Some uncertainty results obtained by the statistical version of the KARATE code system related to core design and safety analysis
| Autor: | E. Temesvári, Cs. Maráczy, I. Panka, Gy. Hegyi |
|---|---|
| Rok vydání: | 2017 |
| Předmět: |
Nuclear and High Energy Physics
Radiation Computer science 020209 energy Nuclear engineering Sampling (statistics) 02 engineering and technology Covariance Core (game theory) Nuclear Energy and Engineering 0202 electrical engineering electronic engineering information engineering Code (cryptography) General Materials Science VVER Safety Risk Reliability and Quality Burnup |
| Zdroj: | Kerntechnik. 82:517-526 |
| ISSN: | 2195-8580 0932-3902 |
| DOI: | 10.3139/124.110826 |
| Popis: | The best-estimate KARATE code system has been widely used for core design calculations and simulations of slow transients of VVER reactors. Recently there has been an increasing need for assessing the uncertainties of such calculations by propagating the basic input uncertainties of the models through the full calculation chain. In order to determine the uncertainties of quantities of interest during the burnup, the statistical version of the KARATE code system has been elaborated. In the first part of the paper, the main features of the new code system are discussed. The applied statistical method is based on Monte-Carlo sampling of the considered input data taking into account mainly the covariance matrices of the cross sections and/or the technological uncertainties. In the second part of the paper, only the uncertainties of cross sections are considered and an equilibrium cycle related to a VVER-440 type reactor is investigated. The burnup dependence of the uncertainties of some safety related parameters (e.g. critical boron concentration, rod worth, feedback coefficients, assembly-wise radial power and burnup distribution) are discussed and compared to the recently used limits. |
| Databáze: | OpenAIRE |
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