Analysis of SPERT reactivity transient by PARET Computer code
Creators
- 1. Laboratoire des etudes thermohydrauliques, Centre de Recherche Nucleaire de Birine, B.P 180 Ain-oussera, Djelfa (Algeria)
- 2. Laboratoire des Analyses de surete Centre de Recherche Nucleaire d'Alger, 02 Boulevard Frantz fanon, BP 399 Alger gare (Algeria)
- 3. Dipartimento di Ingegneria Meccanica, Nucleare e della Produzione - Facolta di Ingegneria, Universita degli studi di Pisa. Via Diotisalvi, 2 - 56100, Pisa (Italy)
Description
The purpose of this work is devoted to the analysis and the study of the SPERT reactivity insertion transient's tests by PARET model. The SPERT excursion power experiments offer an interesting opportunity to check the models and theories. In this sense, a coupled neutronics and core thermal-hydraulic PARET model has been used to perform the analysis of SPERT III experimental reactivity transients. In this framework, the series of step reactivity insertion tests made at the atmospheric pressure and ambient temperature are reproduced by PARET because they are representatives of research reactor operation conditions. The SPERT III-C tests under concern here are self-limited transients and no destructive tests are considered. It is of interest to consider cases where the specified scram is removed. PARET is a channel code based on a coupling of point kinetics, homogeneous 1-D, incompressible fluid and heat transfer and 1-D heat conduction. The results of PARET code are compared with the experimental data; this showed a satisfactory agreement; some of the discrepancies observed are discussed. (author)
Availability note (English)
Available from the INIS Liaison Officer for France, see the INIS website for current contact and E-mail addressesAdditional details
Publishing Information
- Imprint Pagination
- 8 p.
- Report number
- INIS-MA--23-PHYTRA-51
Conference
- Title
- 1. International Conference on Physics and Technology of Reactors and Applications
- Original Conference Title
- PHYTRA 1 - Premiere conference internationale sur la physique et les technologies des reacteurs nucleaires et leurs applications
- Acronym
- PHYTRA 1
- Dates
- 14-16 Mar 2007
- Place
- Marrakech (Morocco)
INIS
- Country of Publication
- Morocco
- Country of Input or Organization
- France
- INIS RN
- 55014106
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- AMBIENT TEMPERATURE; ATMOSPHERIC PRESSURE; COMPUTER CODES; FLUIDS; KINETICS; NEUTRON TRANSPORT; REACTIVITY INSERTIONS; REACTOR OPERATION; RESEARCH REACTORS; SCRAM; THERMAL CONDUCTION; THERMAL HYDRAULICS; TRANSIENTS
- Descriptors DEC
- ENERGY TRANSFER; FLUID MECHANICS; HEAT TRANSFER; HYDRAULICS; MECHANICS; NEUTRAL-PARTICLE TRANSPORT; OPERATION; RADIATION TRANSPORT; REACTOR LIFE CYCLE; REACTOR SHUTDOWN; REACTORS; RESEARCH AND TEST REACTORS; SHUTDOWN
Optional Information
- Notes
- 11 refs.