Sample records for mgr lajos grof-tisza

  1. Appendix 7 - Stripes Architecture Overview

    Broader source: (indexed) [DOE]

    Name: Department of Energy iManage Program Project ID: iManage Program STRIPES Project Project Manager: Mathew Sparks Program Mgr: Lajos Grof-Tisza Doc ID: STRIPES Technical...


    SciTech Connect (OSTI)

    J.A. Kappes


    The purpose of this analysis is to identify the preliminary design basis events (DBEs) for consideration in the design of the Monitored Geologic Repository (MGR). For external events and natural phenomena (e.g., earthquake), the objective is to identify those initiating events that the MGR will be designed to withstand. Design criteria will ensure that radiological release scenarios resulting from these initiating events are beyond design basis (i.e., have a scenario frequency less than once per million years). For internal (i.e., human-induced and random equipment failures) events, the objective is to identify credible event sequences that result in bounding radiological releases. These sequences will be used to establish the design basis criteria for MGR structures, systems, and components (SSCs) design basis criteria in order to prevent or mitigate radiological releases. The safety strategy presented in this analysis for preventing or mitigating DBEs is based on the preclosure safety strategy outlined in ''Strategy to Mitigate Preclosure Offsite Exposure'' (CRWMS M&O 1998f). DBE analysis is necessary to provide feedback and requirements to the design process, and also to demonstrate compliance with proposed 10 CFR 63 (Dyer 1999b) requirements. DBE analysis is also required to identify and classify the SSCs that are important to safety (ITS).

  3. Comp. Sys. Mgr. 4 Curtis Rias

    E-Print Network [OSTI]

    Brinkmann, Peter

    IT Procurement Management Student Technology Fee Coordination Mobile Devices Coordination Site Licensing Coordination Computer Labs Management CUNYfirst Readiness & CUNY Alert Liaison TECHNOLOGY ADVISORY COMMITTEE Project Management Office (PMO) ISS IT Internal Operations Management Office of Information Technology

  4. Title: Freedom of Information Request DIR DIV NAME MGR DEP AMA

    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'sis Taking Over OurThe Iron Spin Transition in2, 2003 (NextTime-Resolved Study91

  5. Emergency Operations Training Academy | National Nuclear Security...

    National Nuclear Security Administration (NNSA)

    Introduction Monitoring Division Mgr Training, Adv NARAC Dispersion Modeling NARAC Web Operations Overview of Consequence Management Overview of the DOENNSA Emergency...


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

    HIRING REQUEST EMPLOYMENT REQUISITION WORKSHEET Hiring Manager: Working Job Title: Supervisor (if not Hire Mgr): Classification Title: Department Name: Employment Type: Regular...

  7. Slide 1

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

    Design 2013 Inverter Reliability Workshop Sandia National Laboratories Electric Power Research Institute (EPRI) Janet Ma, Ph. D, Mgr., Design Quality April, 2013, Santa...

  8. Peggy Burns Asst Dean for

    E-Print Network [OSTI]

    Resnick, Paul

    Dir (Eastern States) Gail Flynn Campaign Director Kristy Demas Acknowledgement Writer Michele Siegal, Marketing & Communications Organizational Chart Updated 4/11/2014 Doug Fletcher Scholarship Program Mgr


    E-Print Network [OSTI]

    Maxwell, Bruce D.

    Barb Stephens Jeff Butler Recruiting Engineering & Utilities A t Di /Mg Campus Maintenance Supervisor Accounting Associates --Asst. Dir/Mgr--- Dan Stevenson Engineering University Engineer --Supervisor-- Tom

  10. ZiS International Office -ZiS Zentrum fr

    E-Print Network [OSTI]

    Mayberry, Marty

    : Mitteleuropa; grenzt an Deutschland, Tschechien, Slowenien, die Slowakei, Ungarn, Italien, die Schweiz und weiterer Gebiete in Europa. So wurden z.B. in Ungarn bereits die Habsburger abgesetzt und Lajos Kossuth Österreich-Ungarn. Doppelmonarchie Österreich-Ungarn Am 15. März 1867 trat die neue Regelung der Umwandlung

  11. 2212 IEEE TRANSACTIONS ON INFORMATION THEORY, VOL. 46, NO. 6, SEPTEMBER 2000 The Super-Trellis Structure of Turbo Codes

    E-Print Network [OSTI]

    Verdú, Sergio

    -Trellis Structure of Turbo Codes Marco Breiling, Student Member, IEEE, and Lajos Hanzo, Senior Member, IEEE Abstract--In this contribution we derive the super-trellis structure of turbo codes. We show that this structure and its associated decoding com- plexity depend strongly on the interleaver applied in the turbo encoder. We provide

  12. Office: ITO PE/Project

    E-Print Network [OSTI]

    Mills, Kevin

    Mgr.: Mills/Swinson PAD No.: Smart Spaces Moving Through Smart Spaces "city-wide appliances" "in1 DARPA Office: ITO PE/Project: Pgm No.: Pgm Mgr.: Mills/Swinson PAD No.: Smart Spaces Personal Information Projection · Develop techniques for projecting personal information from cyberspace into smart

  13. Sample and Implied Volatility in GARCH Models

    E-Print Network [OSTI]

