State-of-the-Art Report on Light Water Reactor Accident-Tolerant Fuels

Pasamehmetoglu, Kemal; Massara, S.; Costa, Davide; Bragg‐Sitton, Shannon; Moatti, Marie; Kurata, Masaki; Iracane, D.; Ivanova, Tatiana; Bischoff, Jeffrey E.; Delafoy, C.; Brachet, J.C.; Chauvin, John; Coulon-Picard, E.; Forgeron, T.; Gonnier, C.; Lorrette, Christophe; Cheng, B.; Csontos, A.; Sowder, Andrew; Topbasi, C.; Yueh, Ken; Cozzo, C.; Pouchon, Manuel A.; Dolley, Evan J.; Rebak, Raúl B.; Gassmann, W.P.; Hania, P.R.; Heuser, Brent J.; Kakiuchi, Kazuo; Katoh, Yutai; Terrani, Kurt A.; Kim, H.G.; Kim, W.J.; Koo, Yang-Hyun; Yang, Jae-Ho; Kohyama, Akira; Lahoda, Edward J.; Xu, Peng; Li, R.; Liu, T.; Zhou, Wenzhan; Linhart, S.; Rehacek, Radomir; Pouillier, E.; Waeckel, N.; Ohta, H.; Petit, Marc; Puide, Mattias; Wright, James H.; Sakamoto, Kazuhiko; Savchenko, A. V.; Ševeček, Martin; Steinbrueck, Martin; Tang, Chongchong; Tulenko, J.S.; Nieuwenhove, R. Van; Vernon, Eric; Verwerft, Marc; Zvonarev, Yu.A.

doi:10.1787/9789264308343-en

Cited by 9 publications

(4 citation statements)

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“…where D v gb (m 2 s À1 ) is the vacancy diffusion coefficient along grain boundaries, d gb (m) the thickness of the diffusion layer in grain boundaries, and the parameter S (À) 4 depends on the fraction of grain faces covered by bubbles (fractional coverage) as detailed in Ref. [56].…”

Section: Inter-granular Modelmentioning

confidence: 99%

“…For analogous reasons, for the intra-granular vacancy diffusion coefficient, D v ig , we chose the one for the U (U 2a) vacancy diffusion along the c-axis. 4 As mentioned above, the parameter S depends on the geometrical representation of the emission/absorption phenomena. For behavior on a surface (grain boundary), the expression for S reads [56]…”

Section: Values For the Model Parametersmentioning

confidence: 99%

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Multiscale modeling of fission gas behavior in U3Si2 under LWR conditions

Barani

Pastore

Pizzocri

et al. 2019

Journal of Nuclear Materials

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In this work, we present a model of fission gas behavior in U 3 Si 2 under light water reactor (LWR) conditions for application in engineering fuel performance codes. The model includes components for intra-granular and inter-granular behavior of fission gases. The intra-granular component is based on cluster dynamics and computes the evolution of intra-granular fission gas bubbles and swelling coupled to gas diffusion to grain boundaries. The inter-granular component describes the evolution of grain-boundary fission gas bubbles coupled to fission gas release. Given the lack of experimental data for U 3 Si 2 under LWR conditions, the model is informed with parameters calculated via atomistic simulations. In particular, we derive fission gas diffusivities through density functional theory calculations, and the re-solution rate of fission gas atoms from intra-granular bubbles through binary collision approximation calculations. The developed model is applied to the simulation of an experiment for U 3 Si 2 irradiated under LWR conditions available from the literature. Results point out a credible representation of fission gas swelling and release in U 3 Si 2 . Finally, we perform a sensitivity analysis for the various model parameters. Based on the sensitivity analysis, indications are derived that can help in addressing future research on the characterization of the physical parameters relative to fission gas behavior in U 3 Si 2 . The developed model is intended to provide a suitable infrastructure for the engineering scale calculation of fission gas behavior in U 3 Si 2 that exploits a multiscale approach to fill the experimental data gap and can be progressively improved as new lower-length scale calculations and validation data become available.

