Relevant bibliographies by topics / Pellet-Cladding Interaction

Contents

  1. Journal articles
  2. Dissertations / Theses
  3. Books
  4. Book chapters
  5. Conference papers
  6. Reports

Academic literature on the topic 'Pellet-Cladding Interaction'

Author: Grafiati
Published: 4 June 2021
Last updated: 18 February 2022

Create a spot-on reference in APA, MLA, Chicago, Harvard, and other styles

Select a source type:

Consult the lists of relevant articles, books, theses, conference reports, and other scholarly sources on the topic 'Pellet-Cladding Interaction.'

Next to every source in the list of references, there is an 'Add to bibliography' button. Press on it, and we will generate automatically the bibliographic reference to the chosen work in the citation style you need: APA, MLA, Harvard, Chicago, Vancouver, etc.

You can also download the full text of the academic publication as pdf and read online its abstract whenever available in the metadata.

Journal articles on the topic "Pellet-Cladding Interaction"

1

Qi, Feipeng, Zhenhai Liu, Quan Li, et al. "Pellet-cladding mechanical interaction analysis of Cr-coated Zircaloy cladding." Nuclear Engineering and Design 367 (October 2020): 110792. http://dx.doi.org/10.1016/j.nucengdes.2020.110792.

Full text
APA, Harvard, Vancouver, ISO, and other styles
2

Halabuk, Dávid, and Jiří Martinec. "CALCULATION OF STRESS AND DEFORMATION IN FUEL ROD CLADDING DURING PELLET-CLADDING INTERACTION." Acta Polytechnica 55, no. 6 (2015): 384. http://dx.doi.org/10.14311/ap.2015.55.0384.

Full text
Abstract:
The elementary parts of every fuel assembly, and thus of the reactor core, are fuel rods. The main function of cladding is hermetic separation of nuclear fuel from coolant. The fuel rod works in very specific and difficult conditions, so there are high requirements on its reliability and safety. During irradiation of fuel rods, a state may occur when fuel pellet and cladding interact. This state is followed by changes of stress and deformations in the fuel cladding. The article is focused on stress and deformation analysis of fuel cladding, where two fuels are compared: a fresh one and a spent
APA, Harvard, Vancouver, ISO, and other styles
3

Hong, Kisik, J. R. Barber, M. D. Thouless, and Wei Lu. "Effect of power history on pellet-cladding interaction." Nuclear Engineering and Design 358 (March 2020): 110439. http://dx.doi.org/10.1016/j.nucengdes.2019.110439.

Full text
APA, Harvard, Vancouver, ISO, and other styles
4

Seo, Sang Kyu, Sung Uk Lee, Eun Ho Lee, Dong Yol Yang, Hyo Chan Kim, and Yong Sik Yang. "3D Finite Element Simulation of Pellet-Cladding Mechanical Interaction." Transactions of the Korean Society of Mechanical Engineers A 40, no. 5 (2016): 437–47. http://dx.doi.org/10.3795/ksme-a.2016.40.5.437.

Full text
APA, Harvard, Vancouver, ISO, and other styles
5

Michel, B., J. Sercombe, and G. Thouvenin. "A new phenomenological criterion for pellet–cladding interaction rupture." Nuclear Engineering and Design 238, no. 7 (2008): 1612–28. http://dx.doi.org/10.1016/j.nucengdes.2008.01.012.

Full text
APA, Harvard, Vancouver, ISO, and other styles
6

YANAGISAWA, Kazuaki, Yoshiaki KONDO, and Erik KOLSTAD. "Pellet-cladding interaction on light water reactor fuel, (I)." Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan 28, no. 7 (1986): 641–57. http://dx.doi.org/10.3327/jaesj.28.641.

Full text
APA, Harvard, Vancouver, ISO, and other styles
7

Michel, B., J. Sercombe, G. Thouvenin, and R. Chatelet. "3D fuel cracking modelling in pellet cladding mechanical interaction." Engineering Fracture Mechanics 75, no. 11 (2008): 3581–98. http://dx.doi.org/10.1016/j.engfracmech.2006.12.014.

