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Nuclear excursions in aqueous solutions of fissile materialsSmith, Adrienne Bobbette, 1960- January 1989 (has links)
Fissile materials in the form of aqueous homogeneous solutions are used during the chemical processing of nuclear materials. In this form there exists the possibility of an accidental criticality. A one-dimensional multi-region model was developed for simulating fast power excursions in a cylinderical homogeneous aqueous fissile solution. The model includes a novel method for computing reactivity feedback that accounts for the axial distribution of power and solution density. The feedback method is based on the change in neutron leakage due to a change in solution density. The model also includes an equation of state derived from quasi-static thermodynamic theory for a solution containing gas bubbles. The model was compared to the KEWB-5 (Kinetic Experiments on Water Boilers) series of experiments. The model could approximate the values of peak power and pressure found in the experiments, but the pressure curves did not match the shapes of the experimental pressure traces.
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Fuel pin optimization for a metal fueled light water reactorMarsh, Robert 12 1900 (has links)
No description available.
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Theory of cladding breach location and size determination using delayed neutron signals /Reece, Warren Daniel 08 1900 (has links)
No description available.
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Denatured breeder with extended burnup fuel cycleBencheikh, Allaoua 08 1900 (has links)
No description available.
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An optimal withdrawal policy for spent nuclear fuel from on-site storage /Swindle, David Wesley, January 1977 (has links)
Thesis (M.S.)--Virginia Polytechnic Institute and State University, 1977. / Vita. Abstract. Includes bibliographical references (leaves 122-124). Also available via the Internet.
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Evaluation of a technique for the remote measurement of surface temperature distributions in laser heated samplesAyling, Joanna R. January 1996 (has links)
No description available.
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Transition from uranium to denatured uranium/thorium fuel in an existing PWR /Walters, M. Audeen. January 1982 (has links)
No description available.
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A nuclear reactor performance and fuel management simulator for power system planning activities /Henderson, Ronald R. January 1971 (has links)
No description available.
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Comparison of Reprocessing Methods for Light Water Reactor FuelChandler, Sharon (Jess) Ann 20 November 2006 (has links)
Currently, the United States is investigating methods to close the nuclear fuel cycle
and increase the use of nuclear power for electricity and cogeneration applications. Congress has called for and held hearings in an attempt to determine an appropriate path forward for reprocessing of nuclear fuel. However, each current proposed method presents a different
set of attributes with regards to: Complexity, safety, wastes, and proliferation risks.
This thesis provides a decision analysis methodology for approaching the reprocessing
issue. The presented methodology builds on the previous work done in the 1970s. Further,
current reprocessing technologies which are capable of processing the oxide fuels utilized
in the majority of United States reactors are evaluated across ten attributes related to
reprocessing performance. A weighted total score is provided for each reprocessing method
in order to separate the technological from political or emotional issues related to selection of a process.
While it is not the goal of this thesis to select a particular best technology, application of this methodology results in the selection of the COmbined EXtraction (COEX) technology when equal weighting is put on the attributes as defined. It is unlikely that a decision maker will approach this decision with equal weighting; however, actual decision maker weightings are known only to the decision makers. By altering the weightings, different technologies are selected.
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PERFORMANCE CONSIDERATIONS OF NUCLEAR REACTOR ACTINIDE RECYCLE AS A WASTE MANAGEMENT ALTERNATIVEMurphy, Daniel John, 1944- January 1978 (has links)
No description available.
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