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W.F. Swinson

Bio: W.F. Swinson is an academic researcher from Oak Ridge National Laboratory. The author has contributed to research in topics: Neutron source & Secondary stress. The author has an hindex of 4, co-authored 11 publications receiving 42 citations.

Papers
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ReportDOI
01 May 1993
TL;DR: The planned Advanced Neutron Source (ANS) as mentioned in this paper will use closely spaced arrays of involute-shaped fuel plates that will be cooled by water flowing through the channels between the plates, and there is concern that at certain coolant flow velocities, adjacent plates may deflect and touch, with resulting failure of the plates.
Abstract: The planned reactor for the Advanced Neutron Source (ANS) will use closely spaced arrays of involute-shaped fuel plates that will be cooled by water flowing through the channels between the plates There is concern that at certain coolant flow velocities, adjacent plates may deflect and touch, with resulting failure of the plates Experiments have been conducted at the Oak Ridge National Laboratory to examine this potential phenomenon Results of the experiments and comparison with analytical predictions are reported The tests were conducted using full-scale epoxy plate models of the aluminum/uranium silicide ANS involute-shaped fuel plates Use of epoxy plates and model theory allowed lower flow velocities and pressures to explore the potential failure mechanism Plate deflections and channel pressures as functions of the flow velocity are examined Comparisons with mathematical models are noted

12 citations

ReportDOI
01 Nov 1993
TL;DR: In this paper, two sets of tests were performed on the upper and lower fuel plates for the structural response of the fuel plates to the required high coolant flow velocities.
Abstract: The reactor for the planned Advanced Neutron Source uses closely spaced plates cooled by heavy water flowing through narrow channels. Two sets of tests were performed on the upper and lower fuel plates for the structural response of the fuel plates to the required high coolant flow velocities. This report contains the data from the second round of tests. Results and conclusions from all of the tests are also included in this report. The tests were done using light water on full-scale epoxy models, and through model theory, the results were related to the prototype plates, which are aluminum-clad aluminum/uranium silicide involute-shaped plates.

11 citations

Journal ArticleDOI
TL;DR: In this article, an experimental-analytical solution to this problem for design purposes has been developed and is presented and is used in the design of a nuclear power plant with a single-input single-output (SISO) system.
Abstract: In some reactors, thin fuel plates are cooled by water flowing through thin channels on either side of the plates. There is a need to know the amount of deformation in the fuel plates due to the coolant flow so that failures can be avoided. A verifiable solution to this problem in the past has not been available. An experimental-analytical solution to this problem for design purposes has been developed and is herein presented.

6 citations

ReportDOI
01 Sep 1994
TL;DR: In this paper, the elastic structural response of the Advanced Neutron Source (ANS) fuel plates to coolant flow and temperature variations is evaluated for a representative plate from the upper and from lower fuel elements.
Abstract: Procedures for evaluating the elastic structural response of the Advanced Neutron Source (ANS) fuel plates to coolant flow and to temperature variations are presented in this report. Calculations are made that predict the maximum deflection and the maximum stress for a representative plate from the upper and from the lower fuel elements.

6 citations

ReportDOI
01 Aug 1995
TL;DR: In this paper, experimental flow tests and analyses to evaluate the structural response of circular arc plates have been conducted, and the results are given in this report, as well as a detailed discussion of the structural properties of these plates.
Abstract: The thin fuel plates planned for the Advanced Neutron Source are to be cooled by forcing heavy water at high velocity, 25 m/s, through thin cooling channels on each side of each plate. Because the potential for structural failure of the plates is a design concern, considerable effort has been expended in assessing this potential. As part of this effort, experimental flow tests and analyses to evaluate the structural response of circular arc plates have been conducted, and the results are given in this report.

3 citations


Cited by
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Journal ArticleDOI
TL;DR: In this article, the authors developed a fluid-structure interaction methodology to investigate numerically the onset of hydroelastic instability of flat-shell-type fuel elements under axial flow conditions.

22 citations

Book ChapterDOI
01 Jan 2016
TL;DR: In this article, wave propagation in plates in unconfined and confined axial flows, their dynamics and stability: infinitely long and wide plates, plate of finite length, and plates of finite width and length.
Abstract: This chapter covers wave propagation in plates in unconfined and confined axial flows, their dynamics and stability: infinitely long and wide plates, plates of finite length, and plates of finite width and length. The dynamics for different boundary conditions is discussed, the effect of damping, nonlinear effects, absolute and convective instabilities for unconfined plates and plates in channels. The dynamics of travelling plates and parallel-plate systems is also discussed. Special attention is paid to the dynamics and stability of cantilevered plates, foils, strips, tapes, and flags. Flapping-plate propulsion and energy harvesting are discussed at the end of the chapter.

13 citations

01 Dec 1995
TL;DR: In this article, an alternative core design utilizing low-enriched uranium (LEU, <20%) silicide fuel with 4.8 g/cm{sup 3} that provides nearly the same neutron flux for experiments as the HEU design, but has a less favorable fuel cycle economy.
Abstract: The FRM-II reactor design of the Technical University of Munich has a compact core that utilizes fuel plates containing highly-enriched uranium (HEU, 93%). This paper presents an alternative core design utilizing low-enriched uranium (LEU, <20%) silicide fuel with 4.8 g/cm{sup 3} that provides nearly the same neutron flux for experiments as the HEU design, but has a less favorable fuel cycle economy. If an LEU fuel with a uranium density of 6.0 - 6.5 g/cm{sup 3} were developed, the alternative design would provide the same neutron flux and use the same number of cores per year as the HEU design. The results of this study show that there are attractive possibilities for using LEU fuel instead of HEU fuel in the FRM-II. Further optimization of the LEU design and near-term availability of LEU fuel with a uranium density greater than 4.8 g/cm{sup 3} would enhance the performance of the LEU core. The RERTR Program is ready to exchange information with the Technical University of Munich to resolve any differences that may exist and to identify design modifications that would optimize reactor performance utilizing LEU fuel.

11 citations

Journal Article
TL;DR: The low-enriched uranium (LEU) design proposed by the Reduced Enrichment Research and Test Reactor (RERTR) Program at Argonne National Laboratory (ANL) has a compact core consisting of a single fuel element that uses LEU (<20%) silicide fuel with 4.5 g U/cm{sup 3} and operates at 32 MW as discussed by the authors.
Abstract: The alternative low-enriched uranium (LEU) design for the; FRM-II proposed by the Reduced Enrichment Research and Test Reactor (RERTR) Program at Argonne National Laboratory (ANL) has a compact core consisting of a single fuel element that uses LEU (<20%) silicide fuel with 4.5 g U/cm{sup 3} and operates at 32 MW. Both the high-enriched uranium (HEU) (93%) design by the Technical University of Munich (TUM) and the LEU design have the same fuel lifetime (50 days) and the same neutron flux performance (8 X 10{sup 14} n/cm{sup 2}{center_dot}s in the reflector). Computer models for the HEU and LEU designs have been exchanged between TUM and ANL, and discrepancies have been resolved.

9 citations