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Sample records for water reactors casl

  1. Consortium for Advanced Simulation of Light Water Reactors (CASL)

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

    Media Kit CASL Acknowledgement This research was supported by the Consortium for Advanced Simulation of Light Water Reactors (http://www.casl.gov), an Energy Innovation Hub (http://www.energy.gov/hubs) for Modeling and Simulation of Nuclear Reactors under U.S. Department of Energy Contract No. DE-AC05-00OR22725. CASL Logo Files CASL Extended - CASL_word.jpg and CASL_word.png CASL without words - CASL.jpg and CASL.png CASL with words - CASL_word.jpg and CASL_word.png CASL Partners - partners.jpg

  2. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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    J.C., CASL: Consortium for the Advanced Simulation of Light Water Reactors - A DOE Energy Innovation Hub, ANS MC2015 Joint Internation Conference on Mathematics and Computation...

  3. Consortium for Advanced Simulation of Light Water Reactors (CASL)

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    Webinars Introduction to CASL Youtube snapshot Consortium for Advanced Simulation of Light Water Reactors Youtube snapshot CASL Dedication Youtube snapshot Energy Secretary Chu visits ORNL Youtube snapshot CASL's VERA: What is Possible? Youtube snapshot Andrew Godfrey - Nuclear Energy Technical Webcasts - VERA Methods Youtube snapshot Subchannel methods for the Thermal-Hydraulic Analysis of Nuclear Power Systems Youtube snapshot Surrogate Models for Uncertainty Quantification presented by Dr.

  4. Consortium for Advanced Simulation of Light Water Reactors (CASL)

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    Science and Technology Archive Energy Department Announces Five Year Renewal of Funding for First Energy Innovation Hub Consortium for Advanced Simulation of Light Water Reactors to Receive up to $121.5 Million Over Five Years. Posted: January 29, 2015 VERA-CS Coupled Multi-physics Capability demonstrated in a Full Core Simulation In December, CASL reported on the latest results from its Watts Bar reactor progression problem modeling. Posted: August 14, 2014 Westinghouse Completes its AP1000®

  5. Consortium for Advanced Simulation of Light Water Reactors (CASL)

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    Light Water Reactors (CASL) - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Energy Defense Waste Management Programs Advanced

  6. CASL: The Consortium for Advanced Simulation of Light Water Reactors A DOE Energy Innovation Hub for Modeling and Simulation of Nuclear Reactors

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    AMA.NRC.P5.01 CASL NRC Commissioner Technical Seminar Jess Gehin Oak Ridge National Laboratory December 22, 2012 CASL-U-2014-0076-000-a CASL-U-2012-0076-000-a 1 CASL: The Consortium for Advanced Simulation of Light Water Reactors A DOE Energy Innovation Hub for Modeling and Simulation of Nuclear Reactors NRC Commissioner Technical Seminar November 30, 2012 Doug Kothe (ORNL) CASL Director Doug Burns (INL) CASL Deputy Director Paul Turinsky (NCSU) CASL Chief Scientist Jess Gehin (ORNL) CASL AMA FA

  7. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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    on issues related to management, performance, strategic direction, and institutional interfaces within CASL. The CASL Director reports to the BOD on all matters related to CASL...

  8. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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    ORNL Laboratory Director and the CASL Senior Leadership Team (SLT) on issues related to management, performance, strategic direction, and institutional interfaces within CASL....

  9. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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    in Drekar, CASL Technical Report: CASL-U-2012-0080-000, June 30, 2012. Bakosi, J., N. Barnett, M.A. Christon, M.M. Francois, R.B. Lowrie and R. Sankaran, Integration of Hydra-TH...

  10. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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    plant power uprates, life extension, and higher burnup fuels Provide the primary bridge between the scientific and computational capabilities developed by CASL and external...

  11. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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    modeling and simulation technology that is deployed and applied broadly throughout the nuclear energy industry to enhance safety, reliability, and economics. CASL will address,...

  12. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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    of technology. Management Performance reflects CASL's ability to meet its virtual one-roof plan (collocation), maintain consortium cohesion and chemistry, and deliver its...

  13. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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    CASL Partners Electric Power Research Institute Idaho National Laboratory Los Alamos National Laboratory Massachusetts Institute of Technology North Carolina State University Oak...

  14. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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    issues. The Science Council advises the following CASL Focus Areas (FAs): Radiation Transport Methods (RTM), Thermal Hydraulics Methods (THM), Materials Performance and...

  15. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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    from CASL (Dr. Mike Short, MIT, October, 31, 2013) Subchannel Methods for the Thermal-Hydraulic Analysis for Nuclear Power Systems (Dr. Michael Doster, NCSU, May 28, 2013)...

  16. Consortium for Advanced Simulation of Light Water Reactors (CASL)

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    Technical Reports 2016 back to top Palmtag, S.MPACT Library Verification by Comparison of Assembly Calculations to Monte Carlo Results, CASL-U-2016-1052-000, March 31, 2016. Khuwaileh, B.A., Turinsky, P.J., Data Assimilation and Uncertainty Quantification Using VERA-CS for a Core Wide LWR Problem with Depletion, CASL Technical Report: CASL-U-2016-1054-000, March 23, 2016. Palmtag, S.Investigation of Thermal Expansion Effects in MPACT, CASL-U-2016-1015-000, February 28, 2016. Palmtag, S.MPACT

  17. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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    Site Map Home About CASL Vision Mission Goals Strategy Integration Performance Metrics Partners Founding Partners Electric Power Research Institute Idaho National Laboratory Los...

  18. CONSORTIUM FOR ADVANCED SIMULATION OF LIGHT WATER REACTORS (CASL) Meeting Notes … September 9, 2010

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    September 11 - 12, 2012 - Oak Ridge, TN Minutes The fifth meeting of the Industry Council (IC) for the Consortium for Advanced Simulation of Light Water Reactors (CASL) was held on September 11 and 12, 2012; at Oak Ridge National Laboratory in Oak Ridge, TN. The first day was a joint meeting of the CASL Science Council and the Industry Council and was co-facilitated by Paul Turinsky of NCSU and John Gaertner of EPRI. The Industry Council met separately on the second day which was chaired by John

  19. Consortium for Advanced Simulation of Light Water Reactors (CASL)

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    Site Map Home CASL Partners Research Science & Technology Archive Journal & Conference Papers Technical Reports Presentations VERA Software & Support VERA 3.3 VERA.edu How To Request VERA Support & Resources Tutorials & Webcasts Upcoming Training Events Tutorials Webinars About CASL Image Gallery Video Gallery Media Kit Organization Board of Directors Industry Council Science Council Contact Us

  20. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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    Engineering and Design, Volume Online, Issue CASL-U-2015-0301-000, August 28, 2015. Smith, T.M., M.A. Christon, E. Baglietto and H. Luo, "Assessment of Models for Near Wall...

  1. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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    capabilities to meet future CASL needs. DTK has been given an open source BSD 3-clause license. The primary code development repository is publicly-hosted under the GitHub group...

  2. Consortium for Advanced Simulation of Light Water Reactors (CASL)

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    Back Industry Council Chairperson: Scott Thomas, Duke Energy Executive Director: Erik Mader, EPRI Mission and Objectives The mission of the Industry Council (IC) is to ensure that CASL solutions are "used and useful", and that CASL provides effective leadership advancing the Modeling and Simulation state-of-the art in the nuclear industry. Specific objectives of the Industry Council are: Early, continuous, and frequent interface and engagement of end-users and technology providers

  3. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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    Virtual Environment for Scientific Collaboration Posted: April 30, 2013 The Consortium for Advanced Simulation of Light Water Reactors, the Department of Energy's first...

  4. CONSORTIUM FOR ADVANCED SIMULATION OF LIGHT WATER REACTORS (CASL) Meeting Notes … September 9, 2010

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    Meetings January 11, 2011 - Oak Ridge, TN February 8, 2011 - Charlotte, NC Minutes The second meeting of the Industry Council (IC) for the Consortium for Advanced Simulation of Light Water Reactors (CASL) was held in two parts on January 11, 2011 at Oak Ridge National Laboratories (ORNL), Oak Ridge, TN; and on February 8, 2011, at the facilities of the Electric Power Research Institute (EPRI) in Charlotte, NC. Both meetings were chaired by John Gaertner of EPRI. Two meetings were necessary

  5. CONSORTIUM FOR ADVANCED SIMULATION OF LIGHT WATER REACTORS (CASL) Meeting Notes … September 9, 2010

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

    August 23 - 24, 2011 - Oak Ridge, TN Minutes The third meeting of the Industry Council (IC) for the Consortium for Advanced Simulation of Light Water Reactors (CASL) was held on August 23 until noon on August 24, 2011, at Oak Ridge National Laboratories (ORNL), Oak Ridge, Tennessee. The meeting was chaired by John Gaertner of EPRI. The agenda, meeting attendees, and IC member organizations are included in Attachment 1 to these minutes. Attendance was by invitation only. Fifteen representatives

  6. CONSORTIUM FOR ADVANCED SIMULATION OF LIGHT WATER REACTORS (CASL) Meeting Notes … September 9, 2010

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

    Meeting September 9, 2010 Minutes The first meeting of the Industry Council (IC) for the Consortium for Advanced Simulation of Light Water Reactors (CASL) was held on September 9, 2010, at the facilities of the Electric Power Research Institute (EPRI) in Charlotte, NC. The meeting was chaired by John Gaertner of EPRI. The meeting attendees and their affiliations are listed on Attachment 1 to these minutes. Attendance was by invitation only. Representatives from 16 organizations were invited. All

  7. Consortium for Advanced Simulation of Light Water Reactors (CASL)

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    CASL's Latest Research CIPS Simulation Capability Implemented in VERA Posted on October 28, 2015 Departure from Nucleate Boiling (DNB) Multi-Physics Approach & Applications using VERA Posted on October 28, 2015 Illustration of VERA Capability to Model a Typical SMR Posted on October 28, 2015 ITM/DNS for High Volume Fraction Bubbly Flow Regimes: Simulations for Closure Development Posted on October 28, 2015 Verification and Validation Supporting VERA Neutronics Code Posted on October 28, 2015

  8. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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    reactor physical phenomena using coupled multiphysics models. VERA also includes the software development environment and computational infrastructure needed for these...

  9. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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    to achieve challenge problem solutions A strong VERA infrastructure supporting software development, testing, and releases. Requirements Drivers Modeling of reactors...

  10. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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    LWRs; Develop and effectively apply modern virtual reactor technology; Engage the nuclear energy community through modeling and simulation; and Deploy new partnership and...

  11. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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    Radiation Transport Methods (RTM) Delivers next-generation radiation transport tools to the virtual Reactor RTM Vision Statement Objectives and Strategies Next generation,...

  12. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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    Thermal Hydraulics Methods (THM) Delivers next-generation thermal-hydraulic simulation tools to Virtual Environment for Reactor Applications (VERA) Thermal Hydraulics Methods...

  13. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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    Read More Fuel pellets and the fuel rod cladding are affected at the microstructural level Under pressure, heat and radiation in the reactor environment, both the fuel pellets and ...

  14. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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    Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, ... leveraging previous taxpayer investments in M&S tools that run on the world's ...

  15. ORNL). Consortium for Advanced Simulation of Light Water Reactors

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    Simulation of Light Water Reactors (CASL) was established by the US Department of Energy in 2010 to advance modeling and simulation capabilities for nuclear reactors. CASL's...

  16. CASL-U-2015-0248-000 Modeling Boiling Water Reactor

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    8-000 Modeling Boiling Water Reactor Designs using MPACT Andrew P. Fitzgerald Brendan ... lattices from the Peach Bottom Unit 2 Reactor Cycles 1 and 2. ATRIUM TM 10 simulations ...

  17. COLLOQUIUM: CASL: Consortium for Advanced Simulation of Light Water

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    Reactors, a DOE Energy Innovation Hub | Princeton Plasma Physics Lab May 29, 2013, 4:15pm to 5:30pm Colloquia MBG Auditorium COLLOQUIUM: CASL: Consortium for Advanced Simulation of Light Water Reactors, a DOE Energy Innovation Hub Dr. Douglas Kothe Oak Ridge National Laboratory The Consortium for Advanced Simulation of Light Water Reactors (CASL) is the first U.S. Department of Energy (DOE) Energy Innovation Hub, established in July 2010 for the modeling and simulation (M&S) of nuclear

  18. Some Specific CASL Requirements for Advanced Multiphase Flow Simulation of Light Water Reactors

    SciTech Connect (OSTI)

    R. A. Berry

    2010-11-01

    Because of the diversity of physical phenomena occuring in boiling, flashing, and bubble collapse, and of the length and time scales of LWR systems, it is imperative that the models have the following features: • Both vapor and liquid phases (and noncondensible phases, if present) must be treated as compressible. • Models must be mathematically and numerically well-posed. • The models methodology must be multi-scale. A fundamental derivation of the multiphase governing equation system, that should be used as a basis for advanced multiphase modeling in LWR coolant systems, is given in the Appendix using the ensemble averaging method. The remainder of this work focuses specifically on the compressible, well-posed, and multi-scale requirements of advanced simulation methods for these LWR coolant systems, because without these are the most fundamental aspects, without which widespread advancement cannot be claimed. Because of the expense of developing multiple special-purpose codes and the inherent inability to couple information from the multiple, separate length- and time-scales, efforts within CASL should be focused toward development of a multi-scale approaches to solve those multiphase flow problems relevant to LWR design and safety analysis. Efforts should be aimed at developing well-designed unified physical/mathematical and high-resolution numerical models for compressible, all-speed multiphase flows spanning: (1) Well-posed general mixture level (true multiphase) models for fast transient situations and safety analysis, (2) DNS (Direct Numerical Simulation)-like models to resolve interface level phenmena like flashing and boiling flows, and critical heat flux determination (necessarily including conjugate heat transfer), and (3) Multi-scale methods to resolve both (1) and (2) automatically, depending upon specified mesh resolution, and to couple different flow models (single-phase, multiphase with several velocities and pressures, multiphase with single

  19. CASL-U-2015-0278-000 CASL Program Highlights

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    78-000 CASL Program Highlights July 2015 Jess Gehin Oak Ridge National Laboratory July 31, 2015 CASL-U-2015-0278-000 1 Demonstrate on new VERA Boiling Water Reactor (BWR) ...

  20. CASL Photo Book

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    CASL Photo Book August 7, 2014 CASL-U-2014-0177-000 CASL-U-2014-0177-000 Predictive science-based simulation technology that harnesses world-class computational power to enhance clean energy production CASL-U-2014-0177-000 Cover photo: 3D visualizations allow a physical walk-through of the top 20% of high-powered rods in a pressurized water reactor core. Details revealed through such visualizations can provide insight into factors affecting core performance. CASL team members often review and

  1. CASL - CASL and TVA

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    CASL and TVA The Tennessee Valley Authority (TVA) provides operational experience and validation information to CASL. Many of the CASL staff are highly skilled in their nuclear energy-relevant area of expertise, but not necessarily operational experience typified by the day-to-day issues encountered in commercial reactors. For example, the physical process of removing the fuel from the core, inspecting it, and then repacking it for the next cycle, which for TVA is planned for months in advance

  2. CASL Industry Council Meeting

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    Meeting 12-13 April 2016 Meeting Minutes Page | 1 The spring 2016 meeting of the Industry Council (IC) for the Consortium for Advanced Simulation of Light Water Reactors (CASL) was held on April 12-13, 2016 at the Aloft Hotel in Greenville, South Carolina and was led by the CASL IC Chairman Scott Thomas of Duke Energy and the new CASL IC Executive Director Erik Mader from the EPRI Fuel Reliability Program. The meeting location and logistics were excellent and the group profusely thanked Lorie

  3. CASL - Image Gallery

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    Image Gallery All Works CASL Modeling Applications Multi-Physics Neutronics Thermal Hydraulics Fuel Performance Corrosion Chemistry Secretary Moniz tours the Consortium... Secretary Moniz tours the Consortium for Advanced Simulation of Light Water Reactors (CASL) View The all-quartz test section design allows... The all-quartz test section design allows for simultaneous measurement of the temperature and phase distribution on the boiling surface, as well as measurement of the velocity field in

  4. CASL-U-2015-0249-000 Rod Cusping

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    Rod Cusping Treatment in MPACT CASL is currently developing a new core simulator called MPACT to solve neutron transport problems for light- water nuclear reactors....

