Published July 1985
| Version v1
Report
Dynamic behavior of rapsodie in exceptional transient experiments
Creators
- 1. CEN CADARACHE, Saint-Paul-Lez-Durance, France
Description
In March and April, 1983, a series of experiments on large transients was performed on the sodium cooled fast reactor RAPSODIE at Cadarache. The main objectives of this program are an increase of existing knowledge on physical phenomena under transient conditions providing additional elements concerning verification of physical models and validation of codes relevant to analysis of incidental and accidental fast reactor behavior. The interpretation of these experiments, covering a wide range from full power and flow down to decay power and natural circulation conditions, has been applied to core dynamic behavior and transient thermohydraulics in primary and secondary circuits of the installation
Additional details
Publishing Information
- Imprint Title
- Fast reactor safety: proceedings of the international topical meeting. Volume 2
- Journal Page Range
- p. 635-641.
- Report number
- CONF-850410--Vol.2
Conference
- Title
- ANS/ENS fast reactor safety meeting.
- Dates
- 21-24 Apr 1985.
- Place
- Knoxville, TN (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17036779
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- AFTER-HEAT REMOVAL; EXPERIMENTAL DATA; FLUID FLOW; FUEL ELEMENTS; HEAT TRANSFER; NATURAL CONVECTION; PERFORMANCE; PHYSICAL RADIATION EFFECTS; PRIMARY COOLANT CIRCUITS; RAPSODIE REACTOR; REACTIVITY; REACTOR ACCIDENTS; REACTOR CORES; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; SECONDARY COOLANT CIRCUITS; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; CONVECTION; COOLING SYSTEMS; DATA; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; INFORMATION; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; NUMERICAL DATA; PLUTONIUM REACTORS; RADIATION EFFECTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; SODIUM COOLED REACTORS; TEST REACTORS