    Kokoszka, Piotr

    Sample and Implied Volatility in GARCH Models Lajos Horva´th University of Utah Piotr Kokoszka Utah of various GARCH-type models is a function hðq� of the parameter vector q which is estimated by bq. For most distributions of the differences ^2 � hðq� and ^2 � hðbq� for broad classes of GARCH-type models. Even though

  14. Chemistry Safety Notes Volume 1, Issue 2 December 2013

    E-Print Network [OSTI]

    Guo, Ting

    by the Chemistry Dept. Safety Committee, written & edited by Debbie Decker, Safety Mgr. EH&S Inspections EH extinguisher, there's a green tag with the fire marshal stamp on one side. On the reverse, there's a list

  15. Electric Utility Measurement & Verification Program

    E-Print Network [OSTI]

    Lau, K.; Henderson, G.; Hebert, D.

    Electric Utility Measurement & Verification Program Ken Lau, P.Eng., CMVP Graham Henderson, P.Eng., CMVP Dan Hebert, P.Eng.,CMVP Mgr, Measurement & Verification Engineering Team Leader Senior Engineer BC Hydro Burnaby, BC Canada...

  16. Appendix 5 - STARS Architectual Overview

    Broader source: (indexed) [DOE]

    Mgr from C Simpson to W Huffer Richard Popovich 1.07 18 Oct 05 Updated Figure 1 (Architecture Diagram) added IDW servers (LPARS), Oracle 10G AS portal server, and File Upload...

  17. alloy-ehi 432: Topics by E-print Network

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

    Sys George Hines 432-3101 Finance & Admin Mgr Sonja Beamon Rezendes 432-5681 Dir 3 Syllabus: CS432 Database Systems Course Number: CS432-01 Computer Technologies and Information...

  18. B174 Complex -

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

    03438 Mason-Reed, Vicki 2-0184 66840 Dixon, Jay 2-4774 Facility Manager Industrial Hygiene Marks, Jonathan 2-8235 05047 Robertson, Janeen 3-3170 67872 PLS Assurance Mgr....

  19. LISTE DES DOCTORATS HONORIFIQUES (ordre chronologique)

    E-Print Network [OSTI]

    Charette, André

    , Joseph Médecine PAUTRIER, Lucien (France) 1924 Lettres NANTEL, Mgr Antonin Droit PERRON, l'honorable J Agriculture BLACK, W.J. Lettres BORDEAUX, Henry Droit CAPITANT, Henri Lucien CHARLETY, Sébastien (France

  20. Praveen Panchal VP of IT and CIO

    E-Print Network [OSTI]

    Brinkmann, Peter

    Technology (OIT) Organization Chart ­ June 13 Mark Kam Deputy CIO Comp. Sys. Mgr. 4 Project Management Office Distribution & Management BARFIT* Coordination Time Keeping IT Procurement Management Student Technology Fee Coordination Mobile Devices Coordination Site Licensing Coordination Computer Labs Management CUNYfirst

  1. Libri ricevuti

    E-Print Network [OSTI]


    Vescovi e Regolari, Malta:Visita Apo- stolica no. 51, Mgr.George A QUILINA OFM , Stanley F IORINI , Malta UniversityPress, Malta 2001, pp. XXXIV +528, 4 tavv. b/n. Documentary


    SciTech Connect (OSTI)

    R.E. Sweeney


    The purpose of this assumptions document is to provide general scope, strategy, technical basis, schedule and cost assumptions for the Monitored Geologic Repository (MGR) life cycle cost (LCC) estimate and schedule update incorporating information from the Viability Assessment (VA) , License Application Design Selection (LADS), 1999 Update to the Total System Life Cycle Cost (TSLCC) estimate and from other related and updated information. This document is intended to generally follow the assumptions outlined in the previous MGR cost estimates and as further prescribed by DOE guidance.


    E-Print Network [OSTI]


  4. Audience/Panel Discussion: Sites Lesson Learned about Activity-level Work Planning and Control Using EFCOG Work Planning and Control Guideline

    Broader source: [DOE]

    Slide Presentation by Donna J. Governor, Deputy Dept Mgr for Planning & Integration, Lawrence Livermore National Laboratory. Lawrence Livermore National Laboratory work planning and control lessons learned and audience/panel discussion on site's lessons learned about Activity-level Work Planning and Control using EFCOG Work Planning and Control Guideline Document.

  5. Particle Physics & Astrophysics David MacFarlane, Director

    E-Print Network [OSTI]

    Wechsler, Risa H.

    Division Head CDMS Richard Partridge Dept Head KIPAC Computing Stuart Marshall Dept Head DES David Burke Services Mgr. Debbie Tryforos Assistant to the Director Sensors & Detectors Chris Kenney Dept Head Redwood Conference Rooms SLUO Debbie Tryforos Assistant to the Director HEP Faculty Coordiantor Assistant


    E-Print Network [OSTI]

    Liblit, Ben

    ) Consider the following (terribly surprising, no doubt) SQL database definitions: CREATE TABLE Emp(emp PRIMARY KEY (emp_id), CONSTRAINT ec2 FOREIGN KEY (dept_id) REFERENCES (Dept)) CREATE TABLE Dept KEY (dept_id), CONSTRAINT dc2 FOREIGN KEY (mgr_id) REFERENCES (Emp)) (Note that ec1, ec2, etc are just