  5. Thermal hydraulics development for CASL

    SciTech Connect (OSTI)

    Lowrie, Robert B

    2010-12-07

    This talk will describe the technical direction of the Thermal-Hydraulics (T-H) Project within the Consortium for Advanced Simulation of Light Water Reactors (CASL) Department of Energy Innovation Hub. CASL is focused on developing a 'virtual reactor', that will simulate the physical processes that occur within a light-water reactor. These simulations will address several challenge problems, defined by laboratory, university, and industrial partners that make up CASL. CASL's T-H efforts are encompassed in two sub-projects: (1) Computational Fluid Dynamics (CFD), (2) Interface Treatment Methods (ITM). The CFD subproject will develop non-proprietary, scalable, verified and validated macroscale CFD simulation tools. These tools typically require closures for their turbulence and boiling models, which will be provided by the ITM sub-project, via experiments and microscale (such as DNS) simulation results. The near-term milestones and longer term plans of these two sub-projects will be discussed.

  6. CASL - Industry Council and CASL Project are Engaged to Investigate

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    Workflow Processes to Ensure Value and Usability of CASL Results Industry Council and CASL Project are Engaged to Investigate Workflow Processes to Ensure Value and Usability of CASL Results John Gaertner, Chairman, CASL Industry Council January 3, 2012 Background The CASL Workflow Project is a joint activity between members of the CASL Industry Council (IC) and the Advanced Modeling Applications (AMA) and Virtual Reactor Integration (VRI) focus areas. The project originated at a Fall 2011

  7. CASL Industry Council Meeting

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    6 CASL Industry Council Meeting March 26-27, 2013 - Cranberry Township, PA Minutes The sixth meeting of the Industry Council (IC) for the Consortium for Advanced Simulation of Light Water Reactors (CASL) was held on March 26-27, 2013 at Westinghouse in Cranberry Township, PA. The first day of the Industry Council was chaired by John Gaertner and the second day was chaired by Heather Feldman. The meeting attendees and their affiliations are listed on Attachment 1 to these minutes. Attendance was

  8. CASL Industry Council Meeting

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    Industry Council Meeting 4 - 5 November 2015 Meeting Minutes The autumn 2015 meeting of the Industry Council (IC) for the Consortium for Advanced Simulation of Light Water Reactors (CASL) was held on 4 - 5 November 2015 at the Oak Ridge National Laboratory (ORNL) in Oak Ridge, TN. The first day of meeting was a joint meeting of the CASL Industry and Science Councils and was held at the Spallation Neutron Source (SNS) facility at ORNL. An independent IC meeting was held the morning of the second

  9. L3:EC.P9.05 CASL Summer Workshop

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    EC.P9.05 CASL Summer Workshop Report 2014 Leigh Winfrey Virginia Polytechnic Institute and State University August 28, 2014 CASL-8-2014-0166-000 CASL-U-2014-0166-000 CASL Education Council Summer Student Workshop 2014 June 11-13, 2014 Oak Ridge National Laboratory CASL (The Consortium for Advanced Simulation of Light Water Reactors) - A DOE Energy Innovation Hub for Modeling & Simulation of Nuclear Reactors Education Program hosted their fourth annual Summer Student Workshop in the summer of

  10. CASL-U-2015-0040-000 Initial Boiling Water

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    40-000 Initial Boiling Water Reactor (BWR) Input Specifications Scott Palmtag Core Physics February 28, 2015 Initial Boiling Water Reactor (BWR) Input Specification Consortium for ...

  11. Light Water Reactors A DOE Energy Innovation Hub for Modeling...

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    and Simulation of Nuclear Reactors CASL is focused on three issues for nuclear energy: reducing cost, reducing the amount of used nuclear fuel, and safety. CASL core...

  12. CASL Plan of Record 2 (1/11-6/11)

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    ... AMA Advanced Modeling Applications ARO All rods out BOC Beginning of Cycle B&W Babcock & Wilcox CASL Consortium for Advanced Simulation of Light Water Reactors DeCART ...

  13. CASL: Renewal Application Process

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    Update Jess Gehin (ORNL), Director Doug Burns (INL), Deputy Director Dave Kropaczek (NCSU), Chief Scientist CASL Industry Council Meeting Greeneville, South Carolina April 13, 2016 CASL-U-2016-1081-000 2 CASL's Mission is to Provide Leading- Edge M&S Capabilities to Improve the Performance of Operating LWRs VISION Predict, with confidence, the performance and assured safety of nuclear reactors, through comprehensive, science-based M&S technology deployed and applied broadly by the U.S.

  14. CASL - CASL's presence at Nureth-14

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    CASL's presence at Nureth-14 CASL Thermal Hydraulics team had a considerable presence at the 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics that took place in Toronto from Sept. 25-30, 2011. The NURETH series of conferences is an outstanding international technical forum on different topics related to thermalhydraulics and nuclear reactor safety with participation from leading practitioners and academic and industry researchers from around the world. NURETH-14 was

  15. CASL - Public Release of CASL Infrastructure Software

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    Public Release of CASL Infrastructure Software The Virtual Environment for Reactor Applications (VERA) comprises a suite of tools for scalable simulation of nuclear reactor core behavior. The following three key components of the VERA infrastructure have been released and made publicly-available: Data TransferKit Data TransferKit (DTK) is a software package designed to provide grid transfer services to the various CASL physics components. The Data Transfer Kit has been redesigned to provide a

  16. CASL-U-2015-0073-000

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    73-000 The Consortium for Advanced Simulation of Light Water Reactors - A DOE Energy Innovation Hub Technical Society Meeting of Knoxville Jess C. Gehin Oak Ridge National Laboratory March 3, 2014 CASL-U-2015-0073-000 The Consortium for Advanced Simulation of Light Water Reactors A DOE Energy Innovation Hub Jess C. Gehin Oak Ridge National Laboratory Technical Society Meeting of Knoxville March 3, 2014 CASL-U-2015-0073-000 2 2 * A Different Approach - Multi-disciplinary, highly collaborative

  17. CASL - Validation of Peregrine with Test Reactor Data

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    Validation of Peregrine with Test Reactor Data At the end of September, Pellet-Cladding Interaction (PCI) Challenge Problem Integrator Robert Montgomery reported that good progress has been made in demonstrating the Peregrine LWR fuel performance modeling software. The Peregrine fuel performance analysis computer program is being developed to provide a single rod 3-dimensional fuel performance modeling capability to assess safety margins and the impact of plant operation and fuel rod design on

  18. CASL - PWR Reactor Vessel Multi-Physics CFD Model

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    PWR Reactor Vessel Multi-Physics CFD Model Jin Yan*1, Yiban Xu1, Andrew Petrarca1, Zeses Karoutas1, Emre Tatli1, Emilio Baglietto2, Jess Gehin3 1Westinghouse Electric Company LLC 2Massachusetts Institute of Technology 3Oak Ridge National Lab *Correspondence to: yan3j@westinghouse.com A complete 3D SolidWorks CAD model of Watts Bar Unit 1 was constructed based on drawings. A single fuel assembly CAD model including all geometrical details was created based on the Westinghouse V5H 17x17 fuel

  19. User guidelines and best practices for CASL VUQ analysis using Dakota.

    SciTech Connect (OSTI)

    Adams, Brian M.; Swiler, Laura Painton; Hooper, Russell; Lewis, Allison; McMahan, Jerry A.,; Smith, Ralph C.; Williams, Brian J.

    2014-03-01

    Sandia's Dakota software (available at http://dakota.sandia.gov) supports science and engineering transformation through advanced exploration of simulations. Specifically it manages and analyzes ensembles of simulations to provide broader and deeper perspective for analysts and decision makers. This enables them to enhance understanding of risk, improve products, and assess simulation credibility. This manual offers Consortium for Advanced Simulation of Light Water Reactors (LWRs) (CASL) partners a guide to conducting Dakota-based VUQ studies for CASL problems. It motivates various classes of Dakota methods and includes examples of their use on representative application problems. On reading, a CASL analyst should understand why and how to apply Dakota to a simulation problem. This SAND report constitutes the product of CASL milestone L3:VUQ.V&V.P8.01 and is also being released as a CASL unlimited release report with number CASL-U-2014-0038-000.

  20. CASL Plan of Record 2 (1/11-6/11)

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    CASL-U-2013-0105-000 Operational Reactor Model Demonstration with VERA: Watts Bar Unit 1 ... Operational Reactor Model Demonstration with VERA CASL-U-2013-0105-001 i ...

  1. CASL - Nuclear Energy - Supercomputer speeds path forward

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    Nuclear Energy - Supercomputer speeds path forward When run on graphics processing units, Denovo ran 3.5 times faster than what was possible with ORNL's Jaguar, which uses only central processing units. With this increase, 3D simulations are now within reach, said Tom Evans, who led the Denovo development team. Titan is a GPU/CPU hybrid to be installed over the next several months. This research supports the Consortium for Advanced Simulation of Light Water Reactors (http://www.casl.gov/).

  2. CASL Milestone L2.VRI.P6.01

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

    L2 Milestone VRI.P7.01 - VERA 3.1 Protected under CASL Master NDA Official Use Only CASL-U-2013-0164-000 i Consortium for Advanced Simulation of LWRs Fe Milestone L2:VRI.P7.01 Virtual Environment for Reactor Applications (VERA): Snapshot 3.1 07/24/2013 John A. Turner CASL-U-2013-0164-000 CASL L2 Milestone VRI.P7.01 - VERA 3.1 CASL-U-2013-0164-000 ii Consortium for Advanced Simulation of LWRs Oak Ridge National Laboratory in partnership with Electric Power Research Institute Idaho National

  3. The Consortium for Advanced Simulation of Light Water Reactors

    SciTech Connect (OSTI)

    Ronaldo Szilard; Hongbin Zhang; Doug Kothe; Paul Turinsky

    2011-10-01

    The Consortium for Advanced Simulation of Light Water Reactors (CASL) is a DOE Energy Innovation Hub for modeling and simulation of nuclear reactors. It brings together an exceptionally capable team from national labs, industry and academia that will apply existing modeling and simulation capabilities and develop advanced capabilities to create a usable environment for predictive simulation of light water reactors (LWRs). This environment, designated as the Virtual Environment for Reactor Applications (VERA), will incorporate science-based models, state-of-the-art numerical methods, modern computational science and engineering practices, and uncertainty quantification (UQ) and validation against data from operating pressurized water reactors (PWRs). It will couple state-of-the-art fuel performance, neutronics, thermal-hydraulics (T-H), and structural models with existing tools for systems and safety analysis and will be designed for implementation on both today's leadership-class computers and the advanced architecture platforms now under development by the DOE. CASL focuses on a set of challenge problems such as CRUD induced power shift and localized corrosion, grid-to-rod fretting fuel failures, pellet clad interaction, fuel assembly distortion, etc. that encompass the key phenomena limiting the performance of PWRs. It is expected that much of the capability developed will be applicable to other types of reactors. CASL's mission is to develop and apply modeling and simulation capabilities to address three critical areas of performance for nuclear power plants: (1) reduce capital and operating costs per unit energy by enabling power uprates and plant lifetime extension, (2) reduce nuclear waste volume generated by enabling higher fuel burnup, and (3) enhance nuclear safety by enabling high-fidelity predictive capability for component performance.

  4. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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

    well-known thermal-hydraulic analysis codes that have found widespread use in the nuclear energy industry. This group of codes is related in that they were developed for modeling...

  5. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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

    to develop the world's first nuclear fuel cycle and today is DOE's largest science and energy laboratory. ORNL has world-leading capabilities in computing and computational...

  6. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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

    plan to set up eight innovation hubs to solve the eight biggest energy problems in the world. CUNY Energy Institute The CUNY Energy Institute is proudly training the next...

  7. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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

    codes (e.g,. a physics simulation) and iterative systems analysis methods such as optimization or uncertainty quantification. It includes algorithms for: optimization with...

  8. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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

    models are being developed based on higher fidelity CFD methods, and may also include adhesionstrength models16 for the crud's surface layer as well as other "release"...

  9. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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

    of plant operation and fuel rod design on the thermo-mechanical behavior, including Pellet-Cladding Interaction (PCI) failures in PWRs. The multi-physics, multi-dimensional...

  10. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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

    to deliver materials insight in the areas of CRUD, Grid-to-Rod-Fretting (GTRF), pellet-cladding interaction (PCI), reactivity insertion accident (RIA) and loss of cooling...

  11. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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

    model and numerical algorithm requirements of VERA. THM collaborates closely with Materials Performance and Optimization (MPO) for sub-grid material and chemistry models,...

  12. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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

    integration (VRI) for integration and development of VERA. Materials Performance and Optimization (MPO) - Develops improved materials performance models for fuels, cladding,...

  13. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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

    and Monte Carlo transport applications. Exnihilo is based on a package architecture model such that each package provides well-defined capabilities. Exnihilo currently...

  14. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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

    that have included management of CERCLA and RCRA remediation projects at the INL, Rocky Flats, and Mound laboratories, management of special nuclear materials at the INL, and...

  15. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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

    ... (MSR) concepts Nuclear fuel cycle systems and options analysis including fuel cycle evaluations to support R&D decisions and technical aspects of thorium-based fuel cycle systems. ...

  16. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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

    Reliable predictions of grid to rod gap, turbulent flow excitation, and resulting rod vibration and wear at any location in core. PCI Pellet-Clad Interaction. Cladding...

  17. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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

    Office of Nuclear Energy (NE) for their advancement of nuclear power; U.S. Nuclear Regulatory Commission (NRC) for safety reviews and licensing; R&D community for identification,...

  18. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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

    The toolkit also provides run-time parallel domain decomposition with data-migration for both static and dynamic load-balancing. Linear algebra is handled through an...

  19. CONSORTIUM FOR ADVANCED SIMULATION OF LIGHT WATER REACTORS (CASL...

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

    ... EPRI Battelle AREVA Westinghouse Global Nuclear Fuels Dominion Duke Energy EDF TVA ... Fuel Analysis 9 Analyze selected accident tolerant PWR fuel design 2018 BWR Safety ...

  20. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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

    ... Rak, Z., and D.W. Brenner, Materials Processing and Optimization (MPO) Fuels, ... Energy Agency (IAEA) Meeting on Accident Tolerant Fuel (ATF) Concepts for LWRs, ...

  1. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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

    Shown are horizontal slides of the coolant enthalpy moving up through the core. Energy Secretary Chu visits ORNL. Nuclear Energy After Fukushima Sharing a vision for the future: On ...

  2. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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

    Subchannel Methods for the Thermal-Hydraulic Analysis for Nuclear Power Systems presented by Dr. Michael Doster...

  3. Consortium for Advanced Simulation of Light Water Reactors (CASL)

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

    Enabling Modeling and Simulation Technology for Nuclear Power Nuclear energy is a tremendous technological success story for the United States. The first full-scale nuclear-powered electrical production plant at Pennsylvania's Shippingport Atomic Power Station was online in 1957, just 25 years after English physicist James Chadwick established the neutron's existence. However, in recent years, accelerated and translational R&D from fundamental discovery to commercialized technology has

  4. Consortium for Advanced Simulation of Light Water Reactors (CASL)

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

    Contact Us Address Oak Ridge National Laboratory PO Box 2008, MS6003 Oak Ridge, TN 37831-6003 Email Information Support ORNL Campus

  5. Consortium for Advanced Simulation of Light Water Reactors (CASL)

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

    VERA VERA.edu Software availability U.S. Citizens and most LPRs as limited by U.S. export control regulations Students, Faculty MOC radiation transport included included Sn and SPn radiation transport included Not included Monte Carlo radiation transport included included Integrated cross-section library included Limited functionality Integrated depletion library included Limited functionality Subchannel thermal-hydraulics included included Fuel performance included included Coolant chemistry

  6. Consortium for Advanced Simulation of Light Water Reactors (CASL...

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

    Smith, T.M., M.A. Christon, E. Baglietto and H. Luo, "Assessment of Models for Near Wall ... Romano, P., N. Horelik, B.R. Herman, A.G. Nelson, B. Forget and K. Smith, "OpenMC: A ...

