Customer Service:
Mon - Fri: 8:30 am - 6 pm EST
Back
Standards PDF Cover Page

 Most recent

ANSI/ANS-19.10-2009 (R2021)

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).

Available for Subscriptions

Content Provider
American National Standards Institute [ansi]

Document History
Revises:
Included in Packages
This standard is not included in any packages.
Amendments & Corrections
We have no amendments or corrections for this standard.
ANSI Logo

As the voice of the U.S. standards and conformity assessment system, the American National Standards Institute (ANSI) empowers its members and constituents to strengthen the U.S. marketplace position in the global economy while helping to assure the safety and health of consumers and the protection of the environment.

Useful Links
CUSTOMER SERVICE
NEW YORK OFFICE
ANSI HEADQUARTERS
2024 © American National Standards Institute (ANSI) All Rights Reserved.