Gas-Cooled Reactor Project Quarterly Progress Report: June 1960

One of 14 reports in the title: Gas-Cooled Reactor Project Progress Report available on this site.

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Description

Report documenting ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Project. Design Investigations: The effects on the power distribuestablished. A mathematical model was developed for studying shifting of the coolant stream as it moves along a rod in order to predict the temperatures of the parallel streams as they progress through the reactor. A fuelelement life code developed for computing the internal temperature structure, the amount of fission gas released, the internal pressure, the cladding strain when the internal pressure exceeds the coolant pressure, and the creep damage was used for comparing top-loading and inventedloading fuel ... continued below

Physical Description

xxiv, 255 p.

Creation Information

Oak Ridge National Laboratory August 22, 1960.

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Titles

  • Main Title: Gas-Cooled Reactor Project Quarterly Progress Report: June 1960
  • Serial Title: Gas-Cooled Reactor Project Progress Report
  • Added Title: Gas-Cooled Reactor Project Quarterly Progress Report for Period Ending June 30, 1960

Description

Report documenting ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Project. Design Investigations: The effects on the power distribuestablished. A mathematical model was developed for studying shifting of the coolant stream as it moves along a rod in order to predict the temperatures of the parallel streams as they progress through the reactor. A fuelelement life code developed for computing the internal temperature structure, the amount of fission gas released, the internal pressure, the cladding strain when the internal pressure exceeds the coolant pressure, and the creep damage was used for comparing top-loading and inventedloading fuel programs for the EGCR. A statistical method was developed for estimating the probability that the hot spot on the EGCR fuel element will exceed a given temperature. A method of cooling the EGCR control rods was developed that will minimize diversion of coolant flow through leakage paths between graphite blocks. A preliminary design of a control rod cooled by this method was developed. Means for reducing the thermal stresses in the top head nozzles of the EGCR pressure vessel were studied. The stresses in the graphite sleeves of the EGCR fuel elements were calculated, and the maximum stress was found to be within the allowable limit. A study was made of the thermal stresses in the EGCR pressure-vessel support skirt, and a satisfactory design was developed. Procedures for removing ruthenium and cerium contamination from steel were outlined and incorporated in procedures for decontaminating the EGCR charge and service machines. Experimental information was obtained on the thermal characteristics of the specified EGCR fuel cluster. The effect of relative orientation of adjacent clusters on the heattransfer distribution in the downstream element was studied by means of mass-removal measurements on naphthalene-coated reds. Velocity distributions in the downstream element of two adjacent EGCR-type clusters were determined with Title I H-bar, Title II cylindrical, and Title II conical spiders at various relative orientations. Also contained in this report was a report of Materials Research and Testing:. (For preceding period see ORNL-2929.) (W.D.M.)

Physical Description

xxiv, 255 p.

Notes

NTIS

Orig. Receipt Date: 31-DEC-60

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Identifier

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  • Report No.: ORNL-2964
  • Grant Number: W-7405-ENG-26
  • DOI: 10.2172/4138453 | External Link
  • Office of Scientific & Technical Information Report Number: 4138453
  • OCLC: 727187066 | External Link
  • SuDoc Number: E 1.99:ORNL-2964
  • Archival Resource Key: ark:/67531/metadc871408

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Creation Date

  • August 22, 1960

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Added to The UNT Digital Library

  • Sept. 16, 2016, 12:32 a.m.

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  • Nov. 29, 2016, 3:18 p.m.

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Oak Ridge National Laboratory. Gas-Cooled Reactor Project Quarterly Progress Report: June 1960, report, August 22, 1960; Oak Ridge, Tennessee. (digital.library.unt.edu/ark:/67531/metadc871408/: accessed August 16, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.