  7. Phase 2 CASL Unlimited Access Report Outline

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

    ... Activities in MPACT During CASL Phase I 20 3.2.1 Critical Experiments 20 3.2.1.1 Babcock & Wilcox Critical Experiments 21 3.2.2.2 The Special Power Excursion Reactor Test (SPERT) ...

  8. Tabular water properties interface for Hydra-TH : CASL THM.CFD.P6.03 milestone report.

    SciTech Connect (OSTI)

    Carpenter, John H.; Belcourt, Noel

    2013-04-01

    Completion of the CASL L3 milestone THM.CFD.P6.03 provides a tabular material properties capability to the Hydra code. A tabular interpolation package used in Sandia codes was modified to support the needs of multi-phase solvers in Hydra. Use of the interface is described. The package was released to Hydra under a government use license. A dummy physics was created in Hydra to prototype use of the interpolation routines. Finally, a test using the dummy physics verifies the correct behavior of the interpolation for a test water table. 3

  9. CASL-U-2015-0067-000 Virtual Environment

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

    7-000 Virtual Environment for Reactor Applications (VERA) Workshop Session 2: Hands on Training Rose Montgomery The Tennessee Valley Authority April 1, 2015 CASL-U-2015-0067-000 1 Virtual Environment for Reactor Applications (VERA) Hands-On Training The American Nuclear Society ANFM Topical Meeting presents April 1, 2015 Hilton Head, SC Please check in to receive your student packet and RSA token to log onto the computers. CASL-U-2015-0067-000 2 2 CASL-U-2015-0067-000 2 CASL-U-2015-0067-000

  10. CASL-8-2015-0102-000

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

    2-000 Lean/Agile Principles and Practices for Developing Quality Scientific Software Roscoe A. Bartlett Oak Ridge National Laboratory July 8-10, 2013 CASL-U-2015-0102-000 Lean/Agile Principles and Practices for Developing Quality Scientific Software Roscoe A. Bartlett CASL Vertical Reactor Integration Software Engineering Lead Trilinos Software Engineering Technologies and Integration Lead Computer Science and Mathematics Div CASL-U-2015-0102-000 2 Managed by UT-Battelle for the U.S. Department

  11. Reactor water cleanup system

    DOE Patents [OSTI]

    Gluntz, Douglas M.; Taft, William E.

    1994-01-01

    A reactor water cleanup system includes a reactor pressure vessel containing a reactor core submerged in reactor water. First and second parallel cleanup trains are provided for extracting portions of the reactor water from the pressure vessel, cleaning the extracted water, and returning the cleaned water to the pressure vessel. Each of the cleanup trains includes a heat exchanger for cooling the reactor water, and a cleaner for cleaning the cooled reactor water. A return line is disposed between the cleaner and the pressure vessel for channeling the cleaned water thereto in a first mode of operation. A portion of the cooled water is bypassed around the cleaner during a second mode of operation and returned through the pressure vessel for shutdown cooling.

  12. Reactor water cleanup system

    DOE Patents [OSTI]

    Gluntz, D.M.; Taft, W.E.

    1994-12-20

    A reactor water cleanup system includes a reactor pressure vessel containing a reactor core submerged in reactor water. First and second parallel cleanup trains are provided for extracting portions of the reactor water from the pressure vessel, cleaning the extracted water, and returning the cleaned water to the pressure vessel. Each of the cleanup trains includes a heat exchanger for cooling the reactor water, and a cleaner for cleaning the cooled reactor water. A return line is disposed between the cleaner and the pressure vessel for channeling the cleaned water thereto in a first mode of operation. A portion of the cooled water is bypassed around the cleaner during a second mode of operation and returned through the pressure vessel for shutdown cooling. 1 figure.

  13. Light Water Reactor Sustainability (LWRS) Program | Department...

    Energy Savers [EERE]

    Nuclear Reactor Technologies Light Water Reactor Sustainability (LWRS) Program Light Water Reactor Sustainability (LWRS) Program Light Water Reactor Sustainability (LWRS) ...

  14. CASL Test Stands . . . Enabling the CASL mission

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

    A comprehensive, science-based understanding of these complex challenges requires high fidelity modeling & simulation (modsim) technology. CASL brings together a...

  15. CASL Plan of Record 2 (1/11-6/11)

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

    L3:RTM.PRT.P9.02 Demonstration of Full Core Reactor Depletion with MPACT Revision 0 ... August 10, 2014 CASL-U-2014-0140-000 Demonstration of Full Core Reactor Depletion with ...

  16. CASL Milestone L2.VRI.P6.01

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

    L2 Milestone VRI.P6.04 - VERA 3.0 CASL-U-2014-0006-000 i Fe Milestone L2:VRI.P6.04 Virtual Environment for Reactor Applications (VERA): Snapshot 3.0 03/29/2013 CASL-U-2014-0006-000 CASL L2 Milestone VRI.P6.04 - VERA 3.0 CASL-U-2014-0006-000 ii Oak Ridge National Laboratory in partnership with Electric Power Research Institute Idaho National Laboratory Los Alamos National Laboratory Massachusetts Institute of Technology North Carolina State University Sandia National Laboratories Tennessee Valley

  17. CASL - Electric Power Research Institute

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

    Electric Power Research Institute Palo Alto, CA EPRI is a collaborative nonprofit organization that conducts research and development relating to generation, delivery, and use of electricity for the benefit of the public. Our members include operators of all U.S. nuclear power plants and a large fraction of the nuclear plants worldwide. Key Contributions Leading the CASL Industry Council Technology and expertise on fuel performacne modeling User requirements for virtual reactor simulation

  18. Microsoft PowerPoint - NEAC CASL @ 3.5 Years Report v4

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

    ... Reactor System Multiphysics Integrator 4 CASL @3.5 Years Mesh Motion Quality Improvement Geometry Management Mesh Motion Quality Improvement Geometry Management Virtual ...

  19. CASL - Keeping It Real

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

    Keeping It Real To ensure its modeling and simulation research activities are appropriately focused on specific industry issues, CASL engages an Industry Council chaired by the Electric Power Research Institute. CASL is committed to engaging the nuclear power industry to ensure its research is "used and useful" and positively contributes to the ability to generate safe, reliable, economical, and carbon-free electricity from nuclear power. In his visit to the CASL facilities at Oak

  20. Los Alamos boosts light-water reactor research with advanced modeling and

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

    simulation technology Los Alamos boosts light-water reactor research Los Alamos boosts light-water reactor research with advanced modeling and simulation technology As part of the consortium CASL will now be deployed to industry and academia under a new inter-institutional agreement for intellectual property. March 2, 2015 A simulation demonstrates the volume fraction of a bubble phase in the region downstream of a 3×3 rod bundle after a short burst of bubbles has been introduced into the

  1. Light water reactor program

    SciTech Connect (OSTI)

    Franks, S.M.

    1994-12-31

    The US Department of Energy`s Light Water Reactor Program is outlined. The scope of the program consists of: design certification of evolutionary plants; design, development, and design certification of simplified passive plants; first-of-a-kind engineering to achieve commercial standardization; plant lifetime improvement; and advanced reactor severe accident program. These program activities of the Office of Nuclear Energy are discussed.

  2. CASL - Analysis of Two-Dimensional Lattice Physics

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

    Analysis of Two-Dimensional Lattice Physics CASL is developing the Virtual Environment for Reactor Applications (VERA) as a key capability to support the analysis of the CASL Challenge Problems. VERA will include a range of physics modeling capabilities necessary to model reactors, including neutronics, thermal hydraulics, fuel performance, and coolant chemistry. Lattice physics analyses, utilizing the newly-developed Michigan lattice physics neutronics capability in MPACT 1.0, are important to

  3. CASL - Initial Modeling and Analysis of the Departure from Nucleate Boiling

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

    Challenge Problem Initial Modeling and Analysis of the Departure from Nucleate Boiling Challenge Problem Yixing Sung, Jin Yan, Zeses E. Karoutas of Westinghouse Electric Company LLC Anh V. Bui, Hongbin Zhang of Idaho National Laboratories Nam Dinh of North Carolina State University Departure from Nucleate Boiling (DNB) is one of the safety-related Challenge Problems (CP) that CASL is addressing in support of Pressurized Water Reactor (PWR) power uprate, high fuel burnup and plant lifetime

  4. CASL-U-2015-0233-000 CASL Program Highlights

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

    3-000 CASL Program Highlights January 2015 Douglas Kothe Oak Ridge National Laboratory January 31, 2015 CASL-U-2015-0233-000 Computational Science Efforts Advance Fuel Performance Simulation MOOSE/Bison-CASL capability more adept at simulating the important fuel pellet-cladding contact phenomena * A new mechanical contact system in MOOSE has resulted in significantly better solution convergence for Bison-CASL * Size of models that can be run with this system had previously been limited due to

  5. CASL Industry Council Members:

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

    CASL Industry Council Members: We are looking forward to hosting you at the upcoming CASL Industry Council Meeting on Tuesday, April 12, 2016 through Wednesday, April 13, 2016 at the following location: ALOFT Greenville Downtown Converge Conference Room 5 North Laurens Street Greenville, SC 29601 864-297-6100 Meeting Contact: Lorie Fox (865) 548-5178 Lodging: ALOFT Greenville Downtown: http://www.aloftgreenvilledowntown.com/ Hotel Information * Check-in time: 4 PM * Checkout time: 12 PM * Fast

  6. CASL Test Stand Experience

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

    Industry Test Stand Experience Stephen Hess, EPRI Heather Feldman, EPRI Brenden Mervin, EPRI Martin Pytel, EPRI Rose Montgomery, TVA Bill Bird, TVA Fausto Franceschini, Westinghouse Electric Company LLC Advanced Modeling Applications 28 March 2014 CASL-U-2014-0036-000 Consortium for Advanced Simulation of LWRs ii CASL-U-2014-0036-000 REVISION LOG Revision Date Affected Pages Revision Description 0 3/28/2014 All Original Report Document pages that are: Export Controlled

  7. WATER BOILER REACTOR

    DOE Patents [OSTI]

    King, L.D.P.

    1960-11-22

    As its name implies, this reactor utilizes an aqueous solution of a fissionable element salt, and is also conventional in that it contains a heat exchanger cooling coil immersed in the fuel. Its novelty lies in the utilization of a cylindrical reactor vessel to provide a critical region having a large and constant interface with a supernatant vapor region, and the use of a hollow sleeve coolant member suspended from the cover assembly in coaxial relation with the reactor vessel. Cool water is circulated inside this hollow coolant member, and a gap between its outer wall and the reactor vessel is used to carry off radiolytic gases for recombination in an external catalyst chamber. The central passage of the coolant member defines a reflux condenser passage into which the externally recombined gases are returned and condensed. The large and constant interface between fuel solution and vapor region prevents the formation of large bubbles and minimizes the amount of fuel salt carried off by water vapor, thus making possible higher flux densities, specific powers and power densities.

  8. CASL-8-2015-0133-000 Robert Salko & Travis Lange Oak Ridge National...

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

    of COBRA-TF for Modeling Full-core, Reactor Operating Cycles CASL-U-2015-0133-000 ... DEVELOPMENT OF COBRA-TF FOR MODELING FULL-CORE, REACTOR OPERATING CYCLES Robert K. Salko ...

  9. CASL-U-2015-0237-000 CASL Program Highlights

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

    7-000 CASL Program Highlights May 2015 Jess C. Gehin Oak Ridge National Laboratory May 31, 2015 CASL-U-2015-0237-000 1 Patent award for CASL-developed VOCC Visualization Capability CASL CASL-U-2015-0237-000 2 Science Council Updated in a Midyear Briefing * On 5/22/15 the Science Council was briefed on - technical progress made in FY15 - actions taken on Science Council FY14 recommendations * Science Council recommendations originating from the briefing include - accelerate moving towards SC

  10. Development of a New 47-Group Library for the CASL Neutronics Simulators

    SciTech Connect (OSTI)

    Kim, Kang Seog; Williams, Mark L; Wiarda, Dorothea; Godfrey, Andrew T

    2015-01-01

    The CASL core simulator MPACT is under development for the neutronics and thermal-hydraulics coupled simulation for the pressurized light water reactors. The key characteristics of the MPACT code include a subgroup method for resonance self-shielding, and a whole core solver with a 1D/2D synthesis method. The ORNL AMPX/SCALE code packages have been significantly improved to support various intermediate resonance self-shielding approximations such as the subgroup and embedded self-shielding methods. New 47-group AMPX and MPACT libraries based on ENDF/B-VII.0 have been generated for the CASL core simulator MPACT of which group structure comes from the HELIOS library. The new 47-group MPACT library includes all nuclear data required for static and transient core simulations. This study discusses a detailed procedure to generate the 47-group AMPX and MPACT libraries and benchmark results for the VERA progression problems.

  11. CASL - Materials and Performance Optimization (MPO)

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

    Materials and Performance Optimization (MPO) The Materials and Performance Optimization (MPO) focus area within CASL has recently developed and released a 3D modeling framework known as MAMBA (MPO Advanced Model for Boron Analysis) to predict CRUD deposition on nuclear fuel rods. CRUD, which refers to Chalk River Unidentified Deposit, is predominately a nickel-ferrite spinel corrosion product that deposits on hot fuel clad surfaces in nuclear reactors. CRUD has a lower thermal conductivity than

  12. CASL Education Program and Summer Institute

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

    0-000 CASL Education Program and Summer Institute Dr. J. Michael Doster Professor of Nuclear Engineering North Carolina State University Director, CASL Education Program 2 CASL-U-2016-1090-000 CASL Education Program A new generation of LWR Designers, Scientists, and Nuclear Power Professionals Program Charter: * Integrate CASL technology into undergraduate and graduate curricula * Develop a plan to educate industry users * Encourage diversity of participation in CASL activities * Advise Chair on

  13. CASL - University of Michigan

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

    University of Michigan Ann Arbor, MI The U-M College of Engineering is home to four leading engineering departments that are actively participating in CASL: Nuclear Engineering and Radiological Sciences Aerospace Engineering Materials Science and Engineering Mechanical Engineering Key Contributions Computational methods development for radiation transport and coupled multiphysics simulation Uncertainty quantification for computational fluid dynamics with adjoint methods Analysis of structural

  14. CASL - Westinghouse Electric Company

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

    Westinghouse Electric Company Cranberry Township, PA Westinghouse Electric Company provides fuel, services, technology, plant design and equipment for the commercial nuclear electric power industry. Westinghouse nuclear technology is helping to provide future generations with safe, clean and reliable electricity. Key Contributions Definition of CASL challenge problems Existing codes and expertise Data for validation Computatinoal fluid dynamics modeling and analysis Development of test stand for

  15. CASL-U-2015-0230-000 CASL Program Highlights

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

    Plan * Uncertainty Quantification for MPACT * Industry Council Actions * Licensing Strategy Update * Education Program FY15 Plan * VERA Release Topics * CASL 2.0 Kickoff...

  16. Light Water Reactor Sustainability Technical Documents | Department...

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

    in Light Water Reactors: Life After 60 Nuclear reactors present a very harsh environment for components service. Components within a reactor core must tolerate high...

  17. CASL OLCF Early Science Award

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

    OLCF Early Science Award CASL-U-2013-0231-000 i Fe High-Fidelity Neutronic Analysis of the Westinghouse AP1000 An Oak Ridge Leadership Computing Facility (OLCF) Early Science Demonstration using the GPU- accelerated Cray XK7 Titan System Tom Evans Fausto Franceschini Andrew Godfrey Steven Hamilton Wayne Joubert John Turner CASL-U-2013-0231-000 CASL OLCF Early Science Award CASL-U-2013-0231-000 ii Oak Ridge National Laboratory in partnership with Electric Power Research Institute Idaho National

  18. Light Water Reactor Sustainability Nondestructive Evaluation...

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

    US Department of Energy Office of Nuclear Energy's Light Water Reactor Sustainability ... A multitude of concrete-based structures are typically part of a light water reactor (LWR) ...

