Analysis of Stresses and Deflections in Top Support Grid, PWR Reactor. Final Report

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The top grid of the PWR reactor core assembly is treated as a simply supported circular plate. The theory of plate is applied to the grid umder mechanical loads. The thermal stress problem is analyzed by treating the plate as under combined action of a laterally distributed load and forces in the middle plane of the plate. The load distribution is calculated from the temperature variation over the grid. The thermal stress problem then is equivalent to two problems: one, of bendimg of plate; and, the other, a plane stress problem. The theoretical formulation for plates under nonuniform heating is ... continued below

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Pages: 88

Creation Information

Yen, T. C. & Vining, R. E., Jr. June 1, 1957.

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Description

The top grid of the PWR reactor core assembly is treated as a simply supported circular plate. The theory of plate is applied to the grid umder mechanical loads. The thermal stress problem is analyzed by treating the plate as under combined action of a laterally distributed load and forces in the middle plane of the plate. The load distribution is calculated from the temperature variation over the grid. The thermal stress problem then is equivalent to two problems: one, of bendimg of plate; and, the other, a plane stress problem. The theoretical formulation for plates under nonuniform heating is developed by neglecting the effect of uneven expansion in the direction perpendicular to the plane of the plate. In replacing the partial dffferential equations by difference equations, the latter are modified to take into account the change in tbickmess and spacing of the grid webs near the boundary. Twentythree difference equations for the twenty-three stations in one octant of the grid are obtained for each second order partial differential equation. The difference equations are solved by assuming that the twisting moments and shearing stresses in the plane of the grid vanish at the boundary. The stresses and deflections due to mechanical loads and thermal expansion are then superposed. (auth)

Physical Description

Pages: 88

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  • Other Information: For Westinghouse Electric Corp. Bettis Plant. Orig. Receipt Date: 31-DEC-58

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  • Report No.: AECU-3629
  • Report No.: F-A1971
  • Grant Number: SUBCONTRACT NO. 73-(14-476)
  • DOI: 10.2172/4311757 | External Link
  • Office of Scientific & Technical Information Report Number: 4311757
  • Archival Resource Key: ark:/67531/metadc1016814

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • June 1, 1957

Added to The UNT Digital Library

  • Oct. 15, 2017, 10:09 p.m.

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  • Jan. 8, 2018, 12:35 a.m.

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Yen, T. C. & Vining, R. E., Jr. Analysis of Stresses and Deflections in Top Support Grid, PWR Reactor. Final Report, report, June 1, 1957; Philadelphia, Pennsylvania. (digital.library.unt.edu/ark:/67531/metadc1016814/: accessed August 17, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.