Full text
APA, Harvard, Vancouver, ISO, and other styles
8

Chao, Chlng-Kong, and Che-Chung Tseng. "A Power-Rate-Dependent Model for Pellet/Cladding Mechanical Interaction." Nuclear Technology 101, no. 2 (1993): 202–11. http://dx.doi.org/10.13182/nt93-a34781.

Full text
APA, Harvard, Vancouver, ISO, and other styles
9

Denis, Alicia, and Alejandro Soba. "Simulation of pellet-cladding thermomechanical interaction and fission gas release." Nuclear Engineering and Design 223, no. 2 (2003): 211–29. http://dx.doi.org/10.1016/s0029-5493(02)00390-4.

Full text
APA, Harvard, Vancouver, ISO, and other styles
10

Yanagisawa, Kazuaki, and Hiroaki Saito. "A study on bamboo ridge deformation induced by pellet-cladding interaction." Nuclear Engineering and Design 97, no. 3 (1986): 339–46. http://dx.doi.org/10.1016/0029-5493(86)90169-x.

Full text
APA, Harvard, Vancouver, ISO, and other styles

Dissertations / Theses on the topic "Pellet-Cladding Interaction"

1

Gojan, Agnieszka. "Advanced Modeling of Pellet-Cladding Interaction." Thesis, KTH, Fysik, 2016. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-192843.

Full text
APA, Harvard, Vancouver, ISO, and other styles
2

Lundgren, Emil. "A new model for Pellet Cladding Interaction risk assessment." Thesis, KTH, Fysik, 2019. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-263048.

Full text
APA, Harvard, Vancouver, ISO, and other styles
3

Jernkvist, Lars Olof. "Modelling of pellet-cladding interaction induced failure of light water reactor nuclear fuel rods." Licentiate thesis, Luleå tekniska universitet, 1998. http://urn.kb.se/resolve?urn=urn:nbn:se:ltu:diva-26115.

Full text
APA, Harvard, Vancouver, ISO, and other styles
4

Konarski, Piotr. "Thermo-chemical-mechanical modeling of nuclear fuel behavior : Impact of oxygen transport in the fuel on Pellet Cladding Interaction." Thesis, Lyon, 2019. http://www.theses.fr/2019LYSEI080.

Full text
Abstract:
L’objectif de cette thèse est d'étudier l'impact du transport de l’oxygène sur la thermochimie de l’interaction pastille-gaine. Pendant les rampes de puissance, le combustible nucléaire est exposé à des gradients de température élevés. Il subit des changements chimiques et structurels. Le gonflement du combustible entraîne un contact mécanique avec la gaine, provoquant des contraintes mécaniques élevées. Simultanément, des espèces chimiquement réactives sont libérées par le centre des pellets chauds et peuvent interagir avec la gaine. La combinaison de ces facteurs chimiques et mécaniques peut
APA, Harvard, Vancouver, ISO, and other styles
5

Baurens, Bertrand. "Couplages thermo-chimie mécaniques dans le dioxyde d'uranium : application à l' intéraction pastille-gaine." Thesis, Aix-Marseille, 2014. http://www.theses.fr/2014AIXM4047/document.

Full text
Abstract:
En rampe de puissance, le combustible nucléaire est soumis à d'importantes contraintes thermiques et mécaniques, et subit une modification profonde de son environnement chimique. Le combustible contraint fortement la gaine, notamment au niveau des zones inter-pastilles, ce qui, associé au relâchement de produits de fission corrosifs, peut conduire à sa rupture par corrosion sous contraintes. Les évolutions simultanées de la mécanique, de la thermique et de la chimie du combustible sont liées, et participent au bon ou mauvais comportement de l'UO2 en rampe de puissance. L'objectif de ce travail
APA, Harvard, Vancouver, ISO, and other styles
6

Barbié, Laureline. "Raffinement de maillage multi-grille local en vue de la simulation 3D du combustible nucléaire des Réacteurs à Eau sous Pression." Thesis, Aix-Marseille, 2013. http://www.theses.fr/2013AIXM4742.