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Section: Inter-granular Modelmentioning

confidence: 99%

Section: Values For the Model Parametersmentioning

confidence: 99%

Multiscale modeling of fission gas behavior in U3Si2 under LWR conditions

Barani

Pastore

Pizzocri

et al. 2019

Journal of Nuclear Materials

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“…A number of socalled accident tolerant fuels (ATF) have been proposed for current light water reactor (LWR) reactor designs. These include coated zirconium alloy claddings; FeCrAl claddings; novel pellet materials and SiC-SiC composite cladding [1][2][3][4][5][6][7][8][9][10][11][12][13][14] . Moving to the longer term, advanced technology fuels (also termed ATF) offer the possibility of not only enhanced safety, but the opportunity to move towards higher burnups.…”

Section: Introductionmentioning

confidence: 99%

Peridynamic Modelling of Cracking in TRISO Particles for High Temperature Reactors

Haynes¹,

Battistini²,

Leide³

et al. 2023

Preprint

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A linear-elastic computer simulation (model) for a single particle of TRISO fuel has been built using a bond-based peridynamic technique implemented in the finite element code 'Abaqus'. The model is able to consider the elastic and thermal strains in each layer of the particle and to simulate potential fracture both within and between layers. The 2D cylindrical model makes use of a plane stress approximation perpendicular to the plane modelled. The choice of plane stress was made by comparison of 2D and 3D finite element models. During an idealised ramp to normal operating power for a kernel of 0.267 W and a bulk fuel temperature of 1305 K, cracks initiate in the buffer near to the kernel-buffer interface and propagate towards the buffer-iPyC coating interface, but do not penetrate the iPyC and containment of the fission products is maintained. In extreme accident conditions, at around 600% (1.60 W) power during a power ramp at 100% power (0.267 W) per second, cracks were predicted to form on the kernel side of the kernel-buffer interface, opposite existing cracks in the buffer. These were predicted to then only grow further with further increases in power. The SiC coating was predicted to subsequently fail at a power of 940% (2.51 W), with cracks formed rapidly at the iPyC-SiC interface and propagating in both directions. These would overcome the containment to fission gas release offered by the SiC 'pressure vessel'. The extremely high power at which failure was predicted indicates the potential safety benefits of the proposed high temperature reactor design based on TRISO fuel.

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“…The most promising ATF concept is the fuel cladding made of Zr-based alloy with a protective Cr coating of outer wall [2,3]. Coating slows down the absorption rate of hydrogen as well as the process of oxidation in normal operation [4][5][6].…”

Section: Introductionmentioning

confidence: 99%

Experimental Study of Damaged Cr-Coated Fuel Cladding in Post-Accident Conditions

Cervenka

Krejčí

Cvrček

et al. 2020

APP

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To enhance the safety of nuclear power, the focus of researchers all around the world has recently mainly objected on the development of Accident Tolerant Fuels. Especially the Chromium coating of current Zirconium based cladding has been widely suggested and discussed for its immense positive effect on overall cladding properties. Nevertheless, it was observed that during the first stage of the Loss of Coolant Accident, cracks appear in the Cr coating due to its inability to tolerate higher plastic strain. Therefore, experimental methodology used in this article focuses on testing fuel cladding with damaged Cr coating after the high-temperature transient. The impact of cracks on degradation of cladding mechanical properties was observed using optical microscopy, ring compression test, microhardness, and evaluating hydrogen content and weight gain.

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State-of-the-Art Report on Light Water Reactor Accident-Tolerant Fuels

Cited by 9 publications

References 0 publications

Multiscale modeling of fission gas behavior in U3Si2 under LWR conditions

Multiscale modeling of fission gas behavior in U3Si2 under LWR conditions

Peridynamic Modelling of Cracking in TRISO Particles for High Temperature Reactors

Experimental Study of Damaged Cr-Coated Fuel Cladding in Post-Accident Conditions

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