Degradation of Cr-coated cladding under the simulated Loss-of-Coolant Accident phenomena
The present study focuses on the evaluation of the mechanical properties degradation of Cr-coated Zr-alloy fuel cladding. The main objective of the work is to find a suitable methodology to evaluate the mechanical properties degradation of coated cladding by performing several separate effects exper...
| Published in: | Acta Polytechnica CTU Proceedings |
|---|---|
| Main Authors: | Petr Červenka, Jakub Krejčí, Ladislav Cvrček, František Manoch, Adéla Chalupová, Patricie Halodová, Petra Gávelová |
| Format: | Article |
| Language: | English |
| Published: |
Czech Technical University in Prague
2022-12-01
|
| Subjects: | |
| Online Access: | https://ojs.cvut.cz/ojs/index.php/APP/article/view/8557 |
Similar Items
EXPERIMENTAL STUDY OF DAMAGED CR-COATED FUEL CLADDING IN POST-ACCIDENT CONDITIONS
by: Petr Červenka, et al.
Published: (2020-12-01)
by: Petr Červenka, et al.
Published: (2020-12-01)
COATED CLADDING BEHAVIOR DURING HIGH-TEMPERATURE TRANSIENTS
by: Adéla Chalupová, et al.
Published: (2019-12-01)
by: Adéla Chalupová, et al.
Published: (2019-12-01)
Impact of hydrogen on rupture behaviour of Zircaloy-4 nuclear fuel cladding during loss-of-coolant accident: a novel observation of failure at multiple locations
by: Siddharth Suman
Published: (2021-02-01)
by: Siddharth Suman
Published: (2021-02-01)
Influence of hydrogen concentration on burst parameters of Zircaloy-4 cladding tube under simulated loss-of-coolant accident
by: Siddharth Suman
Published: (2020-09-01)
by: Siddharth Suman
Published: (2020-09-01)
HIGH-TEMPERATURE OXIDATION OF CHROME-NICKEL ALLOY
by: Adéla Chalupová, et al.
Published: (2020-12-01)
by: Adéla Chalupová, et al.
Published: (2020-12-01)
Failure probability calculations of silicon carbide composite claddings under loss-of-coolant accidents
by: CAO Liwen, et al.
Published: (2023-09-01)
by: CAO Liwen, et al.
Published: (2023-09-01)
Comparison of two kinetic approaches for modeling of radial hydride fraction in zirconium-based fuel rod cladding
by: Mikhail Kolesnik
Published: (2025-07-01)
by: Mikhail Kolesnik
Published: (2025-07-01)
NANOINDENTATION OF HYDROGEN ENRICHED Zr-1Nb ZIRCONIUM ALLOY NUCLEAR FUEL CLADDINGS
by: Ondřej Libera, et al.
Published: (2020-06-01)
by: Ondřej Libera, et al.
Published: (2020-06-01)
Coupled Modeling and Simulation of Phase Transformation in Zircaloy-4 Fuel Cladding Under Loss-of-Coolant Accident Conditions
by: Wenjun Lu, et al.
Published: (2021-06-01)
by: Wenjun Lu, et al.
Published: (2021-06-01)
Axial strength of Zircaloy-4 samples with reduced thickness after a simulated loss of coolant accident
by: Jean Desquines, et al.
Published: (2021-07-01)
by: Jean Desquines, et al.
Published: (2021-07-01)
Electrochemical Formation of Hydride Phases on the Zirconium- 1% Niobium Alloy Used in Nuclear Fuel Cladding
by: I Moradi Gharatloo, et al.
Published: (2016-08-01)
by: I Moradi Gharatloo, et al.
Published: (2016-08-01)
Simulation method for secondary hydriding breakage of zirconium alloy cladding
by: MA Yan, et al.
Published: (2022-04-01)
by: MA Yan, et al.
Published: (2022-04-01)
Steam Oxidation of Silicon Carbide at High Temperatures for the Application as Accident Tolerant Fuel Cladding, an Overview
by: Hai V. Pham, et al.
Published: (2021-07-01)
by: Hai V. Pham, et al.
