The Phenix final tests
Creators
- 1. CEA-Cadarache, BP 1, 13108 Saint Paul lez Durance (France)
- 2. CEA-Grenoble, Grenoble (France)
- 3. Centrale Phenix, CEA-Marcoule, Marcoule (France)
- 4. EDF, Clamart (France)
- 5. AREVA NP, Lyon (France)
Description
After the final shutdown of the Phenix sodium cooled fast reactor and before decommissioning, a final set of tests were performed covering core physics (5 tests: measurement of individual subassembly reactivity worth, decay heat measurement, control rod offsetting, the reactivity effect of a gas bubble, and control rod worth measurement)), fuel behavior (1 test: MOX fuel pin melting) and thermal-hydraulics areas (2 tests: asymmetrical regime and natural convection). Detailed analysis of the tests results is ongoing. It will allow the extension of code validation for core physics, for thermal-hydraulics and for fuel behavior. In addition, the program included two tests related to the comprehension of the four negative reactivity transients (AURN in French acronym) experienced during the reactor operation in 1989 and 1990. The analysis of the AURN transients performed in the early nineties had concluded that the most likely mechanism for a fast decrease of the core reactivity was a radial core deformation named core flowering. The core flowering test was carried out by introducing a mechanical device to deform Phenix core. The purpose of the test was to measure the reactivity effect of such deformation at subcritical and critical zero power conditions. The mechanical behaviour of the core was close to what was expected. Very small changes on core radius give significant reactivity modifications. The standard instrumentation of the reactor was completed by specifically designed devises. The PHENIX final tests program was performed successfully within the planned time schedule and provided a significant amount of data for the development of sodium fast reactors
Additional details
Identifiers
Publishing Information
- Imprint Title
- Proceedings of ICAPP 2011
- Imprint Pagination
- 2851 p.
- Journal Page Range
- p. 659-663
- Report number
- INIS-FR--13-0283
Conference
- Title
- The Power of Innovation
- Acronym
- ICAPP 2011 - Performance and Flexibility
- Dates
- 2-5 May 2011
- Place
- Nice (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 44092851
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; PHENIX REACTOR; REACTIVITY WORTHS; RESEARCH PROGRAMS; TRANSIENTS
- Descriptors DEC
- BREEDER REACTORS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; PLUTONIUM REACTORS; POWER REACTORS; REACTORS; REMOVAL; SODIUM COOLED REACTORS
Optional Information
- Notes
- Available from the INIS Liaison Officer for France, see the 'INIS contacts' section of the INIS website for current contact and E-mail addresses: http://www.iaea.org/INIS/contacts/