Design and proposed utilization of the Sandia Annular Core Research Reactor (ACRR) Metadata

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  • Main Title Design and proposed utilization of the Sandia Annular Core Research Reactor (ACRR)


  • Author: Walker, J.V.
    Creator Type: Personal
  • Author: Reuscher, J.A.
    Creator Type: Personal
  • Author: Pickard, P.S.
    Creator Type: Personal


  • Name: Sandia Laboratories
    Place of Publication: Albuquerque, New Mexico
    Additional Info: Sandia Labs., Albuquerque, NM (USA)


  • Creation: 1979-01-01


  • English


  • Content Description: The Sandia ACRR became operational in 1978 and currently serves as the major in-pile fast reactor safety test facility for the US Nuclear Regulatory Commission. The ACRR is an upgrade of the Annular Core Pulse Reactor (ACPR) with the installation of a new flexible control system and a core of uniquely designed BeO-UO/sub 2/ fuel elements for increasing the neutron fluence in the experiment cavity. The reactor is now capable of driving multi-pin advanced reactor test fuel into vapor with a pulse width of 5 msec. In the steady state mode, the reactor can simulate post accident decay heat at prototypic levels in fission heated debris beds up to 10 cm in diameter. A number of programmed operating modes including high power square waves, ramps and pulses can produce a multitude of power profiles in order to simulate the power histories in the various accident scenarios. The reactor capabilities and the reactor safety research test program are discussed.
  • Physical Description: Pages: 12


  • Keyword: Research And Test Reactors
  • Keyword: Homogeneous Reactors
  • Keyword: Water Moderated Reactors 220600* -- Nuclear Reactor Technology-- Research, Test & Experimental Reactors
  • Keyword: Specifications
  • Keyword: Hydride Moderated Reactors
  • Keyword: Reactor Kinetics
  • Keyword: Kinetics
  • Keyword: Solid Homogeneous Reactors
  • Keyword: Mixed Spectrum Reactors
  • Keyword: Enriched Uranium Reactors
  • Keyword: Acpr Reactor
  • Keyword: Pulsed Reactors
  • Keyword: Water Cooled Reactors
  • Keyword: Reactors
  • STI Subject Categories: 21 Specific Nuclear Reactors And Associated Plants
  • Keyword: Research Reactors


  • Conference: International meeting on fast reactor safety technology, Seattle, WA, USA, 19 Aug 1979


  • Name: Office of Scientific & Technical Information Technical Reports
    Code: OSTI


  • Name: UNT Libraries Government Documents Department
    Code: UNTGD

Resource Type

  • Article


  • Text


  • Report No.: SAND-79-1646C
  • Report No.: CONF-790816-53
  • Grant Number: EY-76-C-04-0789
  • Office of Scientific & Technical Information Report Number: 6117577
  • Archival Resource Key: ark:/67531/metadc1109795


  • Display Note: Dep. NTIS, PC A02/MF A01.