Full text
Abstract:
Le but de cette étude est d'améliorer les performances, en termes d'espace mémoire et de temps de calcul, des simulations actuelles de l'Interaction mécanique Pastille-Gaine (IPG), phénomène complexe pouvant avoir lieu lors de fortes montées en puissance dans les réacteurs à eau sous pression. Parmi les méthodes de raffinement de maillage, méthodes permettant de simuler efficacement des singularités locales, une approche multi-grille locale a été choisie car elle présente l'intérêt de pouvoir utiliser le solveur en boîte noire tout en ayant un faible nombre de degrés de liberté à traiter par n
APA, Harvard, Vancouver, ISO, and other styles
7

Liu, Hao. "Stratégie de raffinement automatique de maillage et méthodes multi-grilles locales pour le contact : application à l'interaction mécanique pastille-gaine." Thesis, Aix-Marseille, 2016. http://www.theses.fr/2016AIXM4720/document.

Full text
Abstract:
Ce travail de thèse s’inscrit dans le cadre de l’étude de l’Interaction mécanique Pastille-Gaine (IPG) se produisant dans les crayons combustibles des réacteurs à eau pressurisée. Ce mémoire porte sur le développement de méthodes de raffinement de maillage permettant de simuler plus précisément le phénomène d’IPG tout en conservant des temps de calcul et un espace mémoire acceptables pour des études industrielles. Une stratégie de raffinement automatique basée sur la combinaison de la méthode multi-grilles Local Defect Correction (LDC) et l’estimateur d’erreur a posteriori de type Zienkiewicz
APA, Harvard, Vancouver, ISO, and other styles
8

Zouari, Ahmed. "Comportement des gaines en alliages de zirconium en conditions thermo-mécaniques représentatives d’un accident RIA." Thesis, Université Paris sciences et lettres, 2020. http://www.theses.fr/2020UPSLM058.

Full text
Abstract:
Ces travaux ont pour but d’établir une meilleure compréhension du comportement thermomécanique à la rupture des gaines du crayon combustible au cours d’un transitoire accidentel de type RIA. Un dispositif expérimental nommé EDC-T permettant la réalisation d’essais mécaniques sur des gaines en Zircaloy-4 avec des biaxialités de déformation ɛzz/ɛ00 entre -0,2 et 1 a été développé. Une campagne expérimentale à 25 °C menée sur ce dispositif a permis d’étudier les effets de la biaxialité et de la vitesse de déformation sur la rupture de la gaine. Les essais réalisés ont montré un effet important de
APA, Harvard, Vancouver, ISO, and other styles
9

Sun, Ming-hung, and 孫銘宏. "The Hydride Effect on Pellet-Cladding Mechanical Interaction." Thesis, 2012. http://ndltd.ncl.edu.tw/handle/26617640375446804601.

Full text
Abstract:
碩士<br>國立臺灣科技大學<br>機械工程系<br>100<br>The pellet fabrication defect “Missing Pellet Surface (MPS)” became an important failure mechanism of BWR fuel in the past decade, and the unexpected high stress induced on cladding inner surface was identified as “non-classical PCI”. Similar failures were found for few PWR rods at the same time. The failure root cause analysis of some leaking rods indicated that hydrides may play an important role of the outside-in cracking. The study of high burnup fuel behavior performed by Japanese also revealed the cladding outside-in crack during power ramp test and may
APA, Harvard, Vancouver, ISO, and other styles

Books on the topic "Pellet-Cladding Interaction"

1

Carrotte, Jerome. Thermomechanical aspects of pellet-cladding interaction in a pressurised water reactor fuel rod. University of Birmingham, 1995.

