QC/QA and safety related procedures. It was assembled for transmission by the US Department of Energy to the Korean Advanced Energy Institute as a part of the US-Korea technical exchange program.

  13. HOW TO FIND A JOB Candidates looking for jobs and employers seeking candidates find each

    E-Print Network [OSTI]

    Suzuki, Masatsugu

    HOW TO FIND A JOB Candidates looking for jobs and employers seeking candidates find each other in a variety of ways. In any economy, a job search should utilize many strategies including resources a short-term position. The question to ask yourself before you begin your search is "What kind of job

  14. Wage and Job Dynamics After Welfare Reform: The Importance of Job Skills

    E-Print Network [OSTI]

    Shyy, Wei

    Wage and Job Dynamics After Welfare Reform: The Importance of Job Skills Rucker C. Johnson), and the Office of the Vice-President for Research at the University of Michigan. #12;Wage and Job Dynamics After Welfare Reform: The Importance of Job Skills Abstract I use data from employers and longitudinal data from

  15. Exempt UNBC Job Evaluation Process Page 1 of 5 JOB EVALUATION

    E-Print Network [OSTI]

    Northern British Columbia, University of

    Exempt UNBC Job Evaluation Process Page 1 of 5 EXEMPT JOB EVALUATION Date of Incorporation On July 1, 1997 the University and the Exempt Employees Group incorporated a job evaluation system-evaluation process. 2) The Exempt Employees Group shall be entitled to appoint one (1) member to the Job Evaluation

  16. Supervisory, Information Technology Specialist Job Title: Supervisory...

    Energy Savers [EERE]

    Supervisory, Information Technology Specialist Job Title: Supervisory, Information Technology Specialist Agency: Department of Energy Hiring Organization: Office of Intelligence...

  17. Page 1 of 14 5/2010 LBNL Construction Safety Check List

    E-Print Network [OSTI]

    Knowles, David William

    Page 1 of 14 5/2010 LBNL Construction Safety Check List Safety Check List MUST be posted at the job (LBNL) Project Manager for review and final approval the LBNL Construction Safety Engineer must reviewed performing work at LBNL. These items and all other requirements in the contractual documents will be enforced

  18. The Quality Jobs Tax Credit (Georgia)

    Broader source: Energy.gov [DOE]

    The Quality Jobs Tax Credit provides a tax credit of $2,500-$5,000 per job, per year, for up to five year to companies that create at least 50 jobs in a twelve month period. Credits may be carried...

  19. REPORTED JOB SATISFACTION: WHAT DOES IT MEAN?

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    1 REPORTED JOB SATISFACTION: WHAT DOES IT MEAN? Louis Lévy-Garboua TEAM (CNRS), University of Paris or regret, i.e. the difference between what happened and what might have happened, on job satisfaction. The main prediction that we test is that job satisfaction correlates with the wage gaps experienced

  20. Technical Review Report for the Safety Analysis Report for Packaging Model 9977 S-SARP-G-00001 Revision 2

    SciTech Connect (OSTI)

