Bettis Atomic Power Laboratory is a U.S. Government-owned research and development facility operated by Bechtel Marine Propulsion Corporation and located in the Pittsburgh suburb of West Mifflin, Pennsylvania. It solely focuses on the design and development of nuclear power for the U.S. Navy and was one of the leaders in creating the "nuclear navy". The laboratory was founded in 1949 on the site of the former Bettis Field and is named after Cyrus Bettis. It covers approximately 207 acres and is operated for the Department of Energy by Bechtel Marine Propulsion Corporation, a wholly owned subsidiary of the Bechtel Corporation. Bechtel won the contract to run the laboratory on September 19, 2008 and assumed operation on February 1, 2009; Prior to that the Lab was operated by another Bechtel subsidiary, Bechtel Bettis, Inc. From the Lab's founding until 1998, it was run by Westinghouse Electric Corporation.The laboratory's work is part of the Naval Nuclear Propulsion Program, which is a joint U.S Navy-DOE program responsible for the research, design, construction, operation and maintenance of U.S. nuclear-powered warships.The laboratory developed Oak Ridge National Laboratory's original design of the pressurized water reactor for operational naval use. It built the nuclear propulsion plants for the first U.S. nuclear submarines and surface ships including the USS Nautilus , the USS George Washington , the USS Long Beach , and the USS Enterprise .Westinghouse's Nuclear Power Division adapted the PWR design for commercial use and built the first commercial nuclear power plant in the United States, the Shippingport Power Plant in the west hills of Pittsburgh.The laboratory has two computers listed on the 26th TOP500 List of supercomputers in the world. Ranked 97 is a 1,090 processor Opteron system and ranked 405 is a 536 processor Itanium 2 system.The laboratory is also home to the U.S. Navy's Bettis Reactor Engineering School. The school provides a post-graduate certificate program in Nuclear Engineering with a focus on nuclear reactor design, construction, and operations. It is open only to Naval personnel and Bettis engineers.The laboratory had been chosen to develop the Project Prometheus nuclear power source for the JIMO project, however, funding for this program was cancelled in the fall of 2005. Wikipedia.
Bockwoldt T.S.,Naval Reactors |
Munsick G.A.,Bettis Atomic Power Laboratory
Journal of Mechanical Design, Transactions of the ASME | Year: 2013
In the textbook by Wahl (1963, Mechanical Springs, 2nd ed., McGraw-Hill, New York, Chap. 20), he derived an equation predicting the diametral growth of a helical spring as the spring is compressed from free to solid height, and the spring's ends are free to rotate. A recent comparison with test data for growth of compression springs revealed that the calculated growth predicted by the Wahl formula did not agree well with measured values. Review of the Wahl derivation uncovered an arithmetic error that, when corrected, brought the calculated and measured diameters into closer agreement. The corrected diametral growth equation presented herein bounds the original data provided by Wahl, better matches an alternate growth equation derived by Ancker and Goodier for most springs evaluated, predicts larger growth than the original Wahl equation, and is a better fit to recent measured data. Copyright © 2013 by ASME.
Pounders J.M.,Georgia Institute of Technology |
Pounders J.M.,Bettis Atomic Power Laboratory |
Rahnemat F.,Georgia Institute of Technology
Nuclear Science and Engineering | Year: 2014
A new solution technique is derived for the time-dependent transport equation. This approach extends the steady-state coarse-mesh transport method that is based on global-local decompositions of large (i.e.,full-core) neutron transport problems. The new method is based on polynomial expansions of the space, angle, and time variables in a response-based formulation of the transport equation. The local problem (coarse-mesh) solutions, which are entirely decoupled from each other, are characterized by space-, angle-, and time-dependent response functions. These response functions are, in turn, used to couple an arbitrary sequence of local problems to form the solution of a much larger global problem. In the current work, the local problem (response function) computations are performed using the Monte Carlo method, while the global (coupling) problem is solved deterministically. The spatial coupling is performed by orthogonal polynomial expansions of the partial currents on the local problem surfaces, and similarly, the time-dependent response of the system (i.e., the time-varying flux) is computed by convolving the time-dependent surface partial currents and time-dependent volumetric sources against precomputed time-dependent response kernels.
Hall Jr. M.M.,Bettis Atomic Power Laboratory |
Flinn J.E.,Argonne National Laboratory
Journal of Nuclear Materials | Year: 2010
Irradiation creep constitutive equations, which were developed in Part I, are used here to analyze in-reactor creep and swelling data obtained ca. 1977-1979 as part of the US breeder reactor program. The equations were developed according to the principles of incremental continuum plasticity for the purpose of analyzing data obtained from a novel irradiation experiment that was conducted, in part, using Type 304 stainless steel that had been previously irradiated to significant levels of void swelling. Analyses of these data support an earlier observation that all stress states, whether tensile, compressive, shear or mixed, can affect both void swelling and interactions between irradiation creep and swelling. The data were obtained using a set of five unique multiaxial creep-test specimens that were designed and used for the first time in this study. The data analyses demonstrate that the constitutive equations derived in Part I provide an excellent phenomenological representation of the interactive creep and swelling phenomena. These equations provide nuclear power reactor designers and analysts with a first-of-its-kind structural analysis tool for evaluating irradiation damage-dependent distortion of complex structural components having gradients in neutron damage rate, temperature and stress state.
Kimball K.J.,Knolls Atomic Power Laboratory |
Clementoni E.M.,Bettis Atomic Power Laboratory
Proceedings of the ASME Turbo Expo | Year: 2012
The Knolls Atomic Power Laboratory (KAPL) and Bettis Atomic Power Laboratory are testing a supercritical carbon dioxide (S-CO2) Brayton power cycle system. The 100 kWe Integrated System Test (IST) is a two shaft recuperated closed Brayton cycle with a variable speed turbine driven compressor and a constant speed turbine driven generator using S-CO2 as the working fluid. The IST was designed to demonstrate operational, control and performance characteristics of an S-CO2 Brayton power cycle over a wide range of conditions. The IST design includes a comprehensive instrumentation and control system incorporating results of turbomachinery operational testing performed at Barber Nichols Inc (BNI) in the Sandia National Laboratory's DOE test loop. A detailed dynamic performance model was used both to predict IST performance and to evaluate the testing completed at BNI. The IST construction was completed in mid 2011 and is currently undergoing shakedown testing. Results of testing completed to date and future testing plans will be summarized. Copyright © 2012 by ASME.
Schubring D.,University of Florida |
Schubring D.,University of Wisconsin - Madison |
Ashwood A.C.,University of Wisconsin - Madison |
Ashwood A.C.,National Renewable Energy Laboratory |
And 2 more authors.
International Journal of Multiphase Flow | Year: 2010
Most approaches to the modeling of annular flow require information regarding the thin liquid film surrounding the central gas core. This film is hypothesized to present a rough surface to the gas core, enhancing interfacial shear and pressure loss, with the roughness closely linked to the height of the film. This height is typically obtained from conductance probe measurements. The present work used planar laser-induced fluorescence to provide direct visualization of the liquid film in upward vertical air-water annular flow. Images were processed to produce the distribution of film heights. The standard deviation and average film thickness are found to be an increasing function of liquid flow and a decreasing function of gas flow, with the standard deviation approaching 0.4 times the average at sufficient liquid flow. © 2010 Elsevier Ltd.