ANS 19.10


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methods for determining neutron fluence in BWR and PWR pressure vessel andreactor internals
2009 Edition, 2009
Includes all amendments and changes through Reaffirmation Notice , 2016

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  • Revision:2009 Edition, 2009
  • Published Date:October 11, 2016
  • Status:Active, Most Current
  • Document Language:English
  • Published By:American Nuclear Society (ANS)
  • Page Count:14
  • ANSI Approved:Yes
  • DoD Adopted:No
  • Scope, purpose, and application

    This standard provides a procedure for the evaluation of the best-estimate fast (E > 1.0 MeV) neutron f luence in the annular region between the core and the inside surface of the vessel, through the pressure vessel and the reactor cavity, between the top and bottom of the active fuel given the neutron source in the core. This evaluation employs both fast neutron flux computations and measurement data from invessel and cavity dosimetry, as appropriate. The standard applies to both U.S.-designed pressurized water reactors ~PWRs! and boiling water reactors (BWRs)