    DiSabatino, A; Hafner, R; West, M

    2007-10-04T23:59:59.000Z

    This Technical Review Report (TRR) summarizes the review findings for the Safety Analysis Report for Packaging (SARP) for the Model 9977 B(M)F-96 shipping container. The content analyzed for this submittal is Content Envelope C.1, Heat Sources, in assemblies of Radioisotope Thermoelectric Generators or food-pack cans. The SARP under review, i.e., S-SARP-G-00001, Revision 2 (August 2007), was originally referred to as the General Purpose Fissile Material Package. The review presented in this TRR was performed using the methods outlined in Revision 3 of the Department of Energy's (DOE's) Packaging Review Guide (PRG) for Reviewing Safety Analysis Reports for Packages. The format of the SARP follows that specified in Revision 2 of the Nuclear Regulatory Commission's, Regulatory Guide 7.9, i.e., Standard Format and Content of Part 71 Applications for Approval of Packages for Radioactive Material. Although the two documents are similar in their content, they are not identical. Formatting differences have been noted in this TRR, where appropriate. The Model 9977 Package is a 35-gallon drum package design that has evolved from a family of packages designed by DOE contractors at the Savannah River Site. The Model 9977 Package design includes a single, 6-inch diameter, stainless steel pressure vessel containment system (i.e., the 6CV) that was designed and fabricated in accordance with Section III, Subsection NB, of the American Society of Mechanical Engineers Boiler & Pressure Vessel Code. The earlier package designs, i.e., the Model 9965, 9966, 9967 and 9968 Packages, were originally designed and certified in the 1980s. In the 1990s, updated package designs that incorporated design features consistent with new safety requirements, based on International Atomic Energy Agency guidelines, were proposed. The updated package designs were the Model 9972, 9973, 9974 and 9975 Packages, respectively. The Model 9975 Package was certified by the Packaging Certification Program, under the Office of Safety Management and Operations. Differences between the Model 9975 Package and the Model 9977 Package include: (1) The lead shield present in the Model 9975 Package is absent in the Model 9977 Package; (2) The Model 9975 Package has eight allowable contents, while the Model 9977 Package has a single allowable content. (3) The 6CV of the Model 9977 Package is similar in design to the outer Containment Vessel of the Model 9975 Package that also incorporates a 5-inch Containment Vessel as the inner Containment Vessel. (4) The Model 9975 Package uses a Celotex{reg_sign}-based impact limiter while the Model 9977 Package uses Last-A-Foam{reg_sign}, a polyurethane foam, for the impact limiter. (5) The Model 9975 Package has two Containment Vessels, while the Model 9977 Package has a single Containment Vessel.

  1. ANALYSIS OF SAFETY RELIEF VALVE PROOF TEST DATA TO OPTIMIZE LIFECYCLE MAINTENANCE COSTS

    SciTech Connect (OSTI)

    Gross, Robert; Harris, Stephen

    2007-08-01T23:59:59.000Z

    Proof test results were analyzed and compared with a proposed life cycle curve or hazard function and the limit of useful life. Relief valve proof testing procedures, statistical modeling, data collection processes, and time-in-service trends are presented. The resulting analysis of test data allows for the estimation of the PFD. Extended maintenance intervals to the limit of useful life as well as methodologies and practices for improving relief valve performance and reliability are discussed. A generic cost-benefit analysis and an expected life cycle cost reduction concludes that $90 million maintenance dollars might be avoided for a population of 3000 valves over 20 years.

  2. Green Jobs and Energy Economy

    E-Print Network [OSTI]

    Kammen, Daniel M.

    , that is The clean energy industry has been targeted as a key area for investment for three primary reasons: greaterGreen Jobs and the Clean Energy Economy ThoughT Leadership series Co-authors Daniel M. Kammen, Founding Director, Renewable and Appropriate Energy Laboratory University of California, Berkeley Ditlev

  3. Green Jobs and Energy Economy

    E-Print Network [OSTI]

    Kammen, Daniel M.

    as a key area for investment for three primary reasons: greater energy in- dependence, improvedGreen Jobs and the Clean Energy Economy THOUGHT LEADERSHIP SERIES Co-authors Ditlev Engel, Chief Distinguished Professor of Energy Founding Director, Renewable and Appropriate Energy Laboratory Co

  4. Illinois Jobs Index release 11/28/2011 www.real.illinois.edu page 1 For August Illinois Job Index, the state and the Nation had positive job growth, the RMW had negative job growth.

    E-Print Network [OSTI]

    Frank, Thomas D.

    Illinois Jobs Index release 11/28/2011 www.real.illinois.edu page 1 For August Illinois Job Index, the state and the Nation had positive job growth, the RMW had negative job growth. The Illinois Job Index Positive Sep 2011­ Oct 2011 Last 12 months Oct 2011 Total non-farm employment Growth Rate % Number of Jobs

  5. Indeed is the #1 job search engine worldwide. Since 2004, Indeed has given job seekers free access to millions of jobs from thousands of company websites and job boards. Our core mis-

    E-Print Network [OSTI]

    Ghosh, Joydeep

    Indeed is the #1 job search engine worldwide. Since 2004, Indeed has given job seekers free access to millions of jobs from thousands of company websites and job boards. Our core mis- sion is to help people get jobs. To make this possible, we built an amazing platform that han- dles 5 billion job search

  6. Illinois Jobs Index release 10/31/2011 www.real.illinois.edu page 1 For August Illinois Job Index, the state and the Nation had positive job growth, the RMW had negative job growth.

