Thermal treatment of uranium oxide irradiated in pressurized water reactor: Swelling and release of fission gases

Zacharie, Isabelle; Lansiart, S.; Combette, P.; Trotabas, M.; Coster, Michel; Groos, M.

doi:10.1016/s0022-3115(98)00039-7

Cited by 48 publications

(13 citation statements)

References 3 publications

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“…At the same elevation but for other locations, the interconnection was achieved and, globally, for this elevation, gas release was rather low, around 40-50%. This is supported by fission gas release observed in annealing regime around 2000 K (30-35% for fuel burnup near 25 GWd/t (Une and Kashibe, 1990;Zacharie, 1998)) or at higher temperature (∼85% for fuel burn-up near 40 Gwd/t at 2573 K (Ducros et al, 2001)). …”

Section: Fission Gas Behaviour During the Fpt0 And Fpt1 Experimentsmentioning

confidence: 61%

“…Nevertheless, one must also consider the behaviour of grain bubbles and their interactions with point and extended defects. In annealing regime up to 2000 K, microstructure observations showed that gas release is accompanied by a rapid growth of grain bubbles (up to hundreds of nanometre) and a decrease of the bubble concentration, mainly near the grainboundary (Kashibe et al, 1993;Une and Kashibe, 1990;Zacharie, 1998). There are still many discussions about the mechanisms for bubble growth (Lösönen, 2000).…”

Section: Fission Gas Behaviour During the Fpt0 And Fpt1 Experimentsmentioning

confidence: 99%

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Fission product release in the first two PHEBUS tests FPT0 and FPT1

Dubourg

Faure-Geors

Nicaise

et al. 2005

Nuclear Engineering and Design

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Section: Fission Gas Behaviour During the Fpt0 And Fpt1 Experimentsmentioning

confidence: 61%

Section: Fission Gas Behaviour During the Fpt0 And Fpt1 Experimentsmentioning

confidence: 99%

Fission product release in the first two PHEBUS tests FPT0 and FPT1

Dubourg

Faure-Geors

Nicaise

et al. 2005

Nuclear Engineering and Design

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“…The precipitation of γ-hydride in zirconium generates three possible equivalent orientation variants with an angle of 120°between each other. The non-zero components of the stressfree transformation strain tensor for the hydride formation are along [0 0 0 1], [11][12][13][14][15][16][17][18][19][20], and directions, respectively. In the simulations, the interfacial energy was assumed to be isotropic.…”

Section: Simulations Of Different Phenomena In Radiation-induced Micrmentioning

confidence: 99%

“…9,[18][19][20][21] The radiation-induced heterogeneity of the microstructures depends on the initial phase and defect structure of the fresh (non-irradiated) materials and on the type and severity of the radiation environment. Fundamental understanding of heterogeneous three-dimensional microstructure evolution is crucial to the development of advanced radiation tolerant materials that can significantly improve the life extension of current reactor fleet and impact advanced reactor designs.…”

Section: Introductionmentioning

confidence: 99%

A review: applications of the phase field method in predicting microstructure and property evolution of irradiated nuclear materials

Sun

et al. 2017

npj Comput Mater

121

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Complex microstructure changes occur in nuclear fuel and structural materials due to the extreme environments of intense irradiation and high temperature. This paper evaluates the role of the phase field method in predicting the microstructure evolution of irradiated nuclear materials and the impact on their mechanical, thermal, and magnetic properties. The paper starts with an overview of the important physical mechanisms of defect evolution and the significant gaps in simulating microstructure evolution in irradiated nuclear materials. Then, the phase field method is introduced as a powerful and predictive tool and its applications to microstructure and property evolution in irradiated nuclear materials are reviewed. The review shows that (1) Phase field models can correctly describe important phenomena such as spatial-dependent generation, migration, and recombination of defects, radiation-induced dissolution, the Soret effect, strong interfacial energy anisotropy, and elastic interaction; (2) The phase field method can qualitatively and quantitatively simulate two-dimensional and three-dimensional microstructure evolution, including radiation-induced segregation, second phase nucleation, void migration, void and gas bubble superlattice formation, interstitial loop evolution, hydrate formation, and grain growth, and (3) The Phase field method correctly predicts the relationships between microstructures and properties. The final section is dedicated to a discussion of the strengths and limitations of the phase field method, as applied to irradiation effects in nuclear materials. npj Computational Materials (2017) 3:16 ; doi:10.1038/s41524-017-0018-y INTRODUCTIONHigh energy particle (such as neutron, ion, and electron) radiation can create major changes in the shape and thermo-mechanical properties of nuclear fuels and structural components of nuclear reactors. These changes are caused by radiation-induced evolution of compositions and microstructures. The main effects of radiation on reactor materials are: (1) dimensional change associated with gas bubble swelling, void swelling, grain growth, and creep; 1-5 (2) loss of ductility and increase in ductile-brittle transition temperature (DBTT) due to the formation of secondphase precipitates, self-interstitial atomic (SIA) loops, and dislocation networks; 6, 7 (3) oxidation and corrosion accelerated by high temperature, fission products, and radiation damage; 8-10 and (4) local and bulk changes in chemical composition, including irradiation-enhanced segregation of alloy components and phase separation.11-17 Figure 1 shows typical microstructures observed in irradiated materials.9, 18-21 The radiation-induced heterogeneity of the microstructures depends on the initial phase and defect structure of the fresh (non-irradiated) materials and on the type and severity of the radiation environment. Fundamental understanding of heterogeneous three-dimensional microstructure evolution is crucial to the development of advanced radiation tolerant materials that can significa...

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“…Nuclear fissions of fuel particles produce fission heat [4,5]; and the solid and inert gas fission products brought by nuclear fission might lead to volume swelling of fuel particles with increasing of burnup, moreover, fission gas release might occur [6][7][8][9]. Furthermore, the fission products and high energy ions produced by nuclear fissions might make the mechanical behaviors of the matrix materials change with burnup [10].…”

Section: Introductionmentioning

confidence: 99%