Thermal Transient Behavior of the Neutron Sensor of a Reactor Safety Device

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Description

The thermal transient behavior of the fuse component of a reactor safety device has been investigated in the KEWB I reactor. The fuse is a neutron flux sensor which, at excessive flux levels, will trip the safety device and cause reactor shutdown. Experimental results on the majority of reactor transients were in good ngreement with calculations. However, on the fastest transients, experimental results were obscured by spurious effects during those intervals when the radiation level was high. lt was not possible to demonstrate reactor shutdown with the safety devices because the inherent shutdown mechanism of the KEWB reactor was too ... continued below

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Pages: 24

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Fitch, S. H. & Springer, T. H. June 1, 1958.

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Description

The thermal transient behavior of the fuse component of a reactor safety device has been investigated in the KEWB I reactor. The fuse is a neutron flux sensor which, at excessive flux levels, will trip the safety device and cause reactor shutdown. Experimental results on the majority of reactor transients were in good ngreement with calculations. However, on the fastest transients, experimental results were obscured by spurious effects during those intervals when the radiation level was high. lt was not possible to demonstrate reactor shutdown with the safety devices because the inherent shutdown mechanism of the KEWB reactor was too efficient. The integrated neutron flux levels attained with the fastest traasients were insufficient to cause the fuse to trip starting from ambient temperatures. Nevertheless, those tests have shown that the fuse component design is adequate for the high power level reactors for which it is intended. A successful trial run was made to demonstrate fuse tripping on transient neutron flux by heating the fuse to about 20 deg C above ambient temperature prior to the beginning of the transient. (auth)

Physical Description

Pages: 24

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NTIS

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  • Other Information: Orig. Receipt Date: 31-DEC-58

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  • Report No.: NAA-SR-2689
  • Grant Number: AT-11-1-GEN-8
  • DOI: 10.2172/4321499 | External Link
  • Office of Scientific & Technical Information Report Number: 4321499
  • Archival Resource Key: ark:/67531/metadc1018291

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Office of Scientific & Technical Information Technical Reports

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Creation Date

  • June 1, 1958

Added to The UNT Digital Library

  • Oct. 15, 2017, 10:09 p.m.

Description Last Updated

  • Jan. 22, 2018, 11:27 a.m.

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Fitch, S. H. & Springer, T. H. Thermal Transient Behavior of the Neutron Sensor of a Reactor Safety Device, report, June 1, 1958; Canoga Park, California. (digital.library.unt.edu/ark:/67531/metadc1018291/: accessed October 18, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.