  7. Chicago's Artisan Baker TM Job Title: Production Supervisor Department: Production

    E-Print Network [OSTI]

    Heller, Barbara

    Chicago's Artisan Baker TM Job Title: Production Supervisor Department: Production Revision Date: 07/15/2012 Reports To: Sr. Production Mgr. Position Overview: The Supervisor's major responsibility is to oversee the daily production operations. This position has the responsibility of coordinating all

  8. Praveen Panchal VP of IT and CIO

    E-Print Network [OSTI]

    Brinkmann, Peter

    Technology Fee Coordination Mobile Devices Coordination Site Licensing Coordination Computer Labs Management Technology (OIT) Organization Chart ­ April 14 Mark Kam Deputy CIO Comp. Sys. Mgr. 4 Project Management IT Internal Operations Management CETL Office of Information Technology (OIT) Organization Chart ­ April 14

  9. LSAIT................................................................................................................................ 1 Contents...............................................................................................................

    E-Print Network [OSTI]

    Resnick, Paul

    , Karen Desktop Support Specialist Sr #12;Dietrich, Erin IT Program Manager Antonelli,Charles App Administrator Senior Nance, Daniel Data Security Analyst Inter Pachla,Karen Systems & Programming Mgr Pelcher Senior Torgersen, John Database Administrator Inter #12;Cox, Doug Desktop Support Manager Berry, Ali

  10. Energy-Efficient Platform Designs for Real-World Wireless Sensing Applications

    E-Print Network [OSTI]

    Shinozuka, Masanobu

    Unit Scheduler Power Mgr Driver Calib. PowerReg.&Distr.Switch windmill solar panel battery other the trade-offs of sensing devices, wireless interfaces, and computation and control units. We also cover Controller mod Sensor + Detector ADC /det Reference Loc. Sens. Sensing Unit Processing Unit Communication

  11. Intact and Degraded Component Criticality Calculations of N Reactors Spent Nuclear Fuel

    SciTech Connect (OSTI)

    L. Angers


    The objective of this calculation is to perform intact and degraded mode criticality evaluations of the Department of Energy's (DOE) N Reactor Spent Nuclear Fuel codisposed in a 2-Defense High-Level Waste (2-DHLW)/2-Multi-Canister Overpack (MCO) Waste Package (WP) and emplaced in a monitored geologic repository (MGR) (see Attachment I). The scope of this calculation is limited to the determination of the effective neutron multiplication factor (k{sub eff}) for both intact and degraded mode internal configurations of the codisposal waste package. This calculation will support the analysis that will be performed to demonstrate the technical viability for disposing of U-metal (N Reactor) spent nuclear fuel in the potential MGR.

  12. Light-Emitting Tag Testing in Conjunction with Testing of the Minimum Gap Runner Turbine Design at Bonneville Dam Powerhouse 1

    SciTech Connect (OSTI)

    Carlson, Thomas J.; Weiland, Mark A.


    This report describes a pilot study conducted by Tom Carlson of PNNL and Mark Weiland of MEVATEC Corp to test the feasibility of using light-emitting tags to visually track objects passing through the turbine environment of a hydroelectric dam. Light sticks were released at the blade tip, mid-blade, and hub in the MGR turbine and a Kaplan turbine at Bonneville Dam and videotaped passing thru the dam to determine visibility and object trajectories.


    SciTech Connect (OSTI)

    S.O. Bader


    The purpose of this design analysis is to specify and document the total and respirable fractions for radioactive materials that are released from an accident event at the Monitored Geologic Repository (MGR) involving commercial spent nuclear fuel (CSNF) in a dry environment. The total and respirable release fractions will be used to support the preclosure licensing basis for the MGR. The total release fraction is defined as the fraction of total CSNF assembly inventory, typically expressed as an activity inventory (e.g., curies), of a given radionuclide that is released to the environment from a waste form. The radionuclides are released from the inside of breached fuel rods (or pins) and from the detachment of radioactive material (crud) from the outside surfaces of fuel rods and other components of fuel assemblies. The total release fraction accounts for several mechanisms that tend to retain, retard, or diminish the amount of radionuclides that are available for transport to dose receptors or otherwise can be shown to reduce exposure of receptors to radiological releases. The total release fraction includes a fraction of airborne material that is respirable and could result in inhalation doses. This subset of the total release fraction is referred to as the respirable release fraction. Potential accidents may involve waste forms that are characterized as either bare (unconfined) fuel assemblies or confined fuel assemblies. The confined CSNF assemblies at the MGR are contained in shipping casks, canisters, or disposal containers (waste packages). In contrast to the bare fuel assemblies, the container that confines the fuel assemblies has the potential of providing an additional barrier for diminishing the total release fraction should the fuel rod cladding breach during an accident. However, this analysis will not take credit for this additional bamer and will establish only the total release fractions for bare unconfined CSNF assemblies, which may however be conservatively applied to confined CSNF assemblies.

  14. Monday Musings, October 22, 2012

    E-Print Network [OSTI]


    and organizational review teams. As always, I welcome your feedback—simply reply to this message with questions or comments. -- STRATEGIC PLANNING Oversight Team Update | Mary Roach (chair) and Aileen Ball (co-chair): On Friday, October 12th, members... Riley ? Brian Rosenblum ? Kathleen Ames-Oliver, HR Mgr Learning & Development (and frequent special guest) -- OA Fund Today, we announced the creation of a $50,000 author’s fund to support open access scholarship at KU’s Lawrence campus and the KU...