Published: (2021-07-01)
DEBRIS-FRETTING TEST OF COATED AND UNCOATED ZR-1%NB CLADDING
by: Marcin Kopeć, et al.
Published: (2019-12-01)
by: Marcin Kopeć, et al.
Published: (2019-12-01)
Understanding the role of hydrogen on creep behaviour of Zircaloy-4 cladding tubes using nanoindentation
by: Siddharth Suman
Published: (2020-09-01)
by: Siddharth Suman
Published: (2020-09-01)
Investigation on hydrogen embrittlement and failure characteristics of Zr-4 cladding based on the GTN method
by: Yangbin Deng, et al.
Published: (2023-09-01)
by: Yangbin Deng, et al.
Published: (2023-09-01)
DEMO Divertor Cassette and Plasma facing Unit in Vessel Loss-of-Coolant Accident
by: Danilo Nicola Dongiovanni, et al.
Published: (2022-11-01)
by: Danilo Nicola Dongiovanni, et al.
Published: (2022-11-01)
Accident Tolerant Fuel Cladding Materials for Light Water Reactors: Analysis of Neutronic Characteristics
by: Ferhat Aziz, et al.
Published: (2024-05-01)
by: Ferhat Aziz, et al.
Published: (2024-05-01)
Stress-induced Hydride Reorientation and Cracking in Fuel Cladding Tube
by: Albertas GRYBĖNAS, et al.
Published: (2014-12-01)
by: Albertas GRYBĖNAS, et al.
Published: (2014-12-01)
Development of FEMAXI-ATF for fuel performance modeling of SiC cladded fuel involving PCMI
by: Yoshihiro Kubo, et al.
Published: (2025-08-01)
by: Yoshihiro Kubo, et al.
Published: (2025-08-01)
Multivariate Time Series Prediction for Loss of Coolant Accidents With a Zigmoid-Based LSTM
by: Shanshan Gong, et al.
Published: (2022-04-01)
by: Shanshan Gong, et al.
Published: (2022-04-01)
Loss of Liquid Lithium Coolant in an Accident in a DONES Test Cell Facility
by: Danilo Nicola Dongiovanni, et al.
Published: (2021-10-01)
by: Danilo Nicola Dongiovanni, et al.
Published: (2021-10-01)
Hydrogen Embrittlement of Titanium: Phenomena and Main Ways of Prevention
by: V.A. Dekhtyarenko, T.V. Pryadko, О.І. Boshko, V.V. Kirilchuk, H.Yu. Mykhailova, and V.I. Bondarchuk
Published: (2024-06-01)
by: V.A. Dekhtyarenko, T.V. Pryadko, О.І. Boshko, V.V. Kirilchuk, H.Yu. Mykhailova, and V.I. Bondarchuk
Published: (2024-06-01)
Probabilistic Approach for Best Estimate of Fuel Rod Fracture During Loss-of-Coolant Accident
by: Hiroki Tanaka, et al.
Published: (2025-02-01)
by: Hiroki Tanaka, et al.
Published: (2025-02-01)
The impact of large-grained UO2 pellet and coated zirconium cladding on design criteria for PWR fuel rod
by: YOU Yan, et al.
Published: (2021-11-01)
by: YOU Yan, et al.
Published: (2021-11-01)
The effect of peak cladding temperature occurring during interim-dry storage on transport-induced cladding embrittlement
by: Kyu-Tae Kim
Published: (2020-07-01)
by: Kyu-Tae Kim
Published: (2020-07-01)
Applicability of Swaging as an Alternative for the Fabrication of Accident-Tolerant Fuel Cladding
by: Dae Yun Kim, et al.
Published: (2020-06-01)
by: Dae Yun Kim, et al.
Published: (2020-06-01)
Thermal hydraulic study of NuScale iPWR passive containment cooling behaviour during loss-of-coolant accident
by: Zhexi Guo, et al.
Published: (2025-06-01)
by: Zhexi Guo, et al.
Published: (2025-06-01)
Development and testing of multicomponent fuel cladding with enhanced accidental performance
by: Jakub Krejčí, et al.
