CRP Publications
Type
Conference proceedings
Year
2024
Description
Juri Stuckert, et al., IAEA ATF-TS benchmark for simulation of bundle tests, Proceedings of the TopFuel 2024 conference, 2024
Country/Organization
KIT (Germany), HUN-REN EK, IAEA
Type
Conference proceedings
Year
2024
Description
Kinya Nakamura, Kenta Inagaki, Naoki Tarumi, Juri Stuckert, Martin ?evecek, BEHAVIOR OF BUNDLES WITH CR COATED CLADDINGS UNDER BDBA CONDITIONS AT THE DEGREE FACILITY, Proc. TOPFUEL 2024, Grenoble, France, 29 September - 3 October 2024
Country/Organization
CRIEPI (Japan), KIT (Germany), CTU (Czech Republic)
Type
Conference proceedings
Year
2024
Description
Z. Hózer, R. Farkas, N. Vér, B. Bürger: CODEX-ATF: Integral Bundle Test With Accident Tolerant Fuel, Proceedings of TOPFUEL 2024, Grenoble, ENS Tolerant Fuel, Proceedings of TOPFUEL 2024, Grenoble, ENS
Country/Organization
HUN-REN Centre for Energy Research
Type
Journal paper
Year
2023
Publication URL
https://www.sciencedirect.com/science/article/pii/S0022311523001757
Description
J. Hong et al., Measurement of local mechanical properties for Cr-coated accident tolerant fuel cladding, Journal of Nuclear Materials 579 (2023) 154407 Description: Micro mechanical properties of Cr-coated layer fabricated by CTU in the frame of ATF-TS has been investigated using micro indentation method.
Country/Organization
Korea Atomic Energy Research Institute
Type
Conference paper (Joint article with Centre for Energy Research, Budapest, Hungary)
Year
2023
Description
INNOVATIVE HIGH TEMPERATURE BALLOONING AND BURST TESTS OF CLADDING MATERIALS ; 2023 WATER REACTOR FUEL PERFORMANCE MEETING; Xi'an, China. (Paper No. WRFPM 2023-0002)
Country/Organization
Atomic Energy Organization of Iran (AEOI)
Type
Conference proceedings
Year
2022
Description
J. Zhang, T. Drieu (Tractebel, Belgium), “FRAPTRAN-TE-1.5 Simulation of the Halden LOCA Tests IFA-650.9 and 10: Impact of Model Options and Assumptions,” In ANS Proc. Top Fuel 2022, October 9–13, 2022, Raleigh, NC, USA, ANS, 2022
Country/Organization
Tractebel (Belgium)
Type
Journal paper
Year
2022
Description
Study on the production of Cr-coated Zr-1%Nb tubes as an ATF evolutionary cladding candidate. In this study, an optimized cathodic arc PVD (ARC-PVD) coating condition, from the coating layer homogeneity and defect density point of views, have been obtained. Two coating material (i.e., pure Chromium and Chromium Nitride) with thicknesses up to 10 microns on typical VVER-1000 cladding tubes (Zr-1%Nb alloy) are developed. Presented SEM results approved improvements in coatings visual properties, and further modifications have been postponed until finalizing the performance examinations in normal operational as well as accidental conditions (LB LOCA). Eventually, the general list of planned tests, from characterizations to mechanical and performance viewpoints, which are currently being carried out, is reported.
Country/Organization
Atomic Energy Organization of Iran (AEOI)
Type
Journal publication
Year
2024
Description
J. Zhang, P. Xu, M. Sevecek, K. S. Sim, and A. Khaperskaia, “Contribution of IAEA coordinated research projects to light water reactors advanced technology fuel testing and simulation,” Nuclear Engineering and Design, vol. 418, p. 112910, Mar. 2024,
Country/Organization
Tractebel (Belgium), CTU (Czech Republic), IAEA
Type
Journal publication
Year
2024
Description
Juri Stuckert, et al., Post-quench ductility limits of coated ATF with various zirconium-based alloys and coating designs, Article in "Journal of Nuclear Materials", 2024.
