Historical

ANSI/ANS-19.10-2009 (R2016)

Methods for Determining Neutron Fluence in BWR and PWR Pressure Vessel and Reactor Internals

This standard provides a procedure for the evaluation of the best-estimate fast (E > 1.0 MeV) neutron fluence 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 bot-tom of the active fuel given the neutron source in the core. This evaluation employs both fast neutron flux computations and measurement data from in-vessel and cavity dosimetry, as appropriate. The standard applies to both U.S.-designed pressurized water reactors (PWRs) and boiling water reactors (BWRs).

CONTENT PROVIDER
American National Standards Institute [ansi]

Others Also Bought
Steady-state Neutronics Methods for Power Reactor Analysis
Nuclear Data Sets for Reactor Design Calculations
The Determination of Thermal Energy Deposition Rates in Nuclear Reactors
Included in Packages
This standard is not included in any packages.
Document History
Amendments & Corrections
We have no amendments or corrections for this standard.