  19. Light Water Reactor Sustainability Program - Integrated Program...

    Office of Environmental Management (EM)

    Program - Integrated Program Plan Light Water Reactor Sustainability Program - Integrated Program Plan The Light Water Reactor Sustainability (LWRS) Program is a research and ...

  20. CASL-U-2015-0234-000 CASL Program Highlights

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

    4-000 CASL Program Highlights February 2015 Douglas Kothe Oak Ridge National Laboratory February 29, 2014 CASL-U-2015-0234-000 Outcome: VERA was demonstrated to be capable of simulating iPWR geometry and control rod management for normal operating conditions. H concentration Contributors: Rose Montgomery (TVA), Ben Collins (ORNL) Independent review by Dudley Raine (B&W) CASL Demonstration of VERA Capabilities to simulate an iPWR SMR Illustration of the B&W mPower iPWR used as a basis for

  1. Improving Reactor Performance Rose Montgomery The Tennessee Valley...

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

    Improving Reactor Performance Rose Montgomery The Tennessee Valley Authority Mark Uhran Oak Ridge National Laboratory April 9, 2013 CASL-U-2013-0034-001 CASL-U-2013-0034-001 ...

  2. CHIMNEY FOR BOILING WATER REACTOR

    DOE Patents [OSTI]

    Petrick, M.

    1961-08-01

    A boiling-water reactor is described which has vertical fuel-containing channels for forming steam from water. Risers above the channels increase the head of water radially outward, whereby water is moved upward through the channels with greater force. The risers are concentric and the radial width of the space between them is somewhat small. There is a relatively low rate of flow of water up through the radially outer fuel-containing channels, with which the space between the risers is in communication. (AE C)

  3. CASL-U-2015-0022-000

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

    Laboratory December 16, 2014 CASL-U-2015-0022-000 K. Clarno and R. Pawlowski ... Tiamat has been developed for analysis of Page 2 of 22 CASL-U-2015-0022-000 Incorporate ...

  4. CASL-8-2015-0220-000

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

    System Thermodynamics Christopher Stanek Los Alamos National Laboratory June 3, 2015 CASL-U-2015-0220-000 CASL-U-2015-0220-000 Starting point should be a comprehensive ...

  5. CASL-U-2015-0243-000

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

    3-000 CFD Simulations of Experiments in a Twin Jet Water Facility Lane Carasik Yassin Hassan Texas A&M University CASL-U-2015-0243-000 CFD Simulations of Experiments in a Twin Jet Water Facility Lane Carasik, Graduate Research Assistant and NEUP Fellow Dr. Yassin Hassan, Professor Twin Jet Studies Turbulent twin jets shooting into quiescent surroundings provide a physics rich platform for developing and validating new simulations. The jet properties can be controlled in the TJWF built to

  6. CASL L1 Milestone report : CASL.P4.01, sensitivity and uncertainty analysis for CIPS with VIPRE-W and BOA.

    SciTech Connect (OSTI)

    Sung, Yixing; Adams, Brian M.; Secker, Jeffrey R.

    2011-12-01

    The CASL Level 1 Milestone CASL.P4.01, successfully completed in December 2011, aimed to 'conduct, using methodologies integrated into VERA, a detailed sensitivity analysis and uncertainty quantification of a crud-relevant problem with baseline VERA capabilities (ANC/VIPRE-W/BOA).' The VUQ focus area led this effort, in partnership with AMA, and with support from VRI. DAKOTA was coupled to existing VIPRE-W thermal-hydraulics and BOA crud/boron deposit simulations representing a pressurized water reactor (PWR) that previously experienced crud-induced power shift (CIPS). This work supports understanding of CIPS by exploring the sensitivity and uncertainty in BOA outputs with respect to uncertain operating and model parameters. This report summarizes work coupling the software tools, characterizing uncertainties, and analyzing the results of iterative sensitivity and uncertainty studies. These studies focused on sensitivity and uncertainty of CIPS indicators calculated by the current version of the BOA code used in the industry. Challenges with this kind of analysis are identified to inform follow-on research goals and VERA development targeting crud-related challenge problems.

  7. HEAVY WATER MODERATED NEUTRONIC REACTOR

    DOE Patents [OSTI]

    Szilard, L.

    1958-04-29

    A nuclear reactor of the type which utilizes uranium fuel elements and a liquid coolant is described. The fuel elements are in the form of elongated tubes and are disposed within outer tubes extending through a tank containing heavy water, which acts as a moderator. The ends of the fuel tubes are connected by inlet and discharge headers, and liquid bismuth is circulated between the headers and through the fuel tubes for cooling. Helium is circulated through the annular space between the outer tubes in the tank and the fuel tubes to cool the water moderator to prevent boiling. The fuel tubes are covered with a steel lining, and suitable control means, heat exchange means, and pumping means for the coolants are provided to complete the reactor assembly.

  8. LIGHT WATER MODERATED NEUTRONIC REACTOR

    DOE Patents [OSTI]

    Christy, R.F.; Weinberg, A.M.

    1957-09-17

    A uranium fuel reactor designed to utilize light water as a moderator is described. The reactor core is in a tank at the bottom of a substantially cylindrical cross-section pit, the core being supported by an apertured grid member and comprised of hexagonal tubes each containing a pluralily of fuel rods held in a geometrical arrangement between end caps of the tubes. The end caps are apertured to permit passage of the coolant water through the tubes and the fuel elements are aluminum clad to prevent corrosion. The tubes are hexagonally arranged in the center of the tank providing an amulus between the core and tank wall which is filled with water to serve as a reflector. In use, the entire pit and tank are filled with water in which is circulated during operation by coming in at the bottom of the tank, passing upwardly through the grid member and fuel tubes and carried off near the top of the pit, thereby picking up the heat generated by the fuel elements during the fission thereof. With this particular design the light water coolant can also be used as the moderator when the uranium is enriched by fissionable isotope to an abundance of U/sup 235/ between 0.78% and 2%.

  9. Advanced Nuclear Technology: Advanced Light Water Reactors Utility...

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

    Nuclear Technology: Advanced Light Water Reactors Utility Requirements Document Small Modular Reactors Inclusion Summary Advanced Nuclear Technology: Advanced Light Water Reactors ...

  10. SUPERHEATING IN A BOILING WATER REACTOR

    DOE Patents [OSTI]

    Treshow, M.

    1960-05-31

    A boiling-water reactor is described in which the steam developed in the reactor is superheated in the reactor. This is accomplished by providing means for separating the steam from the water and passing the steam over a surface of the fissionable material which is not in contact with the water. Specifically water is boiled on the outside of tubular fuel elements and the steam is superheated on the inside of the fuel elements.

  11. CASL Validation Data: An Initial Review

    SciTech Connect (OSTI)

    Nam Dinh

    2011-01-01

    The study aims to establish a comprehensive view of “data” needed for supporting implementation of the Consortium of Advanced Simulation of LWRs (CASL). Insights from this review (and its continual refinement), together with other elements developed in CASL, should provide the foundation for developing the CASL Validation Data Plan (VDP). VDP is instrumental to the development and assessment of CASL simulation tools as predictive capability. Most importantly, to be useful for CASL, the VDP must be devised (and agreed upon by all participating stakeholders) with appropriate account for nature of nuclear engineering applications, the availability, types and quality of CASL-related data, and novelty of CASL goals and its approach to the selected challenge problems. The initial review (summarized on the January 2011 report version) discusses a broad range of methodological issues in data review and Validation Data Plan. Such a top-down emphasis in data review is both needed to see a big picture on CASL data and appropriate when the actual data are not available for detailed scrutiny. As the data become available later in 2011, a revision of data review (and regular update) should be performed. It is expected that the basic framework for review laid out in this report will help streamline the CASL data review in a way that most pertinent to CASL VDP.

  12. CASL - Los Alamos National Laboratory

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

    Los Alamos National Laboratory Los Alamos, NM A world-class, multi-disciplinary research and development institution focused on national security missions, Los Alamos brings to CASL particular strengths in computational and material sciences. Fission and fusion energy Advanced materials Nuclear radiation technologies Science policy Key Contributions Materials science and multiscale leadership Models and numerical methods leadership Advanced computational architectures Advanced code development

  13. Heavy Water Test Reactor Dome Removal

    SciTech Connect (OSTI)

    2011-01-01

    A high speed look at the removal of the Heavy Water Test Reactor Dome Removal. A project sponsored by the Recovery Act on the Savannah River Site.

  14. CASL---U---2014-0038-000

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

    User Guidelines and Best Practices for CASL VUQ Analysis Using Dakota CASL---U---2014-0038-000 Brian M. Adams 1 Russell W. Hooper 1 Allison Lewis 2 Jerry A. McMahan, Jr. 2 Ralph C. S mith 2 Laura P . Swiler 1 Brian J. Williams 3 1 Sandia N ational L aboratories 2 North C arolina S tate U niversity 3 Los A lamos National Laboratory March 2 8, 2014 L3:VUQ.V&V.P8.01 CASL-U-2014-0038-000 User Guidelines and Best Practices for CASL VUQ Analysis Using Dakota Brian M. Adams 1 Russell W. Hooper 2

  15. CASL-U-2015-0101-000

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

    ... * manufacturing quality * operating environment, interference * initial, boundary ... CASL-U-2015-0101-000 9 * What? Determine variability, distributions, statistics of code ...

  16. CASL-8-2015-0021-000 Contact Memory Report CASL.FY14 Rich Williamson

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

    1-000 Contact Memory Report CASL.FY14 Rich Williamson Idaho National Laboratory January 31, 2015 CASL-U-2015-0021-000 Contact Memory Reduction CASL FY15 Letter Report January 30, 2015 Introduction As documented in a prior CASL milestone report [1], work has been underway to transition to a new system of contact enforcement in MOOSE, and by extension, the fuel performance codes BISON and BISON-CASL, which are based on MOOSE. This new system, known as the Constraint system, achieves significantly

  17. PRESSURIZED WATER REACTOR CORE WITH PLUTONIUM BURNUP

    DOE Patents [OSTI]

    Puechl, K.H.

    1963-09-24

    A pressurized water reactor is described having a core containing Pu/sup 240/ in which the effective microscopic neutronabsorption cross section of Pu/sup 240/ in unconverted condition decreases as the time of operation of the reactor increases, in order to compensate for loss of reactivity resulting from fission product buildup during reactor operation. This means serves to improve the efficiency of the reactor operation by reducing power losses resulting from control rods and burnable poisons. (AEC)

  18. CASL - Tennessee Valley Authority

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

    Tennessee Valley Authority Chattanooga, TN The nation's largest public power company, TVA plans to use more nuclear energy in achieving its vision to be one of the nation's leading providers of low-cost and cleaner energy. Key Contributions Physical reactor design Commercial nuclear plant and nuclear fuel operating data Support for testing and validation Key Outcomes Benchmark and test Virtual Environment for Reactor Applications (VERA) with operating reactor data Facilitate early deployment of

  19. Light-Water Breeder Reactor

    DOE Patents [OSTI]

    Beaudoin, B. R.; Cohen, J. D.; Jones, D. H.; Marier, Jr, L. J.; Raab, H. F.

    1972-06-20

    Described is a light-water-moderated and -cooled nuclear breeder reactor of the seed-blanket type characterized by core modules comprising loosely packed blanket zones enriched with fissile fuel and axial zoning in the seed and blanket regions within each core module. Reactivity control over lifetime is achieved by axial displacement of movable seed zones without the use of poison rods in the embodiment illustrated. The seed is further characterized by a hydrogen-to-uranium-233 atom ratio in the range 10 to 200 and a uranium-233-to-thorium-232 atom ratio ranging from 0.012 to 0.200. The seed occupies from 10 to 35 percent of the core volume in the form of one or more individual islands or annuli. (NSA 26: 55130)

  20. Advanced Nuclear Technology: Advanced Light Water Reactors Utility Requirements Document Small Modular Reactors Inclusion Summary

    Office of Energy Efficiency and Renewable Energy (EERE)

    Advanced Nuclear Technology: Advanced Light Water Reactors Utility Requirements Document Small Modular Reactors Inclusion Summary November 2014

  1. CASL - Idaho National Laboratory

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

    Idaho National Laboratory Idaho Falls, ID INL is the lead nuclear energy (NE) laboratory for the U.S. Department of Energy. The laboratory has designed and operated 52 test reactors, including EBR-1, the world's first nuclear power plant Key Contributions System safety analysis Multiscale fuel performance simulation Multiphysics coupling framework (MOOSE) Reactor physics Multiphase flow Validation Nuclear Science User Facilities Key Outcomes Test stand for NE programs Virtual Environment for

  2. TA-2 Water Boiler Reactor Decommissioning Project

    SciTech Connect (OSTI)

    Durbin, M.E.; Montoya, G.M.

    1991-06-01

    This final report addresses the Phase 2 decommissioning of the Water Boiler Reactor, biological shield, other components within the biological shield, and piping pits in the floor of the reactor building. External structures and underground piping associated with the gaseous effluent (stack) line from Technical Area 2 (TA-2) Water Boiler Reactor were removed in 1985--1986 as Phase 1 of reactor decommissioning. The cost of Phase 2 was approximately $623K. The decommissioning operation produced 173 m{sup 3} of low-level solid radioactive waste and 35 m{sup 3} of mixed waste. 15 refs., 25 figs., 3 tabs.

  3. Specification of requirements for the virtual environment for reactor applications simulation environment

    SciTech Connect (OSTI)

    Hess, S. M.; Pytel, M.

    2012-07-01

    In 2010, the United States Dept. of Energy initiated a research and development effort to develop modern modeling and simulation methods that could utilize high performance computing capabilities to address issues important to nuclear power plant operation, safety and sustainability. To respond to this need, a consortium of national laboratories, academic institutions and industry partners (the Consortium for Advanced Simulation of Light Water Reactors - CASL) was formed to develop an integrated Virtual Environment for Reactor Applications (VERA) modeling and simulation capability. A critical element for the success of the CASL research and development effort was the development of an integrated set of overarching requirements that provides guidance in the planning, development, and management of the VERA modeling and simulation software. These requirements also provide a mechanism from which the needs of a broad array of external CASL stakeholders (e.g. reactor / fuel vendors, plant owner / operators, regulatory personnel, etc.) can be identified and integrated into the VERA development plans. This paper presents an overview of the initial set of requirements contained within the VERA Requirements Document (VRD) that currently is being used to govern development of the VERA software within the CASL program. The complex interdisciplinary nature of these requirements together with a multi-physics coupling approach to realize a core simulator capability pose a challenge to how the VRD should be derived and subsequently revised to accommodate the needs of different stakeholders. Thus, the VRD is viewed as an evolving document that will be updated periodically to reflect the changing needs of identified CASL stakeholders and lessons learned during the progress of the CASL modeling and simulation program. (authors)

  4. Review of light water reactor safety

    SciTech Connect (OSTI)

    Cheng, H.S.

    1980-12-01

    A review of the present status of light water reactor (LWR) safety is presented. The review starts with a brief discussion of the outstanding accident scenarios concerning LWRs. Where possible the areas of present technological uncertainties are stressed. To provide a better perspective of reactor safety, it then reviews the probabilistic assessment of the outstanding LWR accidents considered in the Reactor Safety Study (WASH-1400) and discusses the potential impact of the present technological uncertainties on WASH-1400.

  5. Boiling water reactor-full length emergency core cooling heat...

    Office of Scientific and Technical Information (OSTI)

    Technical Report: Boiling water reactor-full length emergency core cooling heat transfer ... Citation Details In-Document Search Title: Boiling water reactor-full length emergency ...

  6. Preliminary design study of small long life boiling water reactor...

    Office of Scientific and Technical Information (OSTI)

    boiling water reactor (BWR) with tight lattice thorium nitride fuel Citation Details In-Document Search Title: Preliminary design study of small long life boiling water reactor ...

  7. Partial Defect Testing of Pressurized Water Reactor Spent Fuel...

    Office of Scientific and Technical Information (OSTI)

    Partial Defect Testing of Pressurized Water Reactor Spent Fuel Assemblies Citation Details In-Document Search Title: Partial Defect Testing of Pressurized Water Reactor Spent Fuel ...