Find full text
APA, Harvard, Vancouver, ISO, and other styles

Book chapters on the topic "Pellet-Cladding Interaction"

1

Frankel, Philipp, Alistair Garner, Adam Plowman, et al. "Toward a Mechanistic Understanding of Pellet Cladding Interaction Using Advanced 3D Characterization and Atomistic Simulation." In Zirconium in the Nuclear Industry: 19th International Symposium. ASTM International, 2021. http://dx.doi.org/10.1520/stp162220190047.

Full text
APA, Harvard, Vancouver, ISO, and other styles
2

Sercombe, Jerome, Bruno Michel, Chantal Riglet-Martial, and Olivier Fandeur. "Modeling of Pellet Cladding Interaction." In Comprehensive Nuclear Materials. Elsevier, 2020. http://dx.doi.org/10.1016/b978-0-12-803581-8.00715-3.

Full text
APA, Harvard, Vancouver, ISO, and other styles
3

Michel, B., J. Sercombe, C. Nonon, and O. Fandeur. "Modeling of Pellet Cladding Interaction." In Comprehensive Nuclear Materials. Elsevier, 2012. http://dx.doi.org/10.1016/b978-0-08-056033-5.00074-4.

Full text
APA, Harvard, Vancouver, ISO, and other styles
4

Piro, Markus H. A., Dion Sunderland, Steve Livingstone, et al. "Pellet-Clad Interaction Behavior in Zirconium Alloy Fuel Cladding." In Comprehensive Nuclear Materials. Elsevier, 2020. http://dx.doi.org/10.1016/b978-0-12-803581-8.09799-x.

Full text
APA, Harvard, Vancouver, ISO, and other styles

Conference papers on the topic "Pellet-Cladding Interaction"

1

Brown, N., M. Cinbiz, B. Garrison, K. Linton, and R. Lowden. "Failure Behavior of Nuclear-grade FeCrAl Cladding under Simulated Pellet-cladding Mechanical Interaction Conditions." In Transactions - 2020 Virtual Conference. AMNS, 2020. http://dx.doi.org/10.13182/t122-32352.

Full text
APA, Harvard, Vancouver, ISO, and other styles
2

Brown, N., M. Cinbiz, B. Garrison, K. Linton, and R. Lowden. "Failure Behavior of Nuclear-grade FeCrAl Cladding under Simulated Pellet-cladding Mechanical Interaction Conditions." In Transactions - 2020 Virtual Conference. AMNS, 2020. http://dx.doi.org/10.13182/t32352.

Full text
APA, Harvard, Vancouver, ISO, and other styles
3

Deng, Yangbin, Bowen Qiu, Yingwei Wu, et al. "Simulation on Pellet-Cladding Mechanical Interaction (PCMI) of Accident Tolerant Fuel (ATF) With Coated Cladding." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-66774.

Full text
Abstract:
In this study, based on the code FROBA (Fuel ROd Behavior Analysis), a thermal-mechanical analysis code initially developed for traditional UO2-Zr fuel elements by our research group, a modified version named FROBA-ATF was developed to perform the fuel performance simulation of ATFs with different claddings, including Zr-4, SiC and Zr-4 coated with SiC. Compared with initial version, the cladding could be divided into arbitrary number control volumes with different materials in the new code, so it can be used to perform the calculation for multilayer coatings. In addition, a new non-rigid PCMI
APA, Harvard, Vancouver, ISO, and other styles
4

Klouzal, Jan, and Martin Dostál. "Modelling of the Impact of Local Effects on Fuel-Cladding Interaction During Power Ramp." In 2014 22nd International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/icone22-30807.