  15. ESF Mine Power Center Platforms

    SciTech Connect (OSTI)

    T.A. Misiak


    The purpose and objective of this analysis is to structurally evaluate the existing Exploratory Studies Facility (ESF) mine power center (MPC) support frames and to design service platforms that will attach to the MPC support frames. This analysis follows the Development Plan titled ''Produce Additional Design for Title 111 Evaluation Report'' (CRWMS M&O 1999a). This analysis satisfies design recommended in the ''Title III Evaluation Report for the Surface and Subsurface Power System'' (CRWMS M&O 1999b, Section 7.6) and concurred with in the ''System Safety Evaluation of Title 111 Evaluation Reports Recommended Work'' (Gwyn 1999, Section 10.1.1). This analysis does not constitute a level-3 deliverable, a level-4 milestone, or a supporting work product. This document is not being prepared in support of the Monitored Geologic Repository (MGR) Site Recommendation (SR), Environmental Impact Statement (EIS), or License Application (LA) and should not be cited as a reference in the MGR SR, EIS, or LA.

  16. Modeling for Airborne Contamination

    SciTech Connect (OSTI)

    F.R. Faillace; Y. Yuan


    The objective of Modeling for Airborne Contamination (referred to from now on as ''this report'') is to provide a documented methodology, along with supporting information, for estimating the release, transport, and assessment of dose to workers from airborne radioactive contaminants within the Monitored Geologic Repository (MGR) subsurface during the pre-closure period. Specifically, this report provides engineers and scientists with methodologies for estimating how concentrations of contaminants might be distributed in the air and on the drift surfaces if released from waste packages inside the repository. This report also provides dose conversion factors for inhalation, air submersion, and ground exposure pathways used to derive doses to potentially exposed subsurface workers. The scope of this report is limited to radiological contaminants (particulate, volatile and gaseous) resulting from waste package leaks (if any) and surface contamination and their transport processes. Neutron activation of air, dust in the air and the rock walls of the drift during the preclosure time is not considered within the scope of this report. Any neutrons causing such activation are not themselves considered to be ''contaminants'' released from the waste package. This report: (1) Documents mathematical models and model parameters for evaluating airborne contaminant transport within the MGR subsurface; and (2) Provides tables of dose conversion factors for inhalation, air submersion, and ground exposure pathways for important radionuclides. The dose conversion factors for air submersion and ground exposure pathways are further limited to drift diameters of 7.62 m and 5.5 m, corresponding to the main and emplacement drifts, respectively. If the final repository design significantly deviates from these drift dimensions, the results in this report may require revision. The dose conversion factors are further derived by using concrete of sufficient thickness to simulate the drift walls. The gamma-ray scattering properties of concrete are sufficiently similar to those of the host rock and proposed insert material; use of concrete will have no significant impact on the conclusions. The information in this report is presented primarily for use in performing pre-closure radiological safety evaluations of radiological contaminants, but it may also be used to develop strategies for contaminant leak detection and monitoring in the MGR. Included in this report are the methods for determining the source terms and release fractions, and mathematical models and model parameters for contaminant transport and distribution within the repository. Various particle behavior mechanisms that affect the transport of contaminant are included. These particle behavior mechanisms include diffusion, settling, resuspension, agglomeration and other deposition mechanisms.


    SciTech Connect (OSTI)

    E.F. Loros


    The Carrier/Cask Handling System receives casks on railcars and legal-weight trucks (LWTs) (transporters) that transport loaded casks and empty overpacks to the Monitored Geologic Repository (MGR) from the Carrier/Cask Transport System. Casks that come to the MGR on heavy-haul trucks (HHTs) are transferred onto railcars before being brought into the Carrier/Cask Handling System. The system is the interfacing system between the railcars and LWTs and the Assembly Transfer System (ATS) and Canister Transfer System (CTS). The Carrier/Cask Handling System removes loaded casks from the cask transporters and transfers the casks to a transfer cart for either the ATS or CTS, as appropriate, based on cask contents. The Carrier/Cask Handling System receives the returned empty casks from the ATS and CTS and mounts the casks back onto the transporters for reshipment. If necessary, the Carrier/Cask Handling System can also mount loaded casks back onto the transporters and remove empty casks from the transporters. The Carrier/Cask Handling System receives overpacks from the ATS loaded with canisters that have been cut open and emptied and mounts the overpacks back onto the transporters for disposal. If necessary, the Carrier/Cask Handling System can also mount empty overpacks back onto the transporters and remove loaded overpacks from them. The Carrier/Cask Handling System is located within the Carrier Bay of the Waste Handling Building System. The system consists of cranes, hoists, manipulators, and supporting equipment. The Carrier/Cask Handling System is designed with the tooling and fixtures necessary for handling a variety of casks. The Carrier/Cask Handling System performance and reliability are sufficient to support the shipping and emplacement schedules for the MGR. The Carrier/Cask Handling System interfaces with the Carrier/Cask Transport System, ATS, and CTS as noted above. The Carrier/Cask Handling System interfaces with the Waste Handling Building System for building structures and space allocations. The Carrier/Cask Handling System interfaces with the Waste Handling Building Electrical System for electrical power.