  8. Accident analysis of heavy water cooled thorium breeder reactor...

    Office of Scientific and Technical Information (OSTI)

    Accident analysis of heavy water cooled thorium breeder reactor Citation Details In-Document Search Title: Accident analysis of heavy water cooled thorium breeder reactor ...

  9. Development of Light Water Reactor Fuels with Enhanced Accident...

    Energy Savers [EERE]

    Development of Light Water Reactor Fuels with Enhanced Accident Tolerance - Report to Congress Development of Light Water Reactor Fuels with Enhanced Accident Tolerance - Report to ...

  10. Light Water Reactor Sustainability (LWRS) Program - R&D Roadmap...

    Office of Environmental Management (EM)

    Damage in Piping Light Water Reactor Sustainability (LWRS) Program - R&D Roadmap for Non-Destructive Evaluation (NDE) of Fatigue Damage in Piping Light water reactor sustainability ...

  11. Light Water Reactor Sustainability Program - Non-Destructive...

    Office of Environmental Management (EM)

    Light Water Reactor Sustainability Program - Non-Destructive Evaluation R&D Roadmap for ... important information to the Light Water Reactor Sustainability (LWRS) program ...

  12. CASL-2015.L2.FMC.P11.01

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

    &$6/ 8 L2.FMC.P11.01 Demonstrate 3D PCI analysis with BISON- CASL for PCI fuel failure in a commercial power reactor Nathan C apps 1 , W enfeng L iu 2 , R obert Montgomery 3 , M artin P ytel 4 , J oe R ashid 2 , Ben Spencer 5 , D ion S underland 3 , R ich Williamson 5 , a nd B rian D . W irth 1 1. University of Tennessee, Knoxville 2. Anatech Corp. 3. Pacific Northwest National Laboratory 4. Electric Power Research Institute 5. Idaho National Laboratory September 30, 2015

  13. Light Water Reactor Sustainability (LWRS) Initiative Science...

    Energy Savers [EERE]

    disposed instead of untreated used fuel. April 29, 2010 Constituents of Used Light Water Reactor Nuclear Fuel (by mass) April 29, 2010 Descriptions from NE R&D Roadmap to...

  14. CASL - Sandia National Laboratory

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

    Sandia National Laboratory Albuquerque, NM Sandia has a long history of providing world-class capabilities in nuclear energy safety and licensing and in advance computational science and high-performance computing. Key Contributions Advanced algorithms and architectures Scalable, coupled, and integrated multiphysics codes Verfication and validation (V&V) and uncertainty quantification (UQ) Safety and risk assessment Key Outcomes Virtual Environment for Reactor Application (VERA) Advanced

  15. CASL-U-2015-0152-000

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

    University of Michigan Forrest B. Brown Los Alamos National Laboratory March 29, 2015 CASL-U-2015-0152-000 Advances in Nuclear Fuel Management V (ANFM 2015) Hilton Head Island, ...

  16. CASL-U-2015-0180-000

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

    Dorothea Wiarda, and Andrew T. Godfrey Oak Ridge National Laboratory April 19, 2015 CASL-U-2015-0180-000 ANS MC2015 - Joint International Conference on Mathematics and ...

  17. CASL-U-2015-0176-000

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

    April 19, 2015 CASL-U-2015-0176-000 ANS MC2015 - Joint International Conference on Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte ...

  18. CASL-U-2015-0224-000

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

    May 28, 2015 CASL-U-2015-0224-000 ANS MC2015 - Joint International Conference on Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte ...

  19. CASL-U-2015-0251-000

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

    Heat Transfer Regimes in CRUD Miaomiao Jin, Michael P. Short Massachusetts Institute of Technology July 7, 2015 CASL-U-2015-0251-000 STUDY ON TWO-PHASE FLUID AND HEAT TRANSFER ...

  20. CASL-8-2015-0026-000

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

    6-000 Fuel Performance with BISON Koroush Shirvan Massachusetts Institute of Technology July 12, 2014 CASL-U-2015-0026-000 Koroush Shirvan Research Scientist June 12, 2014 Fuel performance with BISON NSE Nuclear Science & Engineering at MIT science : systems : society CASL-U-2015-0026-000 Outline  BISON Overview  Prerequisite  Fuel Performance Overview  Oxide Fuel Pin Behavior  Reactivity Initiating Accidents  Metal Fuel Pin Behavior  BISON Demonstration  Conclusions

  1. During FY15, CASL significantly advanced

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

    During FY15, CASL significantly advanced VERA's capability to mod- el the CRUD Challenge Problem to predict the occurrence of CRUD Induced Power Shift (CIPS). VERA has been modified to include the space and time dependent deposition of CRUD onto the fuel, along with boron capture and its effects on local rod power and thermal hydraulic conditions. Early in CASL's program, coolant chemistry subcompo- nents (MAMBA and MAMBA-BDM) were developed to describe local CRUD deposition. Since then the

  2. Pressurized water reactor flow skirt apparatus

    DOE Patents [OSTI]

    Kielb, John F.; Schwirian, Richard E.; Lee, Naugab E.; Forsyth, David R.

    2016-04-05

    A pressurized water reactor vessel having a flow skirt formed from a perforated cylinder structure supported in the lower reactor vessel head at the outlet of the downcomer annulus, that channels the coolant flow through flow holes in the wall of the cylinder structure. The flow skirt is supported at a plurality of circumferentially spaced locations on the lower reactor vessel head that are not equally spaced or vertically aligned with the core barrel attachment points, and the flow skirt employs a unique arrangement of hole patterns that assure a substantially balanced pressure and flow of the coolant over the entire underside of the lower core support plate.

  3. Materials Degradation in Light Water Reactors: Life After 60

    Broader source: Energy.gov [DOE]

    Nuclear reactors present a very harsh environment for components service. Components within a reactor core must tolerate high temperature water, stress, vibration, and an intense neutron field....

  4. CASL - Radiation Transport Methods Update

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

    Radiation Transport Methods Update The Radiation Transport Methods (RTM) focus area is responsible for the development of methods, algorithms, and implementations of radiation transport methods as they apply to the design and analysis of light water nuclear reactors. the fundamental areas of investigation in RTM include high-order deterministic transport low-order transport approximations multigroup cross section generation depletion as it applies to in-core neutronics and material coupling

  5. BOILING WATER REACTOR WITH FEED WATER INJECTION NOZZLES

    DOE Patents [OSTI]

    Treshow, M.

    1963-04-30

    This patent covers the use of injection nozzles for pumping water into the lower ends of reactor fuel tubes in which water is converted directly to steam. Pumping water through fuel tubes of this type of boiling water reactor increases its power. The injection nozzles decrease the size of pump needed, because the pump handles only the water going through the nozzles, additional water being sucked into the tubes by the nozzles independently of the pump from the exterior body of water in which the fuel tubes are immersed. The resulting movement of exterior water along the tubes holds down steam formation, and thus maintains the moderator effectiveness, of the exterior body of water. (AEC)

  6. HEAVY WATER COMPONENTS TEST REACTOR DECOMMISSIONING

    SciTech Connect (OSTI)

    Austin, W.; Brinkley, D.

    2011-10-13

    The Heavy Water Components Test Reactor (HWCTR) Decommissioning Project was initiated in 2009 as a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) Removal Action with funding from the American Recovery and Reinvestment Act (ARRA). This paper summarizes the history prior to 2009, the major D&D activities, and final end state of the facility at completion of decommissioning in June 2011. The HWCTR facility was built in 1961, operated from 1962 to 1964, and is located in the northwest quadrant of the Savannah River Site (SRS) approximately three miles from the site boundary. The HWCTR was a pressurized heavy water test reactor used to develop candidate fuel designs for heavy water power reactors. In December of 1964, operations were terminated and the facility was placed in a standby condition as a result of the decision by the U.S. Atomic Energy Commission to redirect research and development work on heavy water power reactors to reactors cooled with organic materials. For about one year, site personnel maintained the facility in a standby status, and then retired the reactor in place. In the early 1990s, DOE began planning to decommission HWCTR. Yet, in the face of new budget constraints, DOE deferred dismantlement and placed HWCTR in an extended surveillance and maintenance mode. The doors of the reactor facility were welded shut to protect workers and discourage intruders. In 2009 the $1.6 billion allocation from the ARRA to SRS for site footprint reduction at SRS reopened the doors to HWCTR - this time for final decommissioning. Alternative studies concluded that the most environmentally safe, cost effective option for final decommissioning was to remove the reactor vessel, both steam generators, and all equipment above grade including the dome. The transfer coffin, originally above grade, was to be placed in the cavity vacated by the reactor vessel and the remaining below grade spaces would be grouted. Once all above equipment

  7. Light-water reactor accident classification

    SciTech Connect (OSTI)

    Washburn, B.W.

    1980-02-01

    The evolution of existing classifications and definitions of light-water reactor accidents is considered. Licensing practice and licensing trends are examined with respect to terms of art such as Class 8 and Class 9 accidents. Interim definitions, consistent with current licensing practice and the regulations, are proposed for these terms of art.

  8. Hydrogen and water reactor safety: proceedings

    SciTech Connect (OSTI)

    Not Available

    1982-01-01

    Separate abstracts were prepared for papers presented in the following areas of interest: 1) hydrogen research programs; 2) hydrogen behavior during light water reactor accidents; 3) combustible gas generation; 4) hydrogen transport and mixing; 5) combustion modeling and experiments; 6) accelerated flames and detonations; 7) combustion mitigation and control; and 8) equipment survivability.

  9. SELF-REGULATING BOILING-WATER NUCLEAR REACTORS

    DOE Patents [OSTI]

    Ransohoff, J.A.; Plawchan, J.D.

    1960-08-16

    A boiling-water reactor was designed which comprises a pressure vessel containing a mass of water, a reactor core submerged within the water, a reflector tank disposed within the reactor, the reflector tank being open at the top to the interior of the pressure vessel, and a surge tank connected to the reflector tank. In operation the reflector level changes as a function of the pressure witoin the reactor so that the reactivity of the reactor is automatically controlled.

  10. Electrochemistry of Water-Cooled Nuclear Reactors

    SciTech Connect (OSTI)

    Macdonald, Dgiby; Urquidi-Macdonald, Mirna; Pitt, Jonathan

    2006-08-08

    This project developed a comprehensive mathematical and simulation model for calculating thermal hydraulic, electrochemical, and corrosion parameters, viz. temperature, fluid flow velocity, pH, corrosion potential, hydrogen injection, oxygen contamination, stress corrosion cracking, crack growth rate, and other important quantities in the coolant circuits of water-cooled nuclear power plants, including both Boiling Water Reactors (BWRs) and Pressurized Water Reactors (PWRs). The model is being used to assess the three major operational problems in Pressurized Water Reactors (PWR), which include mass transport, activity transport, and the axial offset anomaly, and provide a powerful tool for predicting the accumulation of SCC damage in BWR primary coolant circuits as a function of operating history. Another achievement of the project is the development of a simulation tool to serve both as a training tool for plant operators and as an engineering test-bed to evaluate new equipment and operating strategies (normal operation, cold shut down and others). The development and implementation of the model allows us to estimate the activity transport or "radiation fields" around the primary loop and the vessel, as a function of the operating parameters and the water chemistry.

  11. Light Water Reactor Sustainability Program - Integrated Program Plan |

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

    Department of Energy Light Water Reactor Sustainability Program - Integrated Program Plan Light Water Reactor Sustainability Program - Integrated Program Plan The Light Water Reactor Sustainability (LWRS) Program is a research and development (R&D) program sponsored by the U. S. Department of Energy (DOE), performed in close collaboration and cooperation with related industry R&D programs. Light Water Reactor Sustainability Program - Integrated Program Plan - Revision 3 (2.66 MB)

  12. CASL-U-2015-0116-000

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

    16-000 Implementation and Preliminary Verification of the Quasi-1D Kernel for Intra-pin Resonance Physics in MPACT Yuxuan Liu and William Martin University of Michigan March 16, 2015 CASL-U-2015-0116-000 Implementation and Preliminary Verification of the Quasi-1D Kernel for Intra-pin Resonance Physics in MPACT Yuxuan Liu and William Martin University of Michigan L3:RTM.SUP.P10.03 Milestone Report March 16, 2015 CASL-U-2015-0116-000 2 EXECUTIVE SUMMARY A new resonance self-shielding method ESSM-X

  13. Light Water Reactor Sustainability Program: Materials Aging and...

    Office of Environmental Management (EM)

    Program: Materials Aging and Degradation Technical Program Plan Light Water Reactor ... Primary water stress corrosion cracking (PWSCC) is one key form of degradation in extended ...

  14. Containment system for supercritical water oxidation reactor

    DOE Patents [OSTI]

    Chastagner, P.

    1994-07-05

    A system is described for containment of a supercritical water oxidation reactor in the event of a rupture of the reactor. The system includes a containment for housing the reaction vessel and a communicating chamber for holding a volume of coolant, such as water. The coolant is recirculated and sprayed to entrain and cool any reactants that might have escaped from the reaction vessel. Baffles at the entrance to the chamber prevent the sprayed coolant from contacting the reaction vessel. An impact-absorbing layer is positioned between the vessel and the containment to at least partially absorb momentum of any fragments propelled by the rupturing vessel. Remote, quick-disconnecting fittings exterior to the containment, in cooperation with shut-off valves, enable the vessel to be isolated and the system safely taken off-line. Normally-closed orifices throughout the containment and chamber enable decontamination of interior surfaces when necessary. 2 figures.

  15. Containment system for supercritical water oxidation reactor

    DOE Patents [OSTI]

    Chastagner, Philippe

    1994-01-01

    A system for containment of a supercritical water oxidation reactor in the event of a rupture of the reactor. The system includes a containment for housing the reaction vessel and a communicating chamber for holding a volume of coolant, such as water. The coolant is recirculated and sprayed to entrain and cool any reactants that might have escaped from the reaction vessel. Baffles at the entrance to the chamber prevent the sprayed coolant from contacting the reaction vessel. An impact-absorbing layer is positioned between the vessel and the containment to at least partially absorb momentum of any fragments propelled by the rupturing vessel. Remote, quick-disconnecting fittings exterior to the containment, in cooperation with shut-off valves, enable the vessel to be isolated and the system safely taken off-line. Normally-closed orifices throughout the containment and chamber enable decontamination of interior surfaces when necessary.

  16. CASL-U-2015-0108-000 A CASL Multiphysics Code Coupling Primer: Software

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

    08-000 A CASL Multiphysics Code Coupling Primer: Software Integration 101 (SAND2013-5908C) Roger Pawlowski Sandia National Laboratory July 9, 2013 A CASL Multiphysics Code Coupling Primer: Software Integration 101 Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U.S. Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000. Roger

  17. Light Water Reactor Sustainability Technical Documents | Department of

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

    Energy Nuclear Reactor Technologies » Light Water Reactor Sustainability Program » Light Water Reactor Sustainability Technical Documents Light Water Reactor Sustainability Technical Documents April 30, 2015 LWRS Program and EPRI Long-Term Operations Program - Joint R&D Plan To address the challenges associated with pursuing commercial nuclear power plant operations beyond 60 years, the U.S. Department of Energy's (DOE) Office of Nuclear Energy (NE) and the Electric Power Research

  18. Boiling water neutronic reactor incorporating a process inherent safety design

    DOE Patents [OSTI]

    Forsberg, C.W.

    1985-02-19

    A boiling-water reactor core is positioned within a prestressed concrete reactor vessel of a size which will hold a supply of coolant water sufficient to submerge and cool the reactor core by boiling for a period of at least one week after shutdown. Separate volumes of hot, clean (nonborated) water for cooling during normal operation and cool highly borated water for emergency cooling and reactor shutdown are separated by an insulated wall during normal reactor operation with contact between the two water volumes being maintained at interfaces near the top and bottom ends of the reactor vessel. Means are provided for balancing the pressure of the two water volumes at the lower interface zone during normal operation to prevent entry of the cool borated water into the reactor core region, for detecting the onset of excessive power to coolant flow conditions in the reactor core and for detecting low water levels of reactor coolant. Cool borated water is permitted to flow into the reactor core when low reactor coolant levels or excessive power to coolant flow conditions are encountered.