Full text
Abstract:
The power increase rate of the reactor is often derived using the fuel performance code. Too restrictive rates are not desirable since they lead to the loss of production. On the other hand fast increase or not well controlled axial power oscillation may result in the rod failure due to pellet-cladding interaction. Most of the currently used fuel performance codes treat the stack of the fuel pellets using a simplified “1.5D” approach where individual pellets are not distinguished and the fuel stack is taken to be symmetrical. In reality, several effects must be taken into account when more acc
APA, Harvard, Vancouver, ISO, and other styles
5

Tang, Changbing, Yongjun Jiao, Yuanming Li, Yi Zhou, and Kun Zhang. "Numerical Simulation Method Research on Pellet-Cladding Mechanical Interaction Based on ABAQUS Software." In 2020 International Conference on Nuclear Engineering collocated with the ASME 2020 Power Conference. American Society of Mechanical Engineers, 2020. http://dx.doi.org/10.1115/icone2020-16387.

Full text
Abstract:
Abstract The cladding acts as the first barrier to prevent the release of radioactive fission products, requiring its structural integrity to be maintained throughout the whole operation period of nuclear reactor. Therefore, cladding failure due to PCI (pellet claading mechanical interaction) should be avoided as much as possible in fuel design and operating conditions. At the same time, it is necessary to achieve effective control of the cladding stress by limiting the power growth rate etc. However, in the manufacturing process of fuel rod, the MPS (missing pellet surface) defect is inevitab
APA, Harvard, Vancouver, ISO, and other styles
6

Liu, Rong, and Wenzhong Zhou. "Fully Coupled Multiphysics Simulation of Enhanced Thermal Conductivity UO2-BeO Fuel Behavior." In ASME 2015 International Mechanical Engineering Congress and Exposition. American Society of Mechanical Engineers, 2015. http://dx.doi.org/10.1115/imece2015-52504.

Full text
Abstract:
Commercial light water reactor fuel UO2 has a low thermal conductivity that leads to the development of a large temperature gradient across the fuel pellet, limiting the reactor operational performance due to the effects that include thermal stresses causing pellet cladding interaction and the release of fission product gases. This study presents the development of a modeling and simulation for enhanced thermal conductivity UO2-BeO fuel behavior in a light water reactor, using self-defined multiple physics models fully coupled based on the framework of COMSOL Multiphysics. Almost all the relat
APA, Harvard, Vancouver, ISO, and other styles
7

Kang, Tianshan, Songyang Li, Dingqu Wang, Yueyuan Jiang, and Weihua Li. "Analysis on Pellet-Cladding Interaction of Fuel Rod During Power Ramp of NHR200-II." In 2018 26th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2018. http://dx.doi.org/10.1115/icone26-81596.

Full text
Abstract:
In order to ensure the safety of fuel rods in nuclear reactor, it is necessary to consider the condition of the power ramp during reactor operation, which may cause breakage risk of fuel rod at the time of pellet-cladding interaction (PCI) appearing. To analyze this phenomenon and reduce the risk, a performance analysis model for fuel rod is developed to carry out the steady state and transient simulation using commercial software COSMOL. The full model has three main computational models, which are heat transfer model, mechanical model and internal pressure model. The calculation results show
APA, Harvard, Vancouver, ISO, and other styles
8

Higashi, Yuma, Nozomu Murakami, Tadakatsu Yodo, and Teruhisa Yamamoto. "Development of the Fuel Behavior Analysis Code for Mechanical Fuel Cladding Failure During Reactivity Insertion Event in PWR." In 2020 International Conference on Nuclear Engineering collocated with the ASME 2020 Power Conference. American Society of Mechanical Engineers, 2020. http://dx.doi.org/10.1115/icone2020-16674.

Full text
Abstract:
Abstract Pellet-Cladding Mechanical Interaction (PCMI) failure is the one of failure mode which must be evaluated in the nuclear fuel safety. PCMI is caused by the mechanical load to cladding due to the fuel pellet expansion. Under the high fuel burnup condition, the fuel cladding may become degraded by embrittlement under the neutron-induced irradiation and hydrogen accumulation due to the waterside corrosion. In order to consider the further deterioration of the material with higher burnup, the evaluation using mechanical indicators, e.g. strain and stress, might be required. In this study,
APA, Harvard, Vancouver, ISO, and other styles
9

Ma, Zehua, Koroush Shirvan, Wei Li, and Yingwei Wu. "Modeling Axial Relocation of Fragmented Fuel During Loss of Coolant Conditions by Using ABAQUS." In 2020 International Conference on Nuclear Engineering collocated with the ASME 2020 Power Conference. American Society of Mechanical Engineers, 2020. http://dx.doi.org/10.1115/icone2020-16291.

