Home > NRC Library > ADAMS Public Documents

Forwards "Evaluation of Induced Neutron Flux Error for B&W Reactors," in response to util 810420 submittal.DNB & ctr fuel melt limits at facility are not exceeded because of errors.

Accession Number: ML20042C675

Date Released: Friday, October 25, 2024

Package Contents

The following links on this page are to Adobe Portable Document Format (PDF) files. To obtain a free viewer for displaying this format, see our Plugins, Viewers, and Other Tools.

• ML20052D652 - Forwards "Evaluation of Induced Neutron Flux Error for B&W Reactors," in response to util 810420 submittal.DNB & ctr fuel melt limits at facility are not exceeded because of errors. (3 page(s), 4/21/1982)
• ML20042C674 - "Evaluation of Induced Neutron Flux Error for B&W Reactors." (7 page(s), 4/13/1982)