Best estimate thermo-mechanical fuel modelling in transient analyses
Creators
- 1. Nuclear Research Institute Rez plc., (Czech Republic)
Description
The paper documents the second phase of systematic evaluation of FRAPTRAN+SUSA software package application on IFA650.3 LOCA experiment. A short comment to the first set of calculations has been maid and temperature dependent uncertain input data (boundary conditions) as well as time dependent results for all performed calculations and results of SUSA uncertainty analysis with two-sided tolerance at 95% probability and 95% confidence have been presented. The basic results of the set of the calculations are as follows: 1) uncertainty of thermal boundary conditions ±0.5% of nominal values produced maximum spread in clad hoop strain [from ∼0.064 through ∼0.092(nom. data) to ∼0.099], i.e. -53% to +107%, and clad effective elasto-plastic strain [from ∼0.060 through ∼0.113(nom. data) to ∼0.121], i.e. -70% to +108%; 2) these results are appropriate to last 15 - 20 sec. of the process before the cladding burst. It has been found that: 1) The fill gas pressure is the second most important parameter; 2) Temperature range of uncertainties has growing influence; 3) The BE method for LB LOCA modelling is applicable; 4) The processes with very high dynamics / instabilities create difficulties in frame of BE. The further goal is to perform numerical experiment for real PWR LB LOCA accident fuel rod response to test applicability of the developed methodological procedure
Availability note (English)
Available from INIS in electronic formFiles
39079740.pdf
Files
(2.1 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 20 p.
- Report number
- INIS-BG--1232
Conference
- Title
- 7. International conference on WWER fuel performance, modelling and experimental support
- Dates
- 17-21 Sep 2007
- Place
- Albena (Bulgaria)
INIS
- Country of Publication
- Bulgaria
- Country of Input or Organization
- Bulgaria
- INIS RN
- 39079740
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BOUNDARY CONDITIONS; CLADDING; COMPUTER CODES; COMPUTERIZED SIMULATION; EVALUATION; FUEL RODS; FUELS; LOSS OF COOLANT; PROBABILITY; PWR TYPE REACTORS; TEMPERATURE DEPENDENCE; TEMPERATURE RANGE; TOLERANCE; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; DEPOSITION; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SIMULATION; SURFACE COATING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 13 figs., 1 tab.