Country/Organization
KIT (Germany), CTU (Czech Republic), SNU (China)
Type
Conference proceedings
Year
2023
Publication URL
https://publikationen.bibliothek.kit.edu/1000165938
Description
Róbert Farkas, Nóra Vér, Berta Bürger, Péter Szabó, Zoltán Hózer: The CODEX-ATF Experiment, 28th International QUENCH Workshop
Country/Organization
HUN-REN Centre for Energy Research
Type
Conference proceedings
Year
2024
Description
J. Gomez-Magan, C. Queral, J. Sanchez-Torrijos, A. Soler, T. Drieu, J. Zhang, J.M. Posada, “Generation of the Thermal-Hydraulic Boundary Conditions to be Used for a BEPU LBLOCA Fuel Safety Evaluation with Fuel Rod Codes,” ENS Transactions of TopFuel 2024, Grenoble, France, 29 September - 3 October 2024.
Country/Organization
Tractebel (Belgium), UPM (Spain)
Type
Conference proceedings
Year
2024
Description
Kinya Nakamura, Kenta Inagaki, Naoki Tarumi, Juri Stuckert, Martin ?evecek, Behaviour of Cr-coated cladding bundles under BDBA conditions at the DEGREE facility, 29th International QUENCH Workshop, Karlsruhe Institute of Technology, Campus North, Germany, 19-21 November 2024. DOI: 10.5445/IR/1000177365.
Country/Organization
CRIEPI (Japan), KIT (Germany), CTU (Czech Republic)
Type
conference paper
Year
2023
Description
Investigation of Thermal Creep properties of Chromium Coated Cladding with MERCURY, published on Trans of the Korean Nuclear Society Spring Meeting, 2023
Country/Organization
Korea/KAERI
Type
Proceeding
Year
2024
Publication URL
https://www.euronuclear.org/topfuel-2024/
Description
S.Lee et al., CALIBRATION FOR THERMAL CREEP PROPERTIES OF Cr COATED CLADDING WITH MERCURY AND ISIGHT, Topfuel2024, Grenoble, France, 2024.10 Description: Thermal creep coefficients of coated layer from ATF-TS has been derived using MERCURY and ISIGHT and validated against experimental data.
Country/Organization
Korea Atomic Energy Research Institute
Type
Conference proceedings
Year
2024
Description
J. Zhang, M. ?evecek, K. Sim, A. Khaperskia, “ATF-TS: IAEA Coordinated Research Project on Testing and Simulations for Accident Tolerant and Advanced Technology Fuels,” ENS Transactions of TopFuel 2024, Grenoble, France, 29 September - 3 October 2024
Country/Organization
Tractebel (Belgium), CTU (Czech Republic), IAEA
Type
Conference proceedings
Year
2024
Description
J. Zhang, T. Drieu, K. Sim, A. Khaperskia, “Development of a Fuel Safety Evaluation Methodology for Assessing the Performance of ATFs under Loss-Of-Coolant Accidents,” ENS Transactions of TopFuel 2024, Grenoble, France, 29 September - 3 October 2024
Country/Organization
Tractebel (Belgium), IAEA
Type
Conference paper
Year
2025
Description
Ensayos de compresión diametral en vainas de combustible nuclear avanzado cromadas, Conference paper submitted to the 50th anual meeting of the spanish nuclear society
Country/Organization
UPM-Caminos
Type
Proceeding
Year
2023
Publication URL
https://www.kns.org/
Description
H.Kim et al., Experiment, modeling and evaluation of ATF in the frame of IAEA CRP ATF-TS, Transactions of the Korean Nuclear Society Autumn Meeting, Gyeongju, Korea, October 26-27, 2023 Description: KAERI’s contribution in the ATF-TS has been introduced.
Country/Organization
Korea Atomic Energy Research Institute
Type
Conference paper ( TOP FUEL)
Year
2024
Description
CIEMAT’s main outcomes of the LOCA fuel safety evaluation methodology for ATF performance in the IAEA/CRP ATF-TS.
