ANS 19.10-2009 (R2021) PDF

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).

ANSI :	ANSI Approved
File Size :	1 file , 360 KB
Note :	This product is unavailable in Ukraine, Russia, Belarus
Number of Pages :	14
Published :	02/24/2009