    E-Print Network [OSTI]

    Frank, Thomas D.

    Illinois Jobs Index release 10/31/2011 www.real.illinois.edu page 1 For August Illinois Job Index, the state and the Nation had positive job growth, the RMW had negative job growth. The Illinois Job Index Positive Aug 2011­ Sep 2011 Last 12 months Sep 2011 Total non-farm employment Growth Rate % Number of Jobs

  7. Creating a Job Search Plan UWM Alumni Career Services

    E-Print Network [OSTI]

    Saldin, Dilano

    Creating a Job Search Plan UWM Alumni Career Services Cindy Petrites, Ph.D. www.alumni.uwm.edu #12;Agenda · Reasons for a job search plan · Job search essentials and how to prioritize · Keeping track of your job search · Creating a flexible job search plan #12;Reasons for a Job Search Plan Can help you

  8. Illinois Jobs Index release 01/31/2011 www.real.illinois.edu page 1 For November Illinois Job Index, the state and the Nation had positive job growth, the RMW had negative job growth.

    E-Print Network [OSTI]

    Frank, Thomas D.

    Illinois Jobs Index release 01/31/2011 www.real.illinois.edu page 1 For November Illinois Job Index, the state and the Nation had positive job growth, the RMW had negative job growth. The Illinois Job Index Negative Nov 2011­ Dec 2011 Last 12 months Dec 2011 Total non-farm employment Growth Rate % Number of Jobs

  9. Technical Review Report for the Model 9975-96 Package Safety Analysis Report for Packaging (S-SARP-G-00003, Revision 0, January 2008)

    SciTech Connect (OSTI)

    West, M

    2009-05-22T23:59:59.000Z

    This Technical Review Report (TRR) documents the review, performed by the Lawrence Livermore National Laboratory (LLNL) Staff, at the request of the U.S. Department of Energy (DOE), on the Safety Analysis Report for Packaging, Model 9975, Revision 0, dated January 2008 (S-SARP-G-00003, the SARP). The review includes an evaluation of the SARP, with respect to the requirements specified in 10 CFR 71, and in International Atomic Energy Agency (IAEA) Safety Standards Series No. TS-R-1. The Model 9975-96 Package is a 35-gallon drum package design that has evolved from a family of packages designed by DOE contractors at the Savannah River Site. Earlier package designs, i.e., the Model 9965, the Model 9966, the Model 9967, and the Model 9968 Packagings, were originally designed and certified in the early 1980s. In the 1990s, updated package designs that incorporated design features consistent with the then newer safety requirements were proposed. The updated package designs at the time were the Model 9972, the Model 9973, the Model 9974, and the Model 9975 Packagings, respectively. The Model 9975 Package was certified by the Packaging Certification Program, under the Office of Safety Management and Operations. The safety analysis of the Model 9975-85 Packaging is documented in the Safety Analysis Report for Packaging, Model 9975, B(M)F-85, Revision 0, dated December 2003. The Model 9975-85 Package is certified by DOE Certificate of Compliance (CoC) package identification number, USA/9975/B(M)F-85, for the transportation of Type B quantities of uranium metal/oxide, {sup 238}Pu heat sources, plutonium/uranium metals, plutonium/uranium oxides, plutonium composites, plutonium/tantalum composites, {sup 238}Pu oxide/beryllium metal.

  10. Safety Analysis Report for the use of hazardous production materials in photovoltaic applications at the National Renewable Energy Laboratory

    SciTech Connect (OSTI)

    Crandall, R.S.; Nelson, B.P. [National Renewable Energy Lab., Golden, CO (United States); Moskowitz, P.D.; Fthenakis, V.M. [Brookhaven National Lab., Upton, NY (United States)

    1992-07-01T23:59:59.000Z

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

  11. Facility Safety

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

    2000-11-20T23:59:59.000Z

    The objective of this Order is to establish facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation. The Order has Change 1 dated 11-16-95, Change 2 dated 10-24-96, and the latest Change 3 dated 11-22-00 incorporated. The latest change satisfies a commitment made to the Defense Nuclear Facilities Safety Board (DNFSB) in response to DNFSB recommendation 97-2, Criticality Safety.