  19. Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Assessment of High Value Surveillance Materials

    Office of Energy Efficiency and Renewable Energy (EERE)

    The reactor pressure vessel (RPV) in a light-water reactor (LWR) represents the first line of defense against a release of radiation in case of an accident. Thus, regulations that govern the...

  20. Development of Materials for Supercritical-Water-Cooled Reactor

    Broader source: Energy.gov [DOE]

    Supercritical-Water-Cooled Reactor (SCWR) was selected as one of the promising candidates in Generation IV reactors for its prominent advantages; those are the high thermal efficiency, the system...

  1. The 100K West Reactor Water Treatment Facilities

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

    demolition (D&D) work at the 100K West Reactor Water Treatment Facilities at the Hanford ... facilities and waste sites that supported reactor operations from the 1950s to the 1970s. ...

  2. CASL Plan of Record 2 (1/11-6/11)

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

    VERA Core Physics Benchmark Progression Problem Specifications Revision 2 March 29, 2013 Andrew T. Godfrey Advanced Modeling Applications Oak Ridge National Laboratory A. Godfrey, VERA Core Physics Benchmark Progression Problem Specifications, CASL Technical Report: CASL-U-2012-0131-002 VERA Core Physics Benchmark Problems CASL-U-2012-0131-002 i Consortium for Advanced Simulation of LWRs This report was prepared as an account of work sponsored by an agency of the United States government.

  3. Boiling water neutronic reactor incorporating a process inherent safety design

    DOE Patents [OSTI]

    Forsberg, Charles W.

    1987-01-01

    A boiling-water reactor core is positioned within a prestressed concrete reactor vessel of a size which will hold a supply of coolant water sufficient to submerge and cool the reactor core by boiling for a period of at least one week after shutdown. Separate volumes of hot, clean (non-borated) water for cooling during normal operation and cool highly borated water for emergency cooling and reactor shutdown are separated by an insulated wall during normal reactor operation with contact between the two water volumes being maintained at interfaces near the top and bottom ends of the reactor vessel. Means are provided for balancing the pressure of the two volumes at the lower interface zone during normal operation to prevent entry of the cool borated water into the reactor core region, for detecting the onset of excessive power to coolant flow conditions in the reactor core and for detecting low water levels of reactor coolant. Cool borated water is permitted to flow into the reactor core when low reactor coolant levels or excessive power to coolant flow conditions are encountered.

  4. CASL-U-2015-0157-000 Stabilization Methods

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

    - Joint International Conference on Mathematics and Computation (M&C), Supercomputing ... CASL-U-2015-0157-000 ANS MC2015 - Joint International Conference on Mathematics and ...

  5. Microsoft PowerPoint - CASL IC member Overviews.pptx

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

    ... Erwin, TN Nuclear plant development projects mPower, Terrapower Accident tolerant fuels CASL Interests Tool for Evaluation Model V&V Mission for CAER-IST ...

  6. CASL Plan of Record 2 (1/11-6/11)

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

    CASL-U-2013-0273-000 Demonstration of Advanced Pin-Resolved MOC ... Distribution: To: NA Copy: NA Demonstration of Advanced Pin-Resolved MOC ...

  7. CASL-U-2015-0056-000

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

    a reduced set of user-input data. The utility produces models geared towards Pressurized-Water Reactor (PWR) rod-bundle geometry. It does this by using basic characteristics of...

  8. Screening reactor steam/water piping systems for water hammer

    SciTech Connect (OSTI)

    Griffith, P.

    1997-09-01

    A steam/water system possessing a certain combination of thermal, hydraulic and operational states, can, in certain geometries, lead to a steam bubble collapse induced water hammer. These states, operations, and geometries are identified. A procedure that can be used for identifying whether an unbuilt reactor system is prone to water hammer is proposed. For the most common water hammer, steam bubble collapse induced water hammer, six conditions must be met in order for one to occur. These are: (1) the pipe must be almost horizontal; (2) the subcooling must be greater than 20 C; (3) the L/D must be greater than 24; (4) the velocity must be low enough so that the pipe does not run full, i.e., the Froude number must be less than one; (5) there should be void nearby; (6) the pressure must be high enough so that significant damage occurs, that is the pressure should be above 10 atmospheres. Recommendations on how to avoid this kind of water hammer in both the design and the operation of the reactor system are made.

  9. (Boiling water reactor (BWR) CORA experiments)

    SciTech Connect (OSTI)

    Ott, L.J.

    1990-10-16

    To participate in the 1990 CORA Workshop at Kernforschungszentrum Karlsruhe (KfK) GmbH, Karlsruhe, FRG, on October 1--4, and to participate in detailed discussions on October 5 with the KfK CORA Boiling Water Reactor (BWR) experiments. The traveler attended the 1990 CORA Workshop at KfK, FRG. Participation included the presentation of a paper on work performed by the Boiling Water Reactor Core Melt Progression Phenomena Program at Oak Ridge National Laboratory (ORNL) on posttest analyses of CORA BWR experiments. The Statement of Work (November 1989) for the BWR Core Melt Progression Phenomena Program provides for pretest and posttest analyses of the BWR CORA experiments performed at KfK. Additionally, it is intended that ORNL personnel participate in the planning process for future CORA BWR experiments. For these purposes, meetings were held with KfK staff to discuss such topics as (1) experimental test schedule, (2) BWR test conduct, (3) perceived BWR experimental needs, and (4) KfK operational staff needs with respect to ORNL support. 19 refs.

  10. Water inventory management in condenser pool of boiling water reactor

    DOE Patents [OSTI]

    Gluntz, D.M.

    1996-03-12

    An improved system for managing the water inventory in the condenser pool of a boiling water reactor has means for raising the level of the upper surface of the condenser pool water without adding water to the isolation pool. A tank filled with water is installed in a chamber of the condenser pool. The water-filled tank contains one or more holes or openings at its lowermost periphery and is connected via piping and a passive-type valve (e.g., squib valve) to a high-pressure gas-charged pneumatic tank of appropriate volume. The valve is normally closed, but can be opened at an appropriate time following a loss-of-coolant accident. When the valve opens, high-pressure gas inside the pneumatic tank is released to flow passively through the piping to pressurize the interior of the water-filled tank. In so doing, the initial water contents of the tank are expelled through the openings, causing the water level in the condenser pool to rise. This increases the volume of water available to be boiled off by heat conducted from the passive containment cooling heat exchangers. 4 figs.

  11. Water inventory management in condenser pool of boiling water reactor

    DOE Patents [OSTI]

    Gluntz, Douglas M.

    1996-01-01

    An improved system for managing the water inventory in the condenser pool of a boiling water reactor has means for raising the level of the upper surface of the condenser pool water without adding water to the isolation pool. A tank filled with water is installed in a chamber of the condenser pool. The water-filled tank contains one or more holes or openings at its lowermost periphery and is connected via piping and a passive-type valve (e.g., squib valve) to a high-pressure gas-charged pneumatic tank of appropriate volume. The valve is normally closed, but can be opened at an appropriate time following a loss-of-coolant accident. When the valve opens, high-pressure gas inside the pneumatic tank is released to flow passively through the piping to pressurize the interior of the water-filled tank. In so doing, the initial water contents of the tank are expelled through the openings, causing the water level in the condenser pool to rise. This increases the volume of water available to be boiled off by heat conducted from the passive containment cooling heat exchangers. 4 figs.

  12. Candidate Materials Evaluation for Supercritical Water-Cooled Reactor

    SciTech Connect (OSTI)

    T. R. Allen and G. S. Was

    2008-12-12

    Final technical report on the corrosion, stress corrosion cracking, and radiation response of candidate materials for the supercritical water-cooled reactor concept.

  13. Phase 2 CASL Unlimited Access Report Outline

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

    5-0281-001 MPACT Library Verification by Comparison of Pincell Calculations to Monte Carlo Results Scott Palmtag Core Physics Inc. February 10, 2016 MPACT Pincell Calculations Consortium for Advanced Simulation of LWRs ii CASL-U-2015-0281-000 REVISION LOG Revision Date Affected Pages Revision Description 0 7/14/2015 All Initial Release 1 02/05/2016 All Major update Document pages that are: Export Controlled ________None______________________________________ IP/Proprietary/NDA

  14. Phase 2 CASL Unlimited Access Report Outline

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

    15-000 Investigation of Thermal Expansion Effects in MPACT Scott Palmtag Core Physics Inc. February 28, 2016 MPACT Thermal Expansion Consortium for Advanced Simulation of LWRs ii CASL-U-2016-1015-000 REVISION LOG Revision Date Affected Pages Revision Description 0 2/28/2016 All Initial Release Document pages that are: Export Controlled ________None______________________________________ IP/Proprietary/NDA Controlled_________None_____________________________________ Sensitive

  15. Phase 2 CASL Unlimited Access Report Outline

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

    52-000 MPACT Library Verification by Comparison of Assembly Calculations to Monte Carlo Results Scott Palmtag Core Physics Inc. March 31, 2016 MPACT Assembly Calculations Consortium for Advanced Simulation of LWRs ii CASL-U-2016-1052-000 REVISION LOG Revision Date Affected Pages Revision Description 0 03/31/2016 All Initial Release Document pages that are: Export Controlled ________None______________________________________ IP/Proprietary/NDA

  16. CASL-U-2015-0181-000

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

    1-000 Analysis of Anderson Acceleration on a Simplified Neutronics/Thermal Hydraulics System Alexander Toth and C. T. Kelley North Carolina State University Stuart Slattery, Steven Hamilton, and Kevin Clarno Oak Ridge National Laboratory April 19, 2015 CASL-U-2015-0181-000 ANS MC2015 - Joint International Conference on Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method * Nashville, Tennessee * April 19-23, 2015, on CD-ROM, American

  17. CASL-U-2015-0252-000

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

    2-000 Development of Advanced Analysis Tools for Interface Tracking Simulations Jun Fang, Igor A Bolotnov North Carolina State University July 7, 2015 CASL-U-2015-0252-000 Development of Advanced Analysis Tools for Interface Tracking Simulations Jun Fang, Dr. Igor A. Bolotnov Department of Nuclear Engineering, North Carolina State University Measurement of Lift and Drag Forces Subchannel Simulations and Computational Tools Development In order to evaluate the lift and drag forces, external

  18. CASL-U-2015-0253-000

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

    3-000 Treatment of Nucleation and Bubble Dynamics in High Heat Flux Boiling Yang Liu, Nam Dinh North Carolina State University July 7, 2015 CASL-U-2015-0253-000 TREATMENT OF NUCLEATION AND BUBBLE DYNAMICS IN HIGH HEAT FLUX BOILING Yang Liu, Department of Nuclear Engineering, North Carolina State University Instructor: Dr. Nam Dinh, Department of Nuclear Engineering, North Carolina State University Nucleate boiling is a highly efficient and desirable cooling mechanism in high- power-density

  19. Commercial Light Water Reactor Tritium Extraction Facility

    SciTech Connect (OSTI)

    McHood, M D

    2000-10-12

    A geotechnical investigation program has been completed for the Commercial Light Water Reactor - Tritium Extraction Facility (CLWR-TEF) at the Savannah River Site (SRS). The program consisted of reviewing previous geotechnical and geologic data and reports, performing subsurface field exploration, field and laboratory testing, and geologic and engineering analyses. The purpose of this investigation was to characterize the subsurface conditions for the CLWR-TEF in terms of subsurface stratigraphy and engineering properties for design and to perform selected engineering analyses. The objectives of the evaluation were to establish site-specific geologic conditions, obtain representative engineering properties of the subsurface and potential fill materials, evaluate the lateral and vertical extent of any soft zones encountered, and perform engineering analyses for slope stability, bearing capacity and settlement, and liquefaction potential. In addition, provide general recommendations for construction and earthwork.

  20. Code System for Supercritical Water Cooled Reactor LOCA Analysis.

    Energy Science and Technology Software Center (OSTI)

    1999-10-13

    Version 00 The new SCRELA code was developed to analyze the LOCA of the supercritical water cooled reactor. Since the currently available LWR codes for LOCA analysis could not analyze the significant differences in reactor characteristics between the supercritical-water cooled reactor and the current LWR, the first objective of this code development was to analyze the uniqueness of this reactor. The behavior of the supercritical water in the blowdown phase and the reflood phase ismore » modeled.« less

  1. State space modeling of reactor core in a pressurized water reactor

    SciTech Connect (OSTI)

    Ashaari, A.; Ahmad, T.; M, Wan Munirah W.; Shamsuddin, Mustaffa; Abdullah, M. Adib

    2014-07-10

    The power control system of a nuclear reactor is the key system that ensures a safe operation for a nuclear power plant. However, a mathematical model of a nuclear power plant is in the form of nonlinear process and time dependent that give very hard to be described. One of the important components of a Pressurized Water Reactor is the Reactor core. The aim of this study is to analyze the performance of power produced from a reactor core using temperature of the moderator as an input. Mathematical representation of the state space model of the reactor core control system is presented and analyzed in this paper. The data and parameters are taken from a real time VVER-type Pressurized Water Reactor and will be verified using Matlab and Simulink. Based on the simulation conducted, the results show that the temperature of the moderator plays an important role in determining the power of reactor core.

  2. A Review of Stress Corrosion Cracking/Fatigue Modeling for Light Water Reactor Cooling System Components

    Broader source: Energy.gov [DOE]

    In the United States currently there are approximately 104 operating light water reactors. Of these, 69 are pressurized water reactors (PWRs) and 35 are boiling water reactors (BWRs). In 2007, the...

  3. Process Intensification with Integrated Water-Gas-Shift Membrane Reactor |

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

    Department of Energy Intensification with Integrated Water-Gas-Shift Membrane Reactor Process Intensification with Integrated Water-Gas-Shift Membrane Reactor water-gas-shift.pdf (597.03 KB) More Documents & Publications ITP Energy Intensive Processes: Energy-Intensive Processes Portfolio: Addressing Key Energy Challenges Across U.S. Industry Energy-Intensive Processes Portfolio: Addressing Key Energy Challenges Across U.S. Industry CX-014220: Categorical Exclusion Determination

  4. CASL-U-2014-0069-001

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

    4-0069-001 Modeling an iPWR Startup Core Cycle with VERA Progress Report 2 Milestone L4:AMA.APP.P10.04 Kelly Kenner University of Tennessee - Knoxville Advisors: Ivan Maldonado, UTK Rose Montgomery, TVA Dudley Raine, B&W June 26, 2014 CASL-U-2014-0069-001 Page i Executive Summary The purpose of this report is to provide an update on the research work performed by Kelly Kenner, a Master's Candidate at the University of Tennessee's Department of Nuclear Engineering, as funded by Tennessee

  5. CASL-U-2015-0016-000

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

    6-000 Advanced Calibration and Validation of a Mechanistic Model of Subcooled Boiling Two-Phase Flow Anh Bui, Idaho National Laboratory Brian Williams, Los Alamos National Laboratory Nam Dinh, North Carolina State University April 6, 2014 CASL-U-2015-0016-000 Proceedings of ICAPP 2014 Charlotte, USA, April 6-9, 2014 Paper 14257 Advanced Calibration and Validation of a Mechanistic Model of Subcooled Boiling Two-Phase Flow Anh Bui 1 , Brian Williams 2 , Nam Dinh 3,* 1 Idaho National Laboratory

  6. CASL-U-2015-0183-000

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

    83-000 Analysis of the BEAVRS Benchmark using VERA-CS Benjamin Collins and Andrew Godfrey Oak Ridge National Laboratory April 19, 2015 CASL-U-2015-0183-000 ANS MC2015 - Joint International Conference on Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method * Nashville, TN * April 19-23, 2015, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2015) Page 1 of 11 ANALYSIS OF THE BEAVRS BENCHMARK USING VERA-CS Benjamin Collins  ,

  7. CASL-U-2015-0254-000

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

    4-000 Erosion of a Stratified Layer by a Buoyant Jet in a Large Vessel Fatih S. Sarikurt, Yassin Hassam Texas A&M University July 7, 2015 CASL-U-2015-0254-000 Erosion of a Stratified Layer by a Buoyant Jet in a Large Vessel Fatih Sinan Sarikurt, Graduate Research Assistant Dr. Yassin Hassan, Department Head and Professor of Nuclear Engineering Dimensions and Geometry The fine mesh was a polyhedral mesh with a 20 million cell count. Refinement areas were created and applied as required areas

  8. CASL-U-2015-0258-000

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

    8-000 Sensitivity Study of MOC Parameters with VERA Benchmark Cases Jipu Wang, Bill Martin University of Michigan Benjamin Collins Oak Ridge National Laboratory July 7, 2015 CASL-U-2015-0258-000 Sensitivity Study of MOC Parameters with VERA Benchmark Cases Jipu Wang 1 (jipuwang@umich.edu) , Benjamin Collins 1,2 (collinsbs@ornl.gov), Bill Martin 1 (wrm@umich.edu) 1 Department of Nuclear Engineering and Radiological Sciences University of Michigan, Ann Arbor, MI 48109 2 Oak Ridge National

  9. CASL Plan of Record 2 (1/11-6/11)

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

    1 Thermal Hydraulic Validation Report CASL Mile Stone: L3:AMA.VAL.P4.02 Authors: J. Yan, P. Yuan, Y. Xu, Zeses Karoutas Westinghouse Electric Company Emilio Popov, Sreekanth Pannala, Alan Stagg Oak Ridge National Lab Scott Lucas, Hongbin Zhang Idaho National Lab Robert Brewster, Emilio Baglietto CD-Adapco Elvis Dominguez-Ontiveros, Yassin Hassan Texas A&M March 2012 CASL-8-2012-0037-000 <Document Name> ii CASL-8-2012-0037-000 Please complete sections appropriate for this record. a)

  10. Advanced dry head-end reprocessing of light water reactor spent...

    Office of Scientific and Technical Information (OSTI)

    reprocessing of light water reactor spent nuclear fuel Citation Details In-Document Search Title: Advanced dry head-end reprocessing of light water reactor spent nuclear fuel ...

