FAST FLUX TEST FACILITY CONCEPTUAL COMPONENT DESIGN DISCRIPTION FOR THE REACTOR NUCLEAR CONTROL COMPONENTS No. 33

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This document describes the nuclear control component of the Fast Test Reactor (FTR) . The Fast Test Reactor is t he central test bed of the Fast Flux Test Facility (FFTF). The Reactor Nuclear Control Components described in this document consist of neutron absorbing elements which are moved axially into and out of the general area of the active portion of the core. The electromechanical drive housings are mounted on the reactor cover and are part of the pressure boundary of the vessel and cover during reactor operation. Drive lines (extension shafts) extend through the cover and are connected to ... continued below

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Creator: Unknown. October 1, 1969.

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Description

This document describes the nuclear control component of the Fast Test Reactor (FTR) . The Fast Test Reactor is t he central test bed of the Fast Flux Test Facility (FFTF). The Reactor Nuclear Control Components described in this document consist of neutron absorbing elements which are moved axially into and out of the general area of the active portion of the core. The electromechanical drive housings are mounted on the reactor cover and are part of the pressure boundary of the vessel and cover during reactor operation. Drive lines (extension shafts) extend through the cover and are connected to the poison element. The element is guided in the core throughout its travel by a flow duct which resides in the c or e grid plate receptacle. Sodium coolant from the primary loop is used to cool the neutron absorbing rods. This Conceptual Component Design Description (CCDD) suppor t s and expands the requirements of the Overall Conceptual Systems Design Description . Specifically , it establishes the reactor nuclear control design requirements; describes the current reference design of this control; defines safety, operational · and maintenance principles; indicates unresolved problems ; and identifies the principal interfaces affecting the reactor control component functional requirements and design configuration. Included are functions and design requirements, a physical description of the system, safety considerations, principles of operation, and maintenance principles.

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  • Report No.: BNWL-500 Vol 33
  • Grant Number: AT(45-1)-1830
  • DOI: 10.2172/1088310 | External Link
  • Office of Scientific & Technical Information Report Number: 1088310
  • Archival Resource Key: ark:/67531/metadc834908

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  • October 1, 1969

Added to The UNT Digital Library

  • May 19, 2016, 9:45 a.m.

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  • Sept. 22, 2016, 2:07 p.m.

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FAST FLUX TEST FACILITY CONCEPTUAL COMPONENT DESIGN DISCRIPTION FOR THE REACTOR NUCLEAR CONTROL COMPONENTS No. 33, report, October 1, 1969; Richland, Washington. (https://digital.library.unt.edu/ark:/67531/metadc834908/: accessed May 24, 2019), University of North Texas Libraries, Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.