Investigation of Local Boiling of SM-1

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Description

Abstract; SM-1 Reactor Core I Rearranged and Spiked, and Core II with Special Components were analyzed under various off-design conditions to induce nucleate boiling. The steady state code, STDY-3, written for the thermal analysis of pressurized water cores, was employed for the analysis. The code performs a complete steady state parallel channel thermal analysis for both nominal and hot channels. Thermal characteristics of individual elements were investigated while changing the parameters of primary pressure or inlet temperature to introduce the phenomenon of nucleate boiling in the the core. Reduction of system pressures to 1000, 800, and 600 psia and increasing … continued below

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xiii, 62 pages ; illustrations.

Creation Information

Bradley, P. L. June 20, 1961.

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Description

Abstract; SM-1 Reactor Core I Rearranged and Spiked, and Core II with Special Components were analyzed under various off-design conditions to induce nucleate boiling. The steady state code, STDY-3, written for the thermal analysis of pressurized water cores, was employed for the analysis. The code performs a complete steady state parallel channel thermal analysis for both nominal and hot channels. Thermal characteristics of individual elements were investigated while changing the parameters of primary pressure or inlet temperature to introduce the phenomenon of nucleate boiling in the the core. Reduction of system pressures to 1000, 800, and 600 psia and increasing core inlet temperatures to 465 and 500 degree F were studied as the means to induce boiling in the core. This analysis indicates that SM-1 Core I Rearranged and Spiked can be safely operated at the reduced pressure of 910 psia without introducing extensive boiling in the core. SM-1 Core II with Special Components can be operated at 800 psia or at an inlet temperature of 500 degree F at 1200 psia.

Physical Description

xiii, 62 pages ; illustrations.

Notes

Digitized from microopaque cards.

Contract No. AT(30-1)-2639 with the U.S. Atomic Energy Commission, New York Operations Office.

Includes bibliographic references (page A-17).

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  • Report No.: APAE-88
  • Grant Number: AT(30-1)-2639
  • SuDoc Number: Y 3.AT 7:22/APAE-88
  • Accession or Local Control No: metadc1201984
  • Archival Resource Key: ark:/67531/metadc1201984

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Technical Report Archive and Image Library

The Technical Report Archive & Image Library (TRAIL) identifies, acquires, catalogs, digitizes and provides unrestricted access to U.S. government agency technical reports. The mission of TRAIL is to ensure preservation, discoverability, and persistent open access to government technical publications regardless of form or format.

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Imaged from microcard, these technical reports describe research performed for U.S. government agencies from the 1930s to the 1960s. The reports were provided by the Technical Report Archive and Image Library (TRAIL).

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Creation Date

  • June 20, 1961

Added to The UNT Digital Library

  • Aug. 15, 2019, 10:26 p.m.

Description Last Updated

  • Jan. 5, 2022, 7:26 p.m.

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Bradley, P. L. Investigation of Local Boiling of SM-1, report, June 20, 1961; Schenectady, New York.. (https://digital.library.unt.edu/ark:/67531/metadc1201984/: accessed October 8, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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