Thermo-chemical-mechanical modeling of nuclear fuel behavior: Impact of oxygen transport in the fuel on Pellet Cladding Interaction
Description
The goal of this thesis is to study the impact of oxygen transport on thermochemistry of nuclear fuel and pellet cladding interaction. During power ramps, nuclear fuel is exposed to high temperature gradients. It undergoes chemical and structural changes. The fuel swelling leads to a mechanical contact with the cladding causing high mechanical stresses in the cladding. Simultaneously, chemically reactive gas species are released from the hot pellet center and can interact with the cladding. The combination of these chemical and mechanical factors may lead to the cladding failure by iodine stress corrosion cracking. It has been proven that oxygen transport under high temperature gradients affects irradiated fuel thermochemistry, a phenomenon which may be of importance for stress corrosion cracking. This thesis presents 3D simulations of power ramps in pressurized water reactors with the fuel performance code ALCYONE, which is part of the computing environment PLEIADES. The code has been upgraded to couple the description of irradiated fuel thermochemistry already available with oxygen transport taking into account oxygen thermal diffusion. The impact of oxygen redistribution during a power transient on irradiated fuel thermochemistry in the fuel and on chemically reactive gas release from the fuel (consisting of I(g), I2(g), CsI(g), TeI2(g), Cs(g) and Cs2(g), mainly) is studied. The simulations show that oxygen redistribution, even if moderate in magnitude, leads to the reduction of metallic oxides (molybdenum dioxide, cesium molybdate, chromium oxide) at the fuel pellet center and consequently to the release of a much greater quantity of gaseous cesium, in agreement with post-irradiation examinations. The three-dimensional calculations of the quantities of importance for iodine stress corrosion cracking (hoop stress, hoop strain, iodine partial pressure at the clad inner wall) are then used in simulations of clad crack propagation. (author)
Abstract (French)
L'objectif de cette these est d'etudier l'impact du transport de l'oxygene sur la thermochimie de l'interaction pastille-gaine. Pendant les rampes de puissance, le combustible nucleaire est expose a des gradients de temperature eleves. Il subit des changements chimiques et structurels. Le gonflement du combustible entraine un contact mecanique avec la gaine, provoquant des contraintes mecaniques elevees. Simultanement, des especes chimiquement reactives sont liberees par le centre des pellets chauds et peuvent interagir avec la gaine. La combinaison de ces facteurs chimiques et mecaniques peut entrainer une defaillance de la gaine causee par la fissuration par corrosion sous contrainte. Il a ete prouve que le transport de l'oxygene sous des gradients de temperature eleves affecte la thermochimie, ce qui peut jouer un role important dans la fissuration par corrosion sous contrainte. Cette these presente des simulations 3D de rampes de puissance dans des reacteurs a eau sous pression avec le code de performance de combustible ALCYONE, qui fait partie de l'environnement informatique PLEIADES. Le code a ete mis a jour pour associer la description de la thermochimie du carburant irradie deja disponible au transport de l'oxygene en tenant compte de la thermo diffusion de l'oxygene. L'impact de la redistribution de l'oxygene pendant une periode transitoire de puissance sur la thermochimie du combustible irradie et sur le relachement de gaz chimiquement reactif provenant du combustible (I(g), I2(g), CsI(g), TeI2(g), Cs(g) et Cs2(g) principalement) est etudie. Les simulations montrent que la redistribution de l'oxygene, meme moderee, conduit a la reduction des oxydes metalliques (dioxyde de molybdene, molybdates de cesium, oxyde de chrome) au centre des pastilles de combustible et, par consequent, au relachement d'une quantite beaucoup plus importante de cesium gazeux, en accord avec les examens post-irradiation. Les calculs tridimensionnels des quantites d'importance pour la fissuration par corrosion sous contrainte due a l'iode (contrainte circonferentielle, deformation circonferentielle, pression partielle d'iode sur gaine) sont ensuite utilises dans des simulations de propagation de fissures de gaine. (l'auteur)
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Additional details
Additional titles
- Original title (English)
- Modelisation thermique-chimique-mecanique du comportement du combustible nucleaire: Impact du transport d'oxygene dans le carburant sur l'interaction pastille-gaine
Publishing Information
- Imprint Pagination
- 344 p.
- Report number
- FRCEA-TH--12148
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 51109401
- Subject category
- S36: MATERIALS SCIENCE; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Thesis
- Descriptors DEI
- CESIUM; COMPUTERIZED SIMULATION; CRACK PROPAGATION; CRACKS; FISSION PRODUCTS; FUEL ELEMENT FAILURE; FUEL PELLETS; FUEL-CLADDING INTERACTIONS; IODINE; NUCLEAR FUELS; OXYGEN; STRESS CORROSION; SWELLING; TEMPERATURE GRADIENTS; THERMAL DIFFUSION
- Descriptors DEC
- ALKALI METALS; CHEMICAL REACTIONS; CORROSION; DEFORMATION; DIFFUSION; ELEMENTS; ENERGY SOURCES; FAILURES; FUELS; HALOGENS; ISOTOPES; MATERIALS; METALS; NONMETALS; PELLETS; RADIOACTIVE MATERIALS; REACTOR MATERIALS; SIMULATION
Optional Information
- Notes
- 209 refs.; Available from the INIS Liaison Officer for France, see the INIS website for current contact and E-mail addresses