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Method for Preparation of High Specific Activity Reactor-Produced Lutetium-177 Method for Preparation of High Specific Activity Reactor-Produced Lutetium-177 Disclosure Number 200101033 Technology Summary The subject invention disclosed herein is a method for preparing high specific activity lutetium-177 comprising the indirect production of Lutetium-1…

: Fact Cards
: Lutetium, Reactors, Reactor...

Numerical calculation of the global and local components of the neutron noise field in BWR's NUMERICAL CALCULATION OF THE GLOBAL AND LOCAL, COMPONENTS OF THE NEUTRON NOISE FIELD IN BWR's* F. C. Difilippo1 P. J. Otaduy2 Oak Ridge National Laboratory Oak Ridge, Tennessee 37830 *Re^earch. sponsored by the Department of Energy under contract "with tmioa Carbide Corporation. * Consultant, Nucl…

Method for Dissipating Decay Heat in Nuclear Reactors During an Extended Blackout Method for Dissipating Decay Heat in Nuclear Reactors During an Extended Blackout Disclosure Number 201303060 Technology Summary When a nuclear reactor experiences a blackout, no power is available to run the cooling pumps. Even with the reactor shut down, there is a large amount…

: Fact Cards
: Reactors, Reactor, Heat...

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…

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 …

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 …

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…

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…

SensorNet: Fixed Installations Disclosure Number 200201121 Technology Summary This invention provides rapid quantitative detection of airborne radiological, chemical and biological hazards at public and/or secure installations (embassies, sports facilities). Inventor WORLEY, BRIAN A Computational Sciences & Engineering Div Licensing Contact SIMS, DAVID…

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 …

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