Published December 1984 | Version v1
Report Restricted

System Analysis Handbook

Description

This handbook provides simple procedures for calculating the behavior of light water reactors during a variety of incidents. It provides an additional tool for assessment of ongoing and postincident behavior. The handbook consists of a main body describing generic procedures, an appendix providing specific design data for a limited number of plants for application with the procedures, and an appendix listing existing and planned BWR and PWR plants by containment types and thermal-hydraulic parameters. The procedures are currently limited to break flow rate, decay heat power and integrated power, steam generation from decay heat, mass balance, shutdown margin, natural circulation, noncondensable gas generation, dose estimates, DNB evaluation, void formation in the upper head, and torus heatup

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC A07/MF A01 as TI85006086.

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Additional details

Additional titles

Augmented title (English)
PWR; BWR

Publishing Information

Imprint Pagination
127 p.
Report number
NUREG/CR--4041

Optional Information

Secondary number(s)
EGG--2354.