Country/Organization
CIEMAT
Type
Conference paper
Year
2023
Description
Hidruración de vainas ATF con recubrimiento de Cr; Conference paper submitted to the 48th anual meeting of the Spanish nuclear society
Country/Organization
UPM-Caminos
Type
Journal paper (PNE)
Year
2023
Publication URL
https://doi.org/10.1016/j.pnucene.2023.104838
Description
Modelling FeCrAl cladding thermo-mechanical performance. Part II: Comparative analysis with Zircaloy under LOCA conditions
Country/Organization
CIEMAT
Type
Journal publication
Year
2024
Description
Juri Stuckert, et al., An Overview of Mechanisms of the Degradation of Promising ATF Cladding Materials During Oxidation at High Temperatures, Article in "High Temperature Corrosion of Materials", 2024
Country/Organization
KIT (Germany)
Type
Conference proceedings
Year
2024
Description
T. Drieu, G. Vandenwegh, J. Zhang, “Predicting LOCA Fuel Behaviors of Advanced Technology Fuels with Chromium-Coated Cladding Using the FRAPTRAN-TE-1.5 Code,” ENS Transactions of TopFuel 2024, Grenoble, France, 29 September - 3 October 2024
Country/Organization
Tractebel (Belgium), UPM (Spain)
Type
Conference proceedings
Year
2024
Description
Juri Stuckert, et al., Limiting degradation mechanisms for high-temperature oxidation resistance of promising ATF cladding solutions, Proceedings of the TopFuel 2024 conference, 2024.
Country/Organization
KIT (Germany),
Type
Proceeding
Year
2024
Description
H.Kim et al., Sensitivity analysis and uncertainty analysis of IFA-650.9 using MERCURY, EHPG2024, Loen, Norway, 2024. Description: Sensitivity and uncertainty analysis methodology for MERCURY has been developed and SA/UA of IFA-650.9 using MERCURY has been conducted based on ATF-TS data.
Country/Organization
Korea Atomic Energy Research Institute
Type
Journal paper
Year
2024
Publication URL
https://doi.org/10.1016/j.nme.2024.101799
Description
J. Hong et al., Micro-mechanical evaluations of adhesion properties for Cr-coated accident tolerant fuel cladding, Nuclear Materials and Energy 41 (2024) 101799 Description: Adhesion properties of Cr-coated layer fabricated by CTU in the frame of ATF-TS has been investigated using micro-mechanical tests
Country/Organization
Korea Atomic Energy Research Institute
Type
Conference proceedings
Year
2024
Description
Kinya Nakamura, Kenta Inagaki, Juri Stuckert, Martin ?evecek, Behavior of chromium-coated zirconium alloy fuel rods in simulated beyond design basis accident (2) Comparison of single layer Cr and bi-layer Cr/CrN coated Zircaloy-4 fuel bundles, 2024 Fall meeting of Atomic Energy Society of Japan, 3N03, Tohoku University, Japan, 11-13 September 2024.
Country/Organization
CRIEPI (Japan), KIT (Germany), CTU (Czech Republic)
Type
Conference paper ( NuMat 2022)
Year
2022
Description
Analysis of FeCrAl cladding thermo-mechanical performance under LOCA conditions.
Country/Organization
CIEMAT
Type
Conference proceedings
Year
2024
Description
. Zhang, P. Xu, K. Sim, M. Veshchunov and A. Khaperskaia, “From FUMAC and ACTOF to ATF-TS: Contribution of IAEA CRPs to Advanced Technology Fuel Testing, Modelling and Simulation,” In Proc. Of Top Fuel 2022, October 9–13, 2022, Raleigh, NC, USA, ANS, 2022
Country/Organization
Tractebel (Belgium), INL (USA), IAEA
Type
Conference paper (Top Fuel)
Year
2024
Description
Hot rod thermo-mechanical assessment of Cr-coated Zircaloy in accident scenarios with FRAPTRAN-TUmech.
Country/Organization
CIEMAT
Type
Proceeding
Year
2023
Publication URL
https://www.kns.org/
Description
J.Oh et al., Effect of fission gas diffusivity of dopant in Cr2O3 doped UO2 pellet, Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 18-19, 2023 Description: Fission gas release model of the doped pellet has been developed and implemented based on ATF-TS database.
Country/Organization
Korea Atomic Energy Research Institute
Type
Conference paper (Top Fuel)
Year
2023
Description
Progress on modelling the thermo-mechanical performance of accident-tolerant fuels.