  18. Experimental Test Plan for Grouting H-3 Calcine

    SciTech Connect (OSTI)

    Alan K. Herbst


    Approximately 4400 cubic meters of solid high-level waste called calcine are stored at the Idaho Nuclear Technology and Engineering Center. Under the Idaho Cleanup Project, dual disposal paths are being investigated. The first path includes calcine retrieval, package "as-is", and ship to the Monitored Geological Repository (MGR). The second path involves treatment of the calcine with such methods as vitrification or grouting. This test plan outlines the hot bench scale tests to grout actual calcine and verify that the waste form properties meet the waste acceptance criteria. This is a necessary sequential step in the process of qualifying a new waste form for repository acceptance. The archive H-3 calcine samples at the Contaminated Equipment Maintenance Building attached to New Waste Calcining Facility will be used in these tests at the Remote Analytical Laboratory. The tests are scheduled for the second quarter of fiscal year 2007.

  19. An experimental investigation of the effect of sodium chloride on talc solubility and complexing of aqueous magnesium in supercritical hydrothermal fluids

    E-Print Network [OSTI]

    Grabman, Kenneth Bryan


    5 0. 539 0. 0308 0. 0017 0. 0009 0. 0032 0. 0011 0. 0109 0. 0048 0. 0139 0. 0066 0. 0095 0. 0143 0. 0229 0. 0070 0. 0128 0. 0255 0. 00 1. 17 1. 26 1. 09 1. 98 2. 43 1. 99 3. 08 3. 22 0. 00 3. 78 3. 93 5. 34 4. 71 5. 98 6... NaCl at 500'C Figure 4. Plot of mMg species versus NaCI at 500'C Figure S. Plot of Mgr versus NaCI at 600'C Figure 6. Plot of log mMg, ?versus log ag, ct* at 600'C Figure 7. Plot of log mMg, ?versus log act- at 600'C Figure 8. Plot of mMg species...

  20. Significant Radionuclides Determination

    SciTech Connect (OSTI)

    Jo A. Ziegler


    The purpose of this calculation is to identify radionuclides that are significant to offsite doses from potential preclosure events for spent nuclear fuel (SNF) and high-level radioactive waste expected to be received at the potential Monitored Geologic Repository (MGR). In this calculation, high-level radioactive waste is included in references to DOE SNF. A previous document, ''DOE SNF DBE Offsite Dose Calculations'' (CRWMS M&O 1999b), calculated the source terms and offsite doses for Department of Energy (DOE) and Naval SNF for use in design basis event analyses. This calculation reproduces only DOE SNF work (i.e., no naval SNF work is included in this calculation) created in ''DOE SNF DBE Offsite Dose Calculations'' and expands the calculation to include DOE SNF expected to produce a high dose consequence (even though the quantity of the SNF is expected to be small) and SNF owned by commercial nuclear power producers. The calculation does not address any specific off-normal/DBE event scenarios for receiving, handling, or packaging of SNF. The results of this calculation are developed for comparative analysis to establish the important radionuclides and do not represent the final source terms to be used for license application. This calculation will be used as input to preclosure safety analyses and is performed in accordance with procedure AP-3.12Q, ''Calculations'', and is subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (DOE 2000) as determined by the activity evaluation contained in ''Technical Work Plan for: Preclosure Safety Analysis, TWP-MGR-SE-000010'' (CRWMS M&O 2000b) in accordance with procedure AP-2.21Q, ''Quality Determinations and Planning for Scientific, Engineering, and Regulatory Compliance Activities''.

  1. BWR Source Term Generation and Evaluation

    SciTech Connect (OSTI)

    J.C. Ryman


    This calculation is a revision of a previous calculation (Ref. 7.5) that bears the same title and has the document identifier BBAC00000-01717-0210-00006 REV 01. The purpose of this revision is to remove TBV (to-be-verified) -41 10 associated with the output files of the previous version (Ref. 7.30). The purpose of this and the previous calculation is to generate source terms for a representative boiling water reactor (BWR) spent nuclear fuel (SNF) assembly for the first one million years after the SNF is discharged from the reactors. This calculation includes an examination of several ways to represent BWR assemblies and operating conditions in SAS2H in order to quantify the effects these representations may have on source terms. These source terms provide information characterizing the neutron and gamma spectra in particles per second, the decay heat in watts, and radionuclide inventories in curies. Source terms are generated for a range of burnups and enrichments (see Table 2) that are representative of the waste stream and stainless steel (SS) clad assemblies. During this revision, it was determined that the burnups used for the computer runs of the previous revision were actually about 1.7% less than the stated, or nominal, burnups. See Section 6.6 for a discussion of how to account for this effect before using any source terms from this calculation. The source term due to the activation of corrosion products deposited on the surfaces of the assembly from the coolant is also calculated. The results of this calculation support many areas of the Monitored Geologic Repository (MGR), which include thermal evaluation, radiation dose determination, radiological safety analyses, surface and subsurface facility designs, and total system performance assessment. This includes MGR items classified as Quality Level 1, for example, the Uncanistered Spent Nuclear Fuel Disposal Container (Ref. 7.27, page 7). Therefore, this calculation is subject to the requirements of the Quality Assurance Requirements and Description (Ref. 7.28). The performance of the calculation and development of this document are carried out in accordance with AP-3.124, ''Design Calculation and Analyses'' (Ref. 7.29).


