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

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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 ... continued below

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Pages: 12

Creation Information

Walker, J.V.; Reuscher, J.A. & Pickard, P.S. January 1, 1979.

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This article is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 15 times , with 5 in the last month . More information about this article can be viewed below.

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

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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

Notes

Dep. NTIS, PC A02/MF A01.

Source

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

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  • 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

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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Creation Date

  • January 1, 1979

Added to The UNT Digital Library

  • Feb. 22, 2018, 7:45 p.m.

Description Last Updated

  • March 11, 2019, 3:44 p.m.

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Walker, J.V.; Reuscher, J.A. & Pickard, P.S. Design and proposed utilization of the Sandia Annular Core Research Reactor (ACRR), article, January 1, 1979; Albuquerque, New Mexico. (https://digital.library.unt.edu/ark:/67531/metadc1109795/: accessed March 20, 2019), University of North Texas Libraries, Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.