  11. CHARACTERIZATION OF RADIOACTIVITY IN THE REACTOR VESSEL OF THE HEAVY WATER COMPONENT TEST REACTOR

    SciTech Connect (OSTI)

    Vinson, Dennis

    2010-06-01

    The Heavy Water Component Test Reactor (HWCTR) facility is a pressurized heavy water reactor that was used to test candidate fuel designs for heavy water power reactors. The reactor operated at nominal power of 50 MW{sub th}. The reactor coolant loop operated at 1200 psig and 250 C. Two isolated test loop were designed into the reactor to provide special test conditions. Fig. 1 shows a cut-away view of the reactor. The two loops are contained in four inch diameter stainless steel piping. The HWCTR was operated for only a short duration, from March 1962 to December 1964 in order to test the viability of test fuel elements and other reactor components for use in a heavy water power reactor. The reactor achieved 13,882 MWd of total power while testing 36 different fuel assemblies. In the course of operation, HWCTR experienced the cladding failures of 10 separate test fuel assemblies. In each case, the cladding was breached with some release of fuel core material into the isolated test loop, causing fission product and actinide contamination in the main coolant loop and the liquid and boiling test loops. Despite the contribution of the contamination from the failed fuel, the primary source of radioactivity in the HWCTR vessel and internals is the activation products in the thermal shields, and to a lesser degree, activation products in the reactor vessel walls and liner. A detailed facility characterization report of the HWCTR facility was completed in 1996. Many of the inputs and assumptions in the 1996 characterization report were derived from the HWCTR decommissioning plan published in 1975. The current paper provides an updated assessment of the radioisotopic characteristics of the HWCTR vessel and internals to support decommissioning activities on the facility.

  12. Stress and Fracture Mechanics Analyses of Boiling Water Reactor and Pressurized Water Reactor Pressure Vessel Nozzles

    SciTech Connect (OSTI)

    Yin, Shengjun; Bass, Bennett Richard; Stevens, Gary; Kirk, Mark

    2011-01-01

    This paper describes stress analysis and fracture mechanics work performed to assess boiling water reactor (BWR) and pressurized water reactor (PWR) nozzles located in the reactor pressure vessel (RPV) adjacent to the core beltline region. Various RPV nozzle geometries were investigated: 1. BWR recirculation outlet nozzle; 2. BWR core spray nozzle3 3. PWR inlet nozzle; ; 4. PWR outlet nozzle; and 5. BWR partial penetration instrument nozzle. The above nozzle designs were selected based on their proximity to the core beltline region, i.e., those nozzle configurations that are located close enough to the core region such that they may receive sufficient fluence prior to end-of-license (EOL) to require evaluation as part of establishing the allowed limits on heatup, cooldown, and hydrotest (leak test) conditions. These nozzles analyzed represent one each of the nozzle types potentially requiring evaluation. The purpose of the analyses performed on these nozzle designs was as follows: To model and understand differences in pressure and thermal stress results using a two-dimensional (2-D) axi-symmetric finite element model (FEM) versus a three-dimensional (3-D) FEM for all nozzle types. In particular, the ovalization (stress concentration) effect of two intersecting cylinders, which is typical of RPV nozzle configurations, was investigated; To verify the accuracy of a selected linear elastic fracture mechanics (LEFM) hand solution for stress intensity factor for a postulated nozzle corner crack for both thermal and pressure loading for all nozzle types; To assess the significance of attached piping loads on the stresses in the nozzle corner region; and To assess the significance of applying pressure on the crack face with respect to the stress intensity factor for a postulated nozzle corner crack.

  13. Improving Light Water Reactor Fuel Reliability Via Flow-Induced...

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

    Improving Light Water Reactor Fuel Reliability Via Flow-Indu... Failures of the fuel rod elements used to power U.S. nuclear ... and a recognized bottleneck to optimal fuel utilization. ...

  14. Process for treating effluent from a supercritical water oxidation reactor

    DOE Patents [OSTI]

    Barnes, C.M.; Shapiro, C.

    1997-11-25

    A method for treating a gaseous effluent from a supercritical water oxidation reactor containing entrained solids is provided comprising the steps of expanding the gas/solids effluent from a first to a second lower pressure at a temperature at which no liquid condenses; separating the solids from the gas effluent; neutralizing the effluent to remove any acid gases; condensing the effluent; and retaining the purified effluent to the supercritical water oxidation reactor. 6 figs.

  15. Process Intensification with Integrated Water-Gas-Shift Membrane Reactor

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

    Intensification with Integrated Water-Gas-Shift Membrane Reactor Hydrogen-Selective Membranes for High- Pressure Hydrogen Separation This project will develop hydrogen-selective membranes for an innovative water-gas-shift reactor that improves gas separation effciency, enabling reduced energy use and greenhouse gas emissions. Introduction The goal of process intensifcation is to reduce the equipment footprint, energy consumption, and environmental impact of manufacturing processes. One candidate

  16. Process for treating effluent from a supercritical water oxidation reactor

    DOE Patents [OSTI]

    Barnes, Charles M.; Shapiro, Carolyn

    1997-01-01

    A method for treating a gaseous effluent from a supercritical water oxidation reactor containing entrained solids is provided comprising the steps of expanding the gas/solids effluent from a first to a second lower pressure at a temperature at which no liquid condenses; separating the solids from the gas effluent; neutralizing the effluent to remove any acid gases; condensing the effluent; and retaining the purified effluent to the supercritical water oxidation reactor.

  17. CASL-U-2015-0155-000 VERA Core Simulator

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

    March 29, 2015 CASL-U-2015-0155-000 ANS MC2015 - Joint International Conference on Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte ...

  18. CASL-U-2015-0154-000 I

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

    4-000 I 2 s-LWR Fuel Management Option for an 18-Month Cycle Length D. Salazar, F. ... CASL-U-2015-0154-000 Advances in Nuclear Fuel Management V (ANFM 2015) Hilton Head ...

  19. CASL-U-2015-0151-000 SMR Fuel Cycle

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

    1-000 SMR Fuel Cycle Optimization and Control Rod Depletion Using NESTLE and LWROPT Keith ... CASL-U-2015-0151-000 Advances in Nuclear Fuel Management V (ANFM 2015) Hilton Head ...

  20. CASL-U-2015-0083-000 VERA Configure,

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

    83-000 VERA Configure, Build, Test, and Install Quick Reference Guide Roscoe A. Bartlett Oak Ridge National Laboratory April 17, 2015 CASL-U-2015-0083-000 VERA Configure, Build,...

  1. CASL Milestone L2.AMA.P7.02

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

    of LWRs Fe CASL-U-2013-0196-000 Demonstration of Neutronics Coupled to ... of Milestone L2:AMA.P7.02 - Demonstration of Neutronics Coupled to ...

  2. CASL Milestone L2.VRI.P7.02

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

    Roger Initial Demonstration of Peregrine in VERA-CS Consortium for Advanced Simulation of LWRs i CASL-U-2013-0165-000 Fe Initial Demonstration of Peregrine in VERA-CS R. Pawlowski ...

  3. Effects of Water Radiolysis in Water Cooled Reactors, NERI Proposal No.99-0010. Technical progress report

    SciTech Connect (OSTI)

    Pimblott, S.M.

    2000-04-01

    OAK B188 Effects of Water Radiolysis in Water Cooled Reactors, NERI Proposal No.99-0010. Technical progress report

  4. Practical combinations of light-water reactors and fast reactors for future actinide transmutation

    SciTech Connect (OSTI)

    Collins, Emory D.; Renier, John-Paul

    2007-07-01

    Multicycle partitioning-transmutation (P-T) studies continue to show that use of existing light-water reactors (LWRs) and new advanced light-water reactors (ALWRs) can effectively transmute transuranic (TRU) actinides, enabling initiation of full actinide recycle much earlier than waiting for the development and deployment of sufficient fast reactor (FR) capacity. The combination of initial P-T cycles using LWRs/ALWRs in parallel with economic improvements to FR usage for electricity production, and a follow-on transition period in which FRs are deployed, is a practical approach to near-term closure of the nuclear fuel cycle with full actinide recycle. (authors)

  5. CASL Plan of Record 2 (1/11-6/11)

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

    Analysis of Two-Dimensional Lattice Physics Verification Problems with MPACT Andrew Godfrey, ORNL Fausto Franceschini, Westinghouse Electric Company LLC Scott Palmtag, Core Physics Julie Stout, ORNL Advanced Modeling Applications December 21, 2012 CASL-U-2012-0172-000 Analysis of 2D Lattice Physics Verification Problems with MPACT CASL-U-2012-0172-000 ii Consortium for Advanced Simulation of LWRs REVISION LOG Revision Date Affected Pages Revision Description 0 12/21/2012 All Original Issue

  6. CASL Plan of Record 2 (1/11-6/11)

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

    MPACT Testing and Benchmarking Results March 31, 2014 Andrew T. Godfrey Physics Integration Oak Ridge National Laboratory CASL-U-2014-0045-000 MPACT Testing and Benchmarking Consortium for Advanced Simulation of LWRs ii CASL-U-2014-0045-000 REVISION LOG Revision Date Affected Pages Revision Description 0 3/31/2014 All Original Release Document pages that are: Export Controlled __None_______________________________________________ IP/Proprietary/NDA

  7. CASL-U-2015-0175-000 VPSC

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

    5-000 VPSC Implementation in BISON-CASL Code for Modeling Large Deformation Problems Wenfeng Liu ANATECH Corporation Robert Montgomery Pacific Northwest National Laboratory Carlos Tomé and Chris Stanek Los Alamos National Laboratory Jason Hales Idaho National Laboratory April 19, 2015 CASL-U-2015-0175-000 ANS MC2015 - Joint International Conference on Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method * Nashville, TN * April

  8. CASL-U-2016-1030-000 Development

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

    Consortium for Advanced Simulation of LWRs CASL-U-2016-1030-000 Development and Testing of CTF to Support Modeling of BWR Operating Conditions Robert Salko, Oak Ridge National Laboratory Aaron Wysocki, Oak Ridge National Laboratory Benjamin Collins, Oak Ridge National Laboratory Andrew Godfrey, Oak Ridge National Laboratory Chris Gosdin, Pennsylvania State University Maria Avramova, North Carolina State University 01/29/2016 CASL-U-2016-1030-000 Page ii REVISION LOG Revision Date Affected Pages

  9. Microsoft Word - CASL-U-2015-0265-000

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

    CASL-U-2015-0265-000 Initial BWR Modeling Capability for MPACT Brendan Kochunas Daniel Jabaay Andrew Fitzgerald Thomas Downar University of Michigan Scott Palmtag Core Physics, Inc. July 31, 2015 BWR Capability for MPACT Consortium for Advanced Simulation of LWRs ii CASL-U-2015-0265-000 REVISION LOG Revision Date Affected Pages Revision Description 0 7/31/2015 All Initial version Document pages that are: Export Controlled _________________None_________________________________ IP/Proprietary/NDA

  10. Deployment Scenario of Heavy Water Cooled Thorium Breeder Reactor

    SciTech Connect (OSTI)

    Mardiansah, Deby; Takaki, Naoyuki

    2010-06-22

    Deployment scenario of heavy water cooled thorium breeder reactor has been studied. We have assumed to use plutonium and thorium oxide fuel in water cooled reactor to produce {sup 233}U which will be used in thorium breeder reactor. The objective is to analysis the potential of water cooled Th-Pu reactor for replacing all of current LWRs especially in Japan. In this paper, the standard Pressurize Water Reactor (PWR) has been designed to produce 3423 MWt; (i) Th-Pu PWR, (ii) Th-Pu HWR (MFR = 1.0) and (iii) Th-Pu HWR (MFR 1.2). The properties and performance of the core were investigated by using cell and core calculation code. Th-Pu PWR or HWR produces {sup 233}U to introduce thorium breeder reactor. The result showed that to replace all (60 GWe) LWR by thorium breeder reactor within a period of one century, Th-Pu oxide fueled PWR has insufficient capability to produce necessary amount of {sup 233}U and Th-Pu oxide fueled HWR has almost enough potential to produce {sup 233}U but shows positive void reactivity coefficient.

  11. Light Water Reactor Sustainability Accomplishments Report

    SciTech Connect (OSTI)

    McCarthy, Kathryn A.

    2015-02-01

    Welcome to the 2014 Light Water Reactor Sustainability (LWRS) Program Accomplishments Report, covering research and development highlights from 2014. The LWRS Program is a U.S. Department of Energy research and development program to inform and support the long-term operation of our nation’s commercial nuclear power plants. The research uses the unique facilities and capabilities at the Department of Energy national laboratories in collaboration with industry, academia, and international partners. Extending the operating lifetimes of current plants is essential to supporting our nation’s base load energy infrastructure, as well as reaching the Administration’s goal of reducing greenhouse gas emissions to 80% below 1990 levels by the year 2050. The purpose of the LWRS Program is to provide technical results for plant owners to make informed decisions on long-term operation and subsequent license renewal, reducing the uncertainty, and therefore the risk, associated with those decisions. In January 2013, 104 nuclear power plants operated in 31 states. However, since then, five plants have been shut down (several due to economic reasons), with additional shutdowns under consideration. The LWRS Program aims to minimize the number of plants that are shut down, with R&D that supports long-term operation both directly (via data that is needed for subsequent license renewal), as well indirectly (with models and technology that provide economic benefits). The LWRS Program continues to work closely with the Electric Power Research Institute (EPRI) to ensure that the body of information needed to support SLR decisions and actions is available in a timely manner. This report covers selected highlights from the three research pathways in the LWRS Program: Materials Aging and Degradation, Risk-Informed Safety Margin Characterization, and Advanced Instrumentation, Information, and Control Systems Technologies, as well as a look-ahead at planned activities for 2015. If you

  12. Advanced Pellet Cladding Interaction Modeling Using the US DOE CASL Fuel Performance Code: Peregrine

    SciTech Connect (OSTI)

    Jason Hales; Various

    2014-06-01

    The US DOEs Consortium for Advanced Simulation of LWRs (CASL) program has undertaken an effort to enhance and develop modeling and simulation tools for a virtual reactor application, including high fidelity neutronics, fluid flow/thermal hydraulics, and fuel and material behavior. The fuel performance analysis efforts aim to provide 3-dimensional capabilities for single and multiple rods to assess safety margins and the impact of plant operation and fuel rod design on the fuel thermomechanical- chemical behavior, including Pellet-Cladding Interaction (PCI) failures and CRUD-Induced Localized Corrosion (CILC) failures in PWRs. [1-3] The CASL fuel performance code, Peregrine, is an engineering scale code that is built upon the MOOSE/ELK/FOX computational FEM framework, which is also common to the fuel modeling framework, BISON [4,5]. Peregrine uses both 2-D and 3-D geometric fuel rod representations and contains a materials properties and fuel behavior model library for the UO2 and Zircaloy system common to PWR fuel derived from both open literature sources and the FALCON code [6]. The primary purpose of Peregrine is to accurately calculate the thermal, mechanical, and chemical processes active throughout a single fuel rod during operation in a reactor, for both steady state and off-normal conditions.