    SciTech Connect (OSTI)

    M. C. Knapp


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

  3. Evaluation of Blade-Strike Models for Estimating the Biological Performance of Kaplan Turbines

    SciTech Connect (OSTI)

    Deng, Zhiqun; Carlson, Thomas J.; Ploskey, Gene R.; Richmond, Marshall C.; Dauble, Dennis D.


    Bio-indexing of hydroturbines is an important means to optimize passage conditions for fish by identifying operations for existing and new design turbines that minimize the probability of injury. Cost-effective implementation of bio-indexing requires the use of tools such as numerical and physical turbine models to generate hypotheses for turbine operations that can be tested at prototype scales using live fish. Numerical deterministic and stochastic blade strike models were developed for a 1:25-scale physical turbine model built by the U.S. Army Corps of Engineers for the original design turbine at McNary Dam and for prototype-scale original design and replacement minimum gap runner (MGR) turbines at Bonneville Dam's first powerhouse. Blade strike probabilities predicted by both models were comparable with the overall trends in blade strike probability observed in both prototype-scale live fish survival studies and physical turbine model using neutrally buoyant beads. The predictions from the stochastic model were closer to the experimental data than the predictions from the deterministic model because the stochastic model included more realistic consideration of the aspect of fish approaching to the leading edges of turbine runner blades. Therefore, the stochastic model should be the preferred method for the prediction of blade strike and injury probability for juvenile salmon and steelhead using numerical blade-strike models.

  4. Lower-Temperature Subsurface Layout and Ventilation Concepts

    SciTech Connect (OSTI)

    Christine L. Linden; Edward G. Thomas


    This analysis combines work scope identified as subsurface facility (SSF) low temperature (LT) Facilities System and SSF LT Ventilation System in the Technical Work Plan for Subsurface Design Section FY 01 Work Activities (CRWMS M&O 2001b, pp. 6 and 7, and pp. 13 and 14). In accordance with this technical work plan (TWP), this analysis is performed using AP-3.10Q, Analyses and Models. It also incorporates the procedure AP-SI.1Q, Software Management. The purpose of this analysis is to develop an overall subsurface layout system and the overall ventilation system concepts that address a lower-temperature operating mode for the Monitored Geologic Repository (MGR). The objective of this analysis is to provide a technical design product that supports the lower-temperature operating mode concept for the revision of the system description documents and to provide a basis for the system description document design descriptions. The overall subsurface layout analysis develops and describes the overall subsurface layout, including performance confirmation facilities (also referred to as Test and Evaluation Facilities) for the Site Recommendation design. This analysis also incorporates current program directives for thermal management.

  5. Identification of Aircraft Hazards

    SciTech Connect (OSTI)

    K. Ashley


    Aircraft hazards were determined to be potentially applicable to a repository at Yucca Mountain in ''Monitored Geological Repository External Events Hazards Screening Analysis'' (BSC 2005 [DIRS 174235], Section 6.4.1). That determination was conservatively based upon limited knowledge of flight data in the area of concern and upon crash data for aircraft of the type flying near Yucca Mountain. The purpose of this report is to identify specific aircraft hazards that may be applicable to a monitored geologic repository (MGR) at Yucca Mountain, using NUREG-0800, ''Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants'' (NRC 1987 [DIRS 103124], Section, as guidance for the inclusion or exclusion of identified aircraft hazards. The intended use of this report is to provide inputs for further screening and analysis of identified aircraft hazards based upon the criteria that apply to Category 1 and Category 2 event sequence analyses as defined in 10 CFR 63.2 [DIRS 176544] (Section 4). The scope of this report includes the evaluation of military, private, and commercial use of airspace in the 100-mile regional setting of the repository at Yucca Mountain with the potential for reducing the regional setting to a more manageable size after consideration of applicable screening criteria (Section 7).

  6. Initial Cladding Condition

    SciTech Connect (OSTI)

    E. Siegmann


    The purpose of this analysis is to describe the condition of commercial Zircaloy clad fuel as it is received at the Yucca Mountain Project (YMP) site. Most commercial nuclear fuel is encased in Zircaloy cladding. This analysis is developed to describe cladding degradation from the expected failure modes. This includes reactor operation impacts including incipient failures, potential degradation after reactor operation during spent fuel storage in pool and dry storage and impacts due to transportation. Degradation modes include cladding creep, and delayed hydride cracking during dry storage and transportation. Mechanical stresses from fuel handling and transportation vibrations are also included. This Analysis and Model Report (AMR) does not address any potential damage to assemblies that might occur at the YMP surface facilities. Ranges and uncertainties have been defined. This analysis will be the initial boundary condition for the analysis of cladding degradation inside the repository. In accordance with AP-2.13Q, ''Technical Product Development Planning'', a work plan (CRWMS M&O 2000c) was developed, issued, and utilized in the preparation of this document. There are constraints, caveats and limitations to this analysis. This cladding degradation analysis is based on commercial Pressurized Water Reactor (PWR) fuel with Zircaloy cladding but is applicable to Boiling Water Reactor (BWR) fuel. Reactor operating experience for both PWRs and BWRs is used to establish fuel reliability from reactor operation. It is limited to fuel exposed to normal operation and anticipated operational occurrences (i.e. events which are anticipated to occur within a reactor lifetime), and not to fuel that has been exposed to severe accidents. Fuel burnup projections have been limited to the current commercial reactor licensing environment with restrictions on fuel enrichment, oxide coating thickness and rod plenum pressures. The information provided in this analysis will be used in evaluating the post-closure performance of the Monitored Geologic Repository (MGR) in relation to waste form degradation.


