Published 1976 | Version v1
Report

Comparison of neutronics calculations in a loss-of-flow accident

  • 1. Argonne National Lab., IL

Description

Results of a study of the accuracy of point kinetics reactivity predictions for loss-of-flow transients in a CRBR model are presented. Neutronics calculations were driven by realistic material and temperature histories representative of the thermal-hydraulic feedback which occurs in this type of transient. Reactivity solutions from 3 point kinetics variations and the quasistatic method are compared. One variation is found to be superior to the others for these transients; its prediction at power burst conditions is low by approximately $0.35. Accurate quasistatic neutronics calculations are found to have small CPU requirements relative to the time required for thermal-hydraulic calculations with SAS

Additional details

Publishing Information

Imprint Title
Fast reactor safety and related physics. Vol. II
Journal Page Range
p. 463-472.
Report number
CONF-761001--P2

Conference

Title
International meeting on fast reactor safety and related physics.
Dates
5 - 8 Oct 1976.
Place
Chicago, Illinois, USA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
9365600
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CLINCH RIVER BREEDER REACTOR; LOSS OF FLOW; REACTIVITY; TRANSIENTS
Descriptors DEC
ACCIDENTS; BREEDER REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SODIUM COOLED REACTORS