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Under-Prediction of Localized Tally Uncertainties in Monte Carlo Eigenvalue Calculations Brenden Mervin, Scott Mosher, John Wagner, Ivan Maldonado The University of Tennessee, Department of Nuclear Engineering, 310 Pasqua Engineering Building, Knoxville, TN 37996 Oak Ridge National Laboratory, Nuclear Science and Technology Division, PO BOX 2008, Oak Ridge, TN 37831 INTRODUCTI…

ENHS : the encapsulated nuclear heat source - a nuclear energy concept for emerging worldwide energy markets. ICONE Conference Paper American Society of Mechanical Engineers (ASME) owns all copyright and publication subject to this requirement: Verbatim reproduction of this paper by anyone will be permitted by ASME provided appropriate credit is given to the author(s) and ASME. 1 …

The Encapsulated Nuclear Heat Source for Proliferation-Resistant Low-Waste Nuclear Energy Approved for public release; further dissemination unlimited Preprint UCRL-JC-143186 The Encapsulated Nuclear Heat Source for Proliferation-Resistant Low-Waste Nuclear Energy N. Brown, M. Carelli, L. Conway, M. Dzodzo, E. Greenspan, Q. Hossain, D. Saphier, H. Shimada, J. Sienicki, and D. Wade This …

The Secure, Transportable, Autonomous Reactor System UCRL-JC-134396 PREPRINT The Secure, Transportable, Autonomous Reactor System N.W. Brown, J.A. Hassberger, C. Smith, M. Carelli, E. Greenspan, KL. Peddicord, K. Stroh, D.C. Wade and R.N. Hill This paper was prepared for submittal to the American Nuclear Society International Conference on Future Nuclear Systems Jackson Hole, WY August …

Metal fire implications for advanced reactors. Part 1, literature review. SANDIA REPORT SAND2007-6332 Unlimited Release October 2007 Metal Fire Implications for Advanced Reactors, Part 1: Literature Review Tara J. Olivier, Ross F. Radel, Steven P. Nowlen, Thomas K. Blanchat, & John C. Hewson Prepared by Sandia National Laboratories Albuquerque, N…

Sodium fast reactor safety and licensing research plan. Volume II. SANDIA REPORT SAND2012-4259 Unlimited Release Printed May 2012 Sodium Fast Reactor Safety and Licensing Research Plan Volume II J. LaChance, J. Sackett, R. Wigeland, R. Bari, R. Budnitz, J. Cahalen, C. Grandy, D. Wade, M. Corradini, R. Denning, G. Flanagan, S. Wright, A. Suo-Anttila, J. Hewson, …

Next Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTs) Volume 2: Accident and Thermal Fluids Analysis PIRTs NUREG/CR-6944, Vol. 2 ORNL/TM-2007/147, Vol. 2 Next Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTs) Volume 2: Accident and Thermal Fluids Analysis PIRTs OAK RIDGE NATIONAL LABORATORY …

A unified Monte Carlo approach to fast neutron cross section data evaluation. NUCLEAR DATA AND MEASUREMENT SERIES ANL/NDM-166 A Unified Monte Carlo Approach to Fast Neutron Cross Section Data Evaluation Donald L. Smith January 2008 NUCLEAR ENGINEERING DIVISION ARGONNE NATIONAL LABORATORY 9700 SOUTH CASS AVENUE ARGONNE, ILLINOIS 60439, U.S.A. 1 About Argonne National Laboratory Argonne is a U.S. D…

The INL is a U.S. Department of Energy National Laboratory operated by Battelle Energy Alliance INL/EXT-12-27066 Revision 0 Verification and Validation Strategy for LWRS Tools Carl Stoots, Tom Larson, Richard Schultz, Hans Gougar, Kathryn McCarthy, and David Petti (INL); Laura Swiler (Sandia); Michael Corradini (U. of Wisc) September 2012 DISCLAIMER This information was pre…

Next Generation Nuclear Plant Methods Research and Development Technical Program Plan -- PLN-2498 The INL is a U.S. Department of Energy National Laboratory operated by Battelle Energy Alliance INL/EXT-06-11804 PLN-2498 Rev. 1 Next Generation Nuclear Plant Methods Research and Development Technical Program Plan September 2008 INL/EXT-06-11804 PLN-2498 Rev. 1 Next Generation…

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