    SciTech Connect (OSTI)

    E.P. McCann


    The Site Electrical Power System receives and distributes utility power to all North Portal site users. The major North Portal users are the Protected Area including the subsurface facility and Balance of Plant areas. The system is remotely monitored and controlled from the Surface Operations Monitoring and Control System. The system monitors power quality and provides the capability to transfer between Off-Site Utility and standby power (including dedicated safeguards and security power). Standby power is only distributed to selected loads for personnel safety and essential operations. Security power is only distributed to essential security operations. The standby safeguards and security power is independent from all other site power. The system also provides surface lighting, grounding grid, and lightning protection for the North Portal. The system distributes power during construction, operation, caretaker, and closure phases of the repository. The system consists of substation equipment (disconnect switches, breakers, transformers and grounding equipment) and power distribution cabling from substation to the north portal switch gear building. Additionally, the system includes subsurface facility substation (located on surface), switch-gear, standby diesel generators, underground duct banks, power cables and conduits, switch-gear building and associated distribution equipment for power distribution. Each area substation distributes power to the electrical loads and includes the site grounding, site lighting and lightning protection equipment. The site electrical power system distributes power of sufficient quantity and quality to meet users demands. The Site Electrical Power System interfaces with the North Portal surface systems requiring electrical power. The system interfaces with the Subsurface Electrical Distribution System which will supply power to the underground facilities from the North Portal. Power required for the South Portal and development side activities of the subsurface facility will be provided at the South Portal by the Subsurface Electrical Distribution System. The Site Electrical Power System interfaces with the Off-Site Utility System for the receipt of power. The System interfaces with the Surface Operations Monitoring and Control System for monitoring and control. The System interfaces with MGR Site Layout System for the physical location of equipment and power distribution.

  8. Subsurface Contamination Control

    SciTech Connect (OSTI)

    Y. Yuan


    There are two objectives of this report, ''Subsurface Contamination Control''. The first is to provide a technical basis for recommending limiting radioactive contamination levels (LRCL) on the external surfaces of waste packages (WP) for acceptance into the subsurface repository. The second is to provide an evaluation of the magnitude of potential releases from a defective WP and the detectability of the released contents. The technical basis for deriving LRCL has been established in ''Retrieval Equipment and Strategy for Wp on Pallet'' (CRWMS M and O 2000g, 6.3.1). This report updates the derivation by incorporating the latest design information of the subsurface repository for site recommendation. The derived LRCL on the external surface of WPs, therefore, supercede that described in CRWMS M and O 2000g. The derived LRCL represent the average concentrations of contamination on the external surfaces of each WP that must not be exceeded before the WP is to be transported to the subsurface facility for emplacement. The evaluation of potential releases is necessary to control the potential contamination of the subsurface repository and to detect prematurely failed WPs. The detection of failed WPs is required in order to provide reasonable assurance that the integrity of each WP is intact prior to MGR closure. An emplaced WP may become breached due to manufacturing defects or improper weld combined with failure to detect the defect, by corrosion, or by mechanical penetration due to accidents or rockfall conditions. The breached WP may release its gaseous and volatile radionuclide content to the subsurface environment and result in contaminating the subsurface facility. The scope of this analysis is limited to radioactive contaminants resulting from breached WPs during the preclosure period of the subsurface repository. This report: (1) documents a method for deriving LRCL on the external surfaces of WP for acceptance into the subsurface repository; (2) provides a table of derived LRCL for nuclides of radiological importance; (3) Provides an as low as is reasonably achievable (ALARA) evaluation of the derived LRCL by comparing potential onsite and offsite doses to documented ALARA requirements; (4) Provides a method for estimating potential releases from a defective WP; (5) Provides an evaluation of potential radioactive releases from a defective WP that may become airborne and result in contamination of the subsurface facility; and (6) Provides a preliminary analysis of the detectability of a potential WP leak to support the design of an airborne release monitoring system.


    SciTech Connect (OSTI)

