Time-dependent Fuel Temperature Model for the ANDREA Core Physics Code
Časově závislý model teploty paliva pro makrokód ANDREA
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České vysoké učení technické v Praze
Czech Technical University in Prague
Czech Technical University in Prague
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Přechodové procesy se změnou teploty paliva jsou nedílnou součástí provozu energetického reaktoru a jejich analýza je nutná pro zajištění jaderné bezpečnosti. Práce je zaměřena na tvorbu nestacionárního modelu teploty paliva TVSA-T jaderného reaktoru VVER-1000. Stručně popisuje termomechanické jevy probíhající na lehkovodních reaktorech a možnosti češení rovnice vedení tepla se zaměřením na metodu konečných diferencí (MKD) v radiální geometrii. Na základě analytického řešení vedení tepla je vytvořen stacionární model teploty paliva s parametry závislými na teplotě a vyhoření. Tento model je pak využit k tvorbě nestacionárního modelu založeného na MKD. Funkčnost obou modelů je srovnávána s výpočty ve validovaném kódu TRANSURANUS a ve většině případů je dosahováno dobré shody výsledků. V poslední kapitole je stručně popsán postup implementace teplotního modelu do makrokódu ANDREA.
Transients are integral part of power reactor operation and their analysis must be done to ensure nuclear safety. The thesis deals with time-dependent TVSA-T fuel temperature model of WWER-1000 reactor. At first, thermomechanical phenomena on light water reactors are briefly described, then the possibilities of solving heat transfer equation are covered. Particular attention is given to the finite difference method (FDM) in radial geometry. A stationary fuel temperature model with coefficients dependent on temperature and burnup, based on simple analytical solution of heat transfer is created. After that, time-dependent fuel temperature model is designed using FDM and a part of stationary model. Both models are tested and compared to the referential data obtained by validated TRANSURANUS code. In most cases, there is a good conformity in model and TRANSURANUS results. Finally, the implementation of temperature model into ANDREA core physics code is shortly described.
Transients are integral part of power reactor operation and their analysis must be done to ensure nuclear safety. The thesis deals with time-dependent TVSA-T fuel temperature model of WWER-1000 reactor. At first, thermomechanical phenomena on light water reactors are briefly described, then the possibilities of solving heat transfer equation are covered. Particular attention is given to the finite difference method (FDM) in radial geometry. A stationary fuel temperature model with coefficients dependent on temperature and burnup, based on simple analytical solution of heat transfer is created. After that, time-dependent fuel temperature model is designed using FDM and a part of stationary model. Both models are tested and compared to the referential data obtained by validated TRANSURANUS code. In most cases, there is a good conformity in model and TRANSURANUS results. Finally, the implementation of temperature model into ANDREA core physics code is shortly described.