Published 1976
| Version v1
Report
Comparison of neutronics calculations in a loss-of-flow accident
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