  12. Occupational Health and Safety Animal Job Exposure Form

    E-Print Network [OSTI]

    California at Santa Barbara, University of

    symptoms within the past year? Chronic Cough Asthma Hay Fever Skin Rash Eczema Chronic Allergies (food

  13. FAQS Job Task Analyses - Nuclear Safety Specialist | Department of Energy

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011AT&T,OfficeEnd of Year 2010Salt |ExelonFAQ: RelocationCriticalityFireof

  14. FAQS Job Task Analyses - Occupational Safety | Department of Energy

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011AT&T,OfficeEnd of Year 2010Salt |ExelonFAQ: RelocationCriticalityFireofOccupational

  15. FAQS Job Task Analyses - Electrical Systems and Safety Oversight |

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't YourTransport in Representative Geologic Media |EfficientConstruction Management FAQSDepartment

  16. Job Safety and Health Poster | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742Energy ChinaofSchaeferApril 1, 1999 InspectionVolunteers from theJaneJared

  17. FAQS Job Task Analyses - Deactivation and Decommissioning | Department of

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011AT&T,OfficeEnd of Year 2010Salt |ExelonFAQ: RelocationCriticality Safety FAQS Job

  18. Jobs and Economic Development Impacts from Small Wind: JEDI Model in the Works (Presentation)

    SciTech Connect (OSTI)

    Tegen, S.

    2012-06-01T23:59:59.000Z

    This presentation covers the National Renewable Energy Laboratory's role in economic impact analysis for wind power Jobs and Economic Development Impacts (JEDI) models, JEDI results, small wind JEDI specifics, and a request for information to complete the model.

  19. Mixed-oxide fuel decay heat analysis for BWR LOCA safety evaluation

    SciTech Connect (OSTI)

    Chiang, R. T. [AREVA Inc., 303 Ravendale Drive, Mountain View, CA 94043 (United States)

    2013-07-01T23:59:59.000Z

    The mixed-oxide (MOX) fuel decay heat behavior is analyzed for Boiling Water Reactor (BWR) Loss of Coolant Accident (LOCA) safety evaluation. The physical reasoning on why the decay heat power fractions of MOX fuel fission product (FP) are significantly lower than the corresponding decay heat power fractions of uranium-oxide (UOX) fuel FP is illustrated. This is primarily due to the following physical phenomena. -The recoverable energies per fission of plutonium (Pu)-239 and Pu-241 are significantly higher than those of uranium (U)-235 and U-238. Consequently, the fission rate required to produce the same amount of power in MOX fuel is significantly lower than that in UOX fuel, which leads to lower subsequent FP generation rate and associated decay heat power in MOX fuel than those in UOX fuel. - The effective FP decay energy per fission of Pu-239 is significantly lower than the corresponding effective FP decay energy per fission of U-235, e.g., Pu-239's 10.63 Mega-electron-Volt (MeV) vs. U-235's 12.81 MeV at the cooling time 0.2 second. This also leads to lower decay heat power in MOX fuel than that in UOX fuel. The FP decay heat is shown to account for more than 90% of the total decay heat immediately after shutdown. The FP decay heat results based on the American National Standard Institute (ANSI)/American Nuclear Society (ANS)-5.1-1979 standard method are shown very close to the corresponding FP decay heat results based on the ANSI/ANS-5.1-2005 standard method. The FP decay heat results based on the ANSI/ANS-5.1-1979 simplified method are shown very close to but mostly slightly lower than the corresponding FP decay heat results based on the ANSI/ANS-5.1-1971 method. The FP decay heat results based on the ANSI/ANS-5.1-1979 simplified method or the ANSI/ANS-5.1-1971 method are shown significantly larger than the corresponding FP decay heat results based on the ANSI/ANS-5.1-1979 standard method or the ANSI/ANS-5.1-2005 standard method. (authors)

  20. Analysis of the Relationship Between Vehicle Weight/Size and Safety, and Implications for Federal Fuel Economy Regulation

    E-Print Network [OSTI]

    Wenzel, Thomas P.

    2010-01-01T23:59:59.000Z

    for Federal Fuel Economy Regulation Final Report preparedand have higher fuel economy, and safer than conventionaland have higher fuel economy, without sacrificing safety. 1.