Published: (2020-03-01)
by: Jakub Krejčí, et al.
Published: (2020-03-01)
Development of FEMAXI-ATF for analyzing PCMI behavior of SiC cladded fuel under power ramp conditions
by: Yoshihiro Kubo, et al.
Published: (2024-03-01)
by: Yoshihiro Kubo, et al.
Published: (2024-03-01)
Performance evaluation of Accident Tolerant Fuel under station blackout accident in PWR nuclear power plant by improved ISAA code
by: Bin Zhang, et al.
Published: (2022-07-01)
by: Bin Zhang, et al.
Published: (2022-07-01)
Benchmarking SiCf/SiC, FeCrAl, and Cr-coated Zr alloy claddings: evaluating thermomechanical properties and high-temperature oxidation resistance of next-generation nuclear claddings
by: Ghadeer Hegab Mohamed, et al.
Published: (2025-12-01)
by: Ghadeer Hegab Mohamed, et al.
Published: (2025-12-01)
Definition of parameters for a test section for the analysis of natural convection and coolant loss in the AP1000 nuclear reactor by similarity laws and fractional scaling analysis
by: Luis Felipe Serra Cadiz, et al.
Published: (2019-06-01)
by: Luis Felipe Serra Cadiz, et al.
Published: (2019-06-01)
Effect of Crystallographic Texture on Hydride Orientation in Zr-(1%)Nb Fuel Clad
by: Jalil Salehi, et al.
Published: (2014-08-01)
by: Jalil Salehi, et al.
Published: (2014-08-01)
3D Transient CFD Simulation of an In-Vessel Loss-of-Coolant Accident in the EU DEMO WCLL Breeding Blanket
by: Mauro Sprò, et al.
Published: (2023-04-01)
by: Mauro Sprò, et al.
Published: (2023-04-01)
Hydriding, Oxidation, and Ductility Evaluation of Cr-Coated Zircaloy-4 Tubing
by: Yong Yan, et al.
Published: (2022-11-01)
by: Yong Yan, et al.
Published: (2022-11-01)
Fragility and Leakage Risk Assessment of Nuclear Containment Structure under Loss-of-Coolant Accident Conditions Considering Liner Corrosion
by: Xinbo Li, et al.
Published: (2024-03-01)
by: Xinbo Li, et al.
Published: (2024-03-01)
FALCON code-based analysis of PWR fuel rod behaviour during RIA transients versus new U.S.NRC and current Swiss failure limits
by: G. Khvostov, et al.
Published: (2021-11-01)
by: G. Khvostov, et al.
Published: (2021-11-01)
Assessment of the core-catcher in the VVER-1000 reactor containment under various severe accidents
by: Farhad Salari, et al.
Published: (2023-01-01)
by: Farhad Salari, et al.
Published: (2023-01-01)
Safety Evaluation of Silicon Carbide and Zircaloy-4 Cladding during a Large-Break Loss-of-Coolant Accident
by: Kwangwon Ahn, et al.
Published: (2018-11-01)
by: Kwangwon Ahn, et al.
Published: (2018-11-01)
Similar Items
-
EXPERIMENTAL STUDY OF DAMAGED CR-COATED FUEL CLADDING IN POST-ACCIDENT CONDITIONS
by: Petr Červenka, et al.
Published: (2020-12-01) -
COATED CLADDING BEHAVIOR DURING HIGH-TEMPERATURE TRANSIENTS
by: Adéla Chalupová, et al.
Published: (2019-12-01) -
Impact of hydrogen on rupture behaviour of Zircaloy-4 nuclear fuel cladding during loss-of-coolant accident: a novel observation of failure at multiple locations
by: Siddharth Suman
Published: (2021-02-01) -
Influence of hydrogen concentration on burst parameters of Zircaloy-4 cladding tube under simulated loss-of-coolant accident
by: Siddharth Suman
Published: (2020-09-01) -
HIGH-TEMPERATURE OXIDATION OF CHROME-NICKEL ALLOY
by: Adéla Chalupová, et al.
Published: (2020-12-01)