  13. CASL-8-2015-0103-000 Multi-Phase Flow: Direct Numerical Simulation

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

    of Notre Dame July 8-10, 2013 CASL-U-2015-0103-000 Multi-Phase Flow: Direct ... Laboratories, July 9-10, 2013 CASL-U-2015-0103-000 Multi-Phase Flow: Direct ...

  14. Feasibility study on the thorium fueled boiling water breeder reactor

    SciTech Connect (OSTI)

    PetrusTakaki, N.

    2012-07-01

    The feasibility of (Th,U)O 2 fueled, boiling water breeder reactor based on conventional BWR technology has been studied. In order to determine the potential use of water cooled thorium reactor as a competitive breeder, this study evaluated criticality, breeding and void reactivity coefficient in response to changes made in MFR and fissile enrichments. The result of the study shows that while using light water as moderator, low moderator to fuel volume ratio (MFR=0.5), it was possible to breed fissile fuel in negative void reactivity condition. However the burnup value was lower than the value of the current LWR. On the other hand, heavy water cooled reactor shows relatively wider feasible breeding region, which lead into possibility of designing a core having better neutronic and economic performance than light water with negative void reactivity coefficient. (authors)

  15. SLIDESHOW: Secretary Moniz Visits Oak Ridge National Laboratory...

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

    Energy Secretary Moniz at CASL 1 of 25 Energy Secretary Moniz at CASL Secretary Moniz tours the Consortium for Advanced Simulation of Light Water Reactors (CASL) facility at Oak ...

  16. Advantages of liquid fluoride thorium reactor in comparison with light water reactor

    SciTech Connect (OSTI)

    Bahri, Che Nor Aniza Che Zainul Majid, Amran Ab.; Al-Areqi, Wadeeah M.

    2015-04-29

    Liquid Fluoride Thorium Reactor (LFTR) is an innovative design for the thermal breeder reactor that has important potential benefits over the traditional reactor design. LFTR is fluoride based liquid fuel, that use the thorium dissolved in salt mixture of lithium fluoride and beryllium fluoride. Therefore, LFTR technology is fundamentally different from the solid fuel technology currently in use. Although the traditional nuclear reactor technology has been proven, it has perceptual problems with safety and nuclear waste products. The aim of this paper is to discuss the potential advantages of LFTR in three aspects such as safety, fuel efficiency and nuclear waste as an alternative energy generator in the future. Comparisons between LFTR and Light Water Reactor (LWR), on general principles of fuel cycle, resource availability, radiotoxicity and nuclear weapon proliferation shall be elaborated.

  17. Advanced Computational Thermal Fluid Physics (CTFP) and Its Assessment for Light Water Reactors and Supercritical Reactors

    SciTech Connect (OSTI)

    D.M. McEligot; K. G. Condie; G. E. McCreery; H. M. McIlroy; R. J. Pink; L.E. Hochreiter; J.D. Jackson; R.H. Pletcher; B.L. Smith; P. Vukoslavcevic; J.M. Wallace; J.Y. Yoo; J.S. Lee; S.T. Ro; S.O. Park

    2005-10-01

    Background: The ultimate goal of the study is the improvement of predictive methods for safety analyses and design of Generation IV reactor systems such as supercritical water reactors (SCWR) for higher efficiency, improved performance and operation, design simplification, enhanced safety and reduced waste and cost. The objective of this Korean / US / laboratory / university collaboration of coupled fundamental computational and experimental studies is to develop the supporting knowledge needed for improved predictive techniques for use in the technology development of Generation IV reactor concepts and their passive safety systems. The present study emphasizes SCWR concepts in the Generation IV program.

  18. Heavy Water Components Test Reactor Decommissioning - Major Component Removal

    SciTech Connect (OSTI)

    Austin, W.; Brinkley, D.

    2010-05-05

    The Heavy Water Components Test Reactor (HWCTR) facility (Figure 1) was built in 1961, operated from 1962 to 1964, and is located in the northwest quadrant of the Savannah River Site (SRS) approximately three miles from the site boundary. The HWCTR facility is on high, well-drained ground, about 30 meters above the water table. The HWCTR was a pressurized heavy water test reactor used to develop candidate fuel designs for heavy water power reactors. It was not a defense-related facility like the materials production reactors at SRS. The reactor was moderated with heavy water and was rated at 50 megawatts thermal power. In December of 1964, operations were terminated and the facility was placed in a standby condition as a result of the decision by the U.S. Atomic Energy Commission to redirect research and development work on heavy water power reactors to reactors cooled with organic materials. For about one year, site personnel maintained the facility in a standby status, and then retired the reactor in place. In 1965, fuel assemblies were removed, systems that contained heavy water were drained, fluid piping systems were drained, deenergized and disconnected and the spent fuel basin was drained and dried. The doors of the reactor facility were shut and it wasn't until 10 years later that decommissioning plans were considered and ultimately postponed due to budget constraints. In the early 1990s, DOE began planning to decommission HWCTR again. Yet, in the face of new budget constraints, DOE deferred dismantlement and placed HWCTR in an extended surveillance and maintenance mode. The doors of the reactor facility were welded shut to protect workers and discourage intruders. The $1.6 billion allocation from the American Recovery and Reinvestment Act to SRS for site clean up at SRS has opened the doors to the HWCTR again - this time for final decommissioning. During the lifetime of HWCTR, 36 different fuel assemblies were tested in the facility. Ten of these

  19. Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Initial Assessment of Thermal Annealing Needs and Challenges

    Broader source: Energy.gov [DOE]

    The most life-limiting structural component in light-water reactors (LWR) is the reactor pressure vessel (RPV) because replacement of the RPV is not considered a viable option at this time. LWR...

  20. CASL-U-2015-0123-000 Tom Downar

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

    the LWR-PROTEUS project-an extended validation program for advanced light water reactor core analysis tools conducted at the Paul Scherrer Institute-the radial, internal...

  1. Advanced Nuclear Technology: Advanced Light Water Reactors Utility Requirements Document Small Modular Reactors Inclusion Summary

    SciTech Connect (OSTI)

    Loflin, Leonard; McRimmon, Beth

    2014-12-18

    This report summarizes a project by EPRI to include requirements for small modular light water reactors (smLWR) into the EPRI Utility Requirements Document (URD) for Advanced Light Water Reactors. The project was jointly funded by EPRI and the U.S. Department of Energy (DOE). The report covers the scope and content of the URD, the process used to revise the URD to include smLWR requirements, a summary of the major changes to the URD to include smLWR, and how to use the URD as revised to achieve value on new plant projects.

  2. Self-Sustaining Thorium Boiling Water Reactors

    SciTech Connect (OSTI)

    Greenspan, Ehud; Gorman, Phillip M.; Bogetic, Sandra; Seifried, Jeffrey E.; Zhang, Guanheng; Varela, Christopher R.; Fratoni, Massimiliano; Vijic, Jasmina J.; Downar, Thomas; Hall, Andrew; Ward, Andrew; Jarrett, Michael; Wysocki, Aaron; Xu, Yunlin; Kazimi, Mujid; Shirvan, Koroush; Mieloszyk, Alexander; Todosow, Michael; Brown, Nicolas; Cheng, Lap

    2015-03-15

    The primary objectives of this project are to: Perform a pre-conceptual design of a core for an alternative to the Hitachi proposed fuel-self- sustaining RBWR-AC, to be referred to as a RBWR-Th. The use of thorium fuel is expected to assure negative void coefficient of reactivity (versus positive of the RBWR-AC) and improve reactor safety; Perform a pre-conceptual design of an alternative core to the Hitachi proposed LWR TRU transmuting RBWR-TB2, to be referred to as the RBWR-TR. In addition to improved safety, use of thorium for the fertile fuel is expected to improve the TRU transmutation effectiveness; Compare the RBWR-Th and RBWR-TR performance against that of the Hitachi RBWR core designs and sodium cooled fast reactor counterparts - the ARR and ABR; and, Perform a viability assessment of the thorium-based RBWR design concepts to be identified along with their associated fuel cycle, a technology gap analysis, and a technology development roadmap. A description of the work performed and of the results obtained is provided in this Overview Report and, in more detail, in the Attachments. The major findings of the study are summarized.

  3. High-Temperature Water-Gas Shift Membrane Reactor Study

    SciTech Connect (OSTI)

    Ciocco, M.V.; Iyoha, O.; Enick, R.M.; Killmeyer, R.P.

    2007-06-01

    NETL’s Office of Research and Development is exploring the integration of membrane reactors into coal gasification plants as a way of increasing efficiency and reducing costs. Water-Gas Shift Reaction experiments were conducted in membrane reactors at conditions similar to those encountered at the outlet of a coal gasifier. The changes in reactant conversion and product selectivity due to the removal of hydrogen via the membrane reactor were quantified. Research was conducted to determine the influence of residence time and H2S on CO conversion in both Pd and Pd80wt%Cu membrane reactors. Effects of the hydrogen sulfide-to-hydrogen ratio on palladium and a palladium-copper alloy at high-temperature were also investigated. These results were compared to thermodynamic calculations for the stability of palladium sulfides.

  4. Development of 1000 MWe Advanced Boiling Water Reactor

    SciTech Connect (OSTI)

    Kazuo Hisajima; Ken Uchida; Keiji Matsumoto; Koichi Kondo; Shigeki Yokoyama; Takuya Miyagawa [Toshiba Corporation (Japan)

    2006-07-01

    1000 MWe Advanced Boiling Water Reactor has only two main steam lines and six reactor internal pumps, whereas 1350 MWe ABWR has four main steam lines and ten reactor internal pumps. In order to confirm how the differences affect hydrodynamic conditions in the dome and lower plenum of the reactor pressure vessel, fluid analyses have been performed. The results indicate that there is not substantial difference between 1000 MWe ABWR and 1350 MWe ABWR. The primary containment vessel of the ABWR consists of the drywell and suppression chamber. The suppression chamber stores water to suppress pressure increase in the primary containment vessel and to be used as the source of water for the emergency core cooling system following a loss-of-coolant accident. Because the reactor pressure vessel of 1000 MWe ABWR is smaller than that of 1350 MWe ABWR, there is room to reduce the size of the primary containment vessel. It has been confirmed feasible to reduce inner diameter of the primary containment vessel from 29 m of 1350 MWe ABWR to 26.5 m. From an economic viewpoint, a shorter outage that results in higher availability of the plant is preferable. In order to achieve 20-day outage that results in 97% of availability, improvement of the systems for removal of decay heat is introduced that enables to stop all the safety-related decay heat removal systems except at the beginning of an outage. (authors)

  5. Fuel Summary Report: Shippingport Light Water Breeder Reactor - Rev. 2

    SciTech Connect (OSTI)

    Olson, Gail Lynn; Mc Cardell, Richard Keith; Illum, Douglas Brent

    2002-09-01

    The Shippingport Light Water Breeder Reactor (LWBR) was developed by Bettis Atomic Power Laboratory to demonstrate the potential of a water-cooled, thorium oxide fuel cycle breeder reactor. The LWBR core operated from 1977-82 without major incident. The fuel and fuel components suffered minimal damage during operation, and the reactor testing was deemed successful. Extensive destructive and nondestructive postirradiation examinations confirmed that the fuel was in good condition with minimal amounts of cladding deformities and fuel pellet cracks. Fuel was placed in wet storage upon arrival at the Expended Core Facility, then dried and sent to the Idaho Nuclear Technology and Engineering Center for underground dry storage. It is likely that the fuel remains in good condition at its current underground dry storage location at the Idaho Nuclear Technology and Engineering Center. Reports show no indication of damage to the core associated with shipping, loading, or storage.

  6. Assessment of light water reactor accident management programs and experience

    SciTech Connect (OSTI)

    Hammersley, R.J.

    1992-03-01

    The objective of this report is to provide an assessment of the current light water reactor experience regarding accident management programs and associated technology developments. This assessment for light water reactor (LWR) designs is provided as a resource and reference for the development of accident management capabilities for the production reactors at the Savannah River Site. The specific objectives of this assessment are as follows: 1. Perform a review of the NRC, utility, and industry (NUMARC, EPRI) accident management programs and implementation experience. 2. Provide an assessment of the problems and opportunities in developing an accident management program in conjunction or following the Individual Plant Examination process. 3. Review current NRC, utility, and industry technological developments in the areas of computational tools, severe accident predictive tools, diagnostic aids, and severe accident training and simulation.

  7. METHOD OF OPERATING A HEAVY WATER MODERATED REACTOR

    DOE Patents [OSTI]

    Vernon, H.C.

    1962-08-14

    A method of removing fission products from the heavy water used in a slurry type nuclear reactor is described. According to the process the slurry is steam distilled with carbon tetrachloride so that at least a part of the heavy water and carbon tetrachloride are vaporized; the heavy water and carbon tetrachloride are separated; the carbon tetrachloride is returned to the steam distillation column at different points in the column to aid in depositing the slurry particles at the bottom of the column; and the heavy water portion of the condensate is purified. (AEC)

  8. Integrity of the reactor coolant boundary of the European pressurized water reactor (EPR)

    SciTech Connect (OSTI)

    Goetsch, D.; Bieniussa, K.; Schulz, H.; Jalouneix, J.

    1997-04-01

    This paper is an abstract of the work performed in the frame of the development of the IPSN/GRS approach in view of the EPR conceptual safety features. EPR is a pressurized water reactor which will be based on the experience gained by utilities and designers in France and in Germany. The reactor coolant boundary of a PWR includes the reactor pressure vessel (RPV), those parts of the steam generators (SGs) which contain primary coolant, the pressurizer (PSR), the reactor coolant pumps (RCPs), the main coolant lines (MCLs) with their branches as well as the other connecting pipes and all branching pipes including the second isolation valves. The present work covering the integrity of the reactor coolant boundary is mainly restricted to the integrity of the main coolant lines (MCLs) and reflects the design requirements for the main components of the reactor coolant boundary. In the following the conceptual aspects, i.e. design, manufacture, construction and operation, will be assessed. A main aspect is the definition of break postulates regarding overall safety implications.

  9. CASL Plan of Record 2 (1/11-6/11)

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

    VERA Requirements Document (VRD) - Revision 1 Stephen M. Hess AMA Focus Area 30 March 2012 CASL-U-2011-0074-002 VERA Technical Requirements by Component Consortium for Advanced Simulation of LWRs ii CASL-U-2011-0074-002 REVISION LOG Revision Date Affected Pages Revision Description 0 2/25/2011 All Original Version 1 3/31/2012 Revision 1 1A 4/19/2012 all Revision 1A (Mario) Document pages that are: Export Controlled _______________None__________________________________ IP/Proprietary/NDA

  10. CASL Plan of Record 2 (1/11-6/11)

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

    IC Workflow Project: Final Report Andrew Godfrey Advanced Modeling Applications Oak Ridge National Laboratory March 30 th , 2012 godfreyat@ornl.gov CASL-U-2011-0236-002 IC Workflow Project Final Report Consortium for Advanced Simulation of LWRs i CASL-U-2011-0236-002 REVISION LOG Revision Date Affected Pages Revision Description 0 12/31/2011 All Original Draft Report 1 1/25/2012 All Minor Revision 2 3/30/2012 All Include data from Phase 2 Document pages that are: Export Controlled