    W.D. Lindholm


    The purpose of this analysis is to identify and evaluate the functional space and spatial relationship requirements for the two main nuclear buildings, the Waste Handling Building (WHB) and the Waste Treatment Building (WTB), which are part of the Repository Surface Facilities. This analysis is consistent with the Development Plan for ''WHB/WTB Space Program Analysis for Site Recommendation'' (CRWMS M&O 2000r), which concentrates on the primary, primary support, facility support, and miscellaneous building support areas located in the WHB and WTB. The development plan was completed in accordance with AP-2.134, ''Technical Product Development Planning''. The objective and scope of this analysis is to develop a set of spatial parameters (e.g., square footage, room heights, etc.) and layout requirements (e.g., adjacency and access/circulation requirements, etc.) from which preliminary building floor plans are developed and presented as figures. The resulting figures will provide information to support the Site Recommendation and the total system life cycle cost. This analysis uses the Viability Assessment (VA) ''Surface Nuclear Facilities Space Program Analysis'' (SPA) (CRWMS M&O 1997c) as the baseline reference document and further develops the functional requirements based on Project-directed changes, including incorporation of a new design basis waste stream and the applicable elements of Enhanced Design Alternative (EDA)-II, as identified in the ''License Application Design Selection Report'' (CRWMS M&O 1999e), which followed the initial SPA (baseline). The impacts of the EDA-II were almost entirely to the WHB. To meet the EDA-II thermal requirements, hotter fuel would be handled, therefore requiring a fuel-blending pool to be added to the WHB in order to age the hotter he1 at the repository and provide for commercial spent nuclear fuel (CSNF) blending. In addition to EDA-II recommendations, the waste stream was modified, including the elimination of approximately 300 multi-purpose canisters from the CSNF schedule. The bases for the Monitored Geologic Repository (MGR) surface design changes, as a result of the waste stream changes, are defined in ''Calculations from Surface Facilities Operations in Support of the Revision to the Waste Quantity, Mix, and Throughput Study'' (CRWMS M&O 2000c, Section 2.4). This effort resulted in a reduction in the number of canister transfer lines from 2 to 1. In addition, as indicated in ''WITNESS Model Input for Thermal Blending of Commercial Spent Nuclear Fuel Assemblies'' (CRWMS M&O 19991), the quantity of dual-purpose canisters (DPCs) assumed to be shipped to the repository has been reduced by about 37 percent. This change resulted in a reduction of the number of Assembly Transfer System (ATS) lines in the WHB from 3 to 2. In summary, this analysis is intended to provide a preliminary level of design showing room square footages and heights associated with the WHB and WTB. These spatial dimensions are anticipated to increase or decrease as the design progresses.

  10. DOE Hydropower Program Biennial Report for FY 2005-2006

    SciTech Connect (OSTI)

    Sale, Michael J [ORNL; Cada, Glenn F [ORNL; Acker, Thomas L. [Northern Arizona State University and National Renewable Energy Laboratory; Carlson, Thomas [Pacific Northwest National Laboratory (PNNL); Dauble, Dennis D. [Pacific Northwest National Laboratory (PNNL); Hall, Douglas G. [Idaho National Laboratory (INL)


    SUMMARY The U.S. Department of Energy (DOE) Hydropower Program is part of the Office of Wind and Hydropower Technologies, Office of Energy Efficiency and Renewable Energy. The Program's mission is to conduct research and development (R&D) that will increase the technical, societal, and environmental benefits of hydropower. The Department's Hydropower Program activities are conducted by its national laboratories: Idaho National Laboratory (INL) [formerly Idaho National Engineering and Environmental Laboratory], Oak Ridge National Laboratory (ORNL), Pacific Northwest National Laboratory (PNNL), and National Renewable Energy Laboratory (NREL), and by a number of industry, university, and federal research facilities. Programmatically, DOE Hydropower Program R&D activities are conducted in two areas: Technology Viability and Technology Application. The Technology Viability area has two components: (1) Advanced Hydropower Technology (Large Turbine Field Testing, Water Use Optimization, and Improved Mitigation Practices) and (2) Supporting Research and Testing (Environmental Performance Testing Methods, Computational and Physical Modeling, Instrumentation and Controls, and Environmental Analysis). The Technology Application area also has two components: (1) Systems Integration and Technology Acceptance (Hydro/Wind Integration, National Hydropower Collaborative, and Integration and Communications) and (2) Supporting Engineering and Analysis (Valuation Methods and Assessments and Characterization of Innovative Technology). This report describes the progress of the R&D conducted in FY 2005-2006 under all four program areas. Major accomplishments include the following: Conducted field testing of a Retrofit Aeration System to increase the dissolved oxygen content of water discharged from the turbines of the Osage Project in Missouri. Contributed to the installation and field testing of an advanced, minimum gap runner turbine at the Wanapum Dam project in Washington. Completed a state-of-the-science review of hydropower optimization methods and published reports on alternative operating strategies and opportunities for spill reduction. Carried out feasibility studies of new environmental performance measurements of the new MGR turbine at Wanapum Dam, including measurement of behavioral responses, biomarkers, bioindex testing, and the use of dyes to assess external injuries. Evaluated the benefits of mitigation measures for instream flow releases and the value of surface flow outlets for downstream fish passage. Refined turbulence flow measurement techniques, the computational modeling of unsteady flows, and models of blade strike of fish. Published numerous technical reports, proceedings papers, and peer-reviewed literature, most of which are available on the DOE Hydropower website. Further developed and tested the sensor fish measuring device at hydropower plants in the Columbia River. Data from the sensor fish are coupled with a computational model to yield a more detailed assessment of hydraulic environments in and around dams. Published reports related to the Virtual Hydropower Prospector and the assessment of water energy resources in the U.S. for low head/low power hydroelectric plants. Convened a workshop to consider the environmental and technical issues associated with new hydrokinetic and wave energy technologies. Laboratory and DOE staff participated in numerous workshops, conferences, coordination meetings, planning meetings, implementation meetings, and reviews to transfer the results of DOE-sponsored research to end-users.