Full text
Abstract:
Abstract In a light-water reactor, during normal operating condition, the UO2 nuclear fuel pellets undergo fragmentation primarily due to presence of thermal stresses, fission gas development and pellet-clad mechanical interaction. Under Loss of Coolant Accident (LOCA) conditions, a portion of fuel fragments can freely move downwards to the ballooning region due to the significant cladding deformation. The fuel relocation can localize the heat load and in turn accelerate the cladding balloon and burst process. Cladding burst is of great concern because of the potential for fuel dispersal into
APA, Harvard, Vancouver, ISO, and other styles
10

Li, Feng, Takeshi Mihara, Yutaka Udagawa, and Masaki Amaya. "Biaxial-EDC Test Attempts With Pre-Cracked Zircaloy-4 Cladding Tubes." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-67602.

Full text
Abstract:
When the pellet-cladding mechanical interaction (PCMI) occurs in a reactivity-initiated accident (RIA), the states of stress and strain in the fuel cladding varies in a range depending on the friction and degree of bonding between cladding and pellet. Japan Atomic Energy Agency has developed the improved Expansion-due-to-compression (EDC) test apparatus to investigate the PCMI failure criterion of high-burnup fuel under such conditions. In this study, the failure behavior of cladding tube was investigated by using the improved EDC test apparatus. Cold-worked, stress-relieved and recrystallized
APA, Harvard, Vancouver, ISO, and other styles

Reports on the topic "Pellet-Cladding Interaction"

1

Singh, Gyanender, Ryan Sweet, Brian D. Wirth, Kurt Terrani, and Yutai Kato. Bison Modeling of SiC/SiC Cladding Including Fuel-Pellet Interaction. Office of Scientific and Technical Information (OSTI), 2016. http://dx.doi.org/10.2172/1507879.

Full text
APA, Harvard, Vancouver, ISO, and other styles
2

Orient, G. E., and N. M. Ghoniem. Model for the mechanical pellet-cladding interaction during power cycles. Office of Scientific and Technical Information (OSTI), 1986. http://dx.doi.org/10.2172/5481451.

Full text
APA, Harvard, Vancouver, ISO, and other styles
3

Barner, J., and D. Fitzsimmons. Electrically heated ex-reactor pellet-cladding interaction (PCI) simulations utilizing irradiated Zircaloy cladding. [PWR]. Office of Scientific and Technical Information (OSTI), 1985. http://dx.doi.org/10.2172/6021014.

Full text
APA, Harvard, Vancouver, ISO, and other styles
4

Spencer, B. W., J. W. Peterson, W. Jiang, Y. Lui, S. Veeraraghavan, and A. Casagranda. BISON Contact Algorithm Improvements in Support of Pellet Cladding Mechanical Interaction Modeling. Office of Scientific and Technical Information (OSTI), 2017. http://dx.doi.org/10.2172/1473589.

Full text
APA, Harvard, Vancouver, ISO, and other styles
5

Beyer, Carl E., and Kenneth J. Geelhood. Pellet-Cladding Mechanical Interaction Failure Threshold for Reactivity Initiated Accidents for Pressurized Water Reactors and Boiling Water Reactors. Office of Scientific and Technical Information (OSTI), 2013. http://dx.doi.org/10.2172/1362006.

Full text
APA, Harvard, Vancouver, ISO, and other styles
We offer discounts on all premium plans for authors whose works are included in thematic literature selections. Contact us to get a unique promo code!

To the bibliography