Post-test analysis with RELAP5/MOD2 of ROSA-IV/LSTF natural circulation test ST-NC-02
Creators
- 1. CEA Centre d'Etudes Nucleaires de Fontenay-aux-Roses, 92 (France)
Description
Results of post-test analysis for the ROSA-IV/LSTF natural circulation experiment ST-NC-02 are presented. The experiment consisted of many steady-state stages registered for different primary inventories. The calculation was done with RELAP5/MOD2 CYCLE 36.00. Discrepancies between the calculation and the experiment are observed: the core flow rate is overestimated at inventories between 80 % and 95 %; the inventory at which dryout occurs in the core is also much overestimated. The causes of these discrepancies are studies through sensitivity calculations and the following key parameters are pointed out: the interfacial friction and the form loss coefficients in the vessel riser, the SG U-tube multidimensional behaviour, the interfacial friction in the SG inlet plenum and in the pipe located underneath. (author)
Availability note (English)
MF available from INIS under the Report Number.Files
20030286.pdf
Files
(1.2 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 58 p.
- Report number
- JAERI-M--88-215
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 20030286
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BOUNDARY CONDITIONS; DRYOUT; FLOW RATE; FRICTION FACTOR; NATURAL CONVECTION; PRESSURE DROP; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; R CODES; REACTOR CHANNELS; REACTOR CORES; REACTOR SAFETY; SENSITIVITY ANALYSIS; STEADY-STATE CONDITIONS; VAPOR CONDENSATION
- Descriptors DEC
- COMPUTER CODES; CONVECTION; COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; HEAT TRANSFER; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS