ARMA models in the analysis of temperature noise measurements in a super-phenix subassembly mock-up
- 1. Comitato Nazionale per l'Energia Nucleare, Casaccia (Italy). Centro di Studi Nucleari
- 2. Comitato Nazionale per l'Energia Nucleare, Bologna (Italy)
Description
The noise analysis methods play an important role in the early, reliable detection of local cooling disturbances in a fast reactor subassembly such as sodium boiling or blockage, which are considered among the initiating events of major disruptive core accidents. Box and Jenkins auto-regressive moving-average ARMA models are applied to the analysis of several temperature time-series measured by the Commissariat a l'Energie Atomique in the course of the CFNa experiment carried out at the nuclear center of Grenoble. The source of data is a thermocouple placed at the outlet of a Super-Phenix subassembly mock-up. The analysis shows that a simple ARMA (3,2) model adequately accounts for the observed fluctuations. This model provides methods for a continuous, in situ estimate of the thermocouple time constant, for the identification of a suitable boiling and blockage indicator and for the detection in real time of suddenly occurring disturbances. (author)
Additional details
Publishing Information
- Journal Title
- Ann. Nucl. Energy
- Journal Volume
- 7
- Journal Issue
- 12
- Series
- Ann. Nucl. Energy.
- Journal Page Range
- 665-683
- ISSN
- 0306-4549
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 12596695
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- BOILING; FLUCTUATIONS; FUEL ASSEMBLIES; LIQUID METALS; MOCKUP; SODIUM; SUPER PHENIX REACTOR; TEMPERATURE NOISE
- Descriptors DEC
- ALKALI METALS; BREEDER REACTORS; ELEMENTS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FLUIDS; LIQUID METAL COOLED REACTORS; LIQUIDS; METALS; NOISE; PHASE TRANSFORMATIONS; PLUTONIUM REACTORS; REACTORS; SODIUM COOLED REACTORS; STRUCTURAL MODELS; VARIATIONS