Country/Organization
CIEMAT
Type
Journal paper (PNE)
Year
2022
Publication URL
https://doi.org/10.1016/j.pnucene.2022.104417
Description
Modelling FeCrAl cladding thermo-mechanical performance. Part I: Steady-state conditions
Country/Organization
CIEMAT
Type
Proceeding
Year
2023
Publication URL
https://www.kns.org/
Description
S.Lee et al., Investigation of thermal creep properties of chromium coated cladding with MERCURY, Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 18-19, 2023 Description: Thermal creep properties of Cr-coated layer fabricated by CTU in the frame of ATF-TS has been derived using MERCURY and the properties have been shared with participants.
Country/Organization
Korea Atomic Energy Research Institute
Type
Journal paper (NED)
Year
2025
Description
Modelling FeCrAl cladding thermo-mechanical performance: CIEMAT’s contribution to IAEA/CRP ATF-TS
Country/Organization
CIEMAT
Type
Conference paper
Year
2024
Description
Integridad estructural de vainas de combustible ATF; Conference paper submitted to the 50th anual meeting of the spanish nuclear society
Country/Organization
UPM-Caminos
Type
Conference proceedings
Year
2023
Description
Kinya Nakamura, Kenta Inagaki, Juri Stuckert, Martin ?evecek, Behavior of chromium-coated zirconium alloy fuel rods in simulated beyond design basis accident, 2023 Annual meeting of Atomic Energy Society of Japan, 2F15, Tokyo University, Japan, 13-15 March 2023.
Country/Organization
CRIEPI (Japan), KIT (Germany), CTU (Czech Republic)
Type
Proceeding
Year
2023
Publication URL
https://virtual.oxfordabstracts.com/#/event/public/3997/
Description
J. Hong et al., Evaluation of adhesion properties of Cr coated accident tolerant fuel cladding, Materials Today Conference 2023, Aug. 2-5, Singapore. Description: Adhesion properties of Cr-coated layer fabricated by CTU in the frame of ATF-TS has been investigated using micro-cantilever bending tests.
Country/Organization
Korea Atomic Energy Research Institute
Type
Proceeding
Year
2024
Publication URL
https://www.euronuclear.org/topfuel-2024/
Description
C.Shin et al., THE SENSITIVITY ANALYSIS AND UNCERTAINTY ANALYSIS FOR ACCIDENT TOLERANT FUEL WITH MERCURY CODE IN IAEA-CRP ATF-TS, Topfuel2024, Grenoble, France, 2024.10 Description: The sensitivity analysis and uncertainty analysis has been carried out for NPP safety analysis with accident tolerant fuel models
Country/Organization
Korea Atomic Energy Research Institute
Type
conference paper
Year
2022
Description
FRAPTRAN-TE-1.5 Simulation of the Halden LOCA Tests IFA-650.9 and 10: Impact of Model Options and Assumptions, presented at TOPFUEL 2022
Country/Organization
Belgium/TRACTEBEL
Type
conference paper
Year
2022
Description
From FUMAC and ACTOF to ATF-TS: Contribution of IAEA CRPs to Advanced Technology Fuel Testing, Modelling and Simulation, presented at TOPFUEL 2022.
Country/Organization
Belgium/TRACTEBEL
Type
journal article
Year
Measurement of Local Mechanical Properties for Cr-Coated Accident Tolernt Fuel Cladding, published on J. of Nuclear Materials 579 (2023) 154407
Country/Organization
Korea/KAERI
Type
Conference proceedings
Year
2024
Description
J. Zhang and T. Drieu, "Establishing a LOCA Fuel Safety Evaluation Methodology for Assessment of Advanced Technology Fuel Performance Using FRAPTRAN-TE-1.5", Proc. 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-14), Vancouver, BC, Canada, August 25 – 28, 2024.
Country/Organization
Tractebel (Belgium),
Type
journal article
Year
2022
Description
Multi-Elemental Coatings on Zirconium Alloy for Corrosion Resistance Improvement, published on Coatings 2022, 12, 1112.
Country/Organization
Poland/INCT
