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          Testing and Simulation for Advanced Technology and Accident Tolerant Fuels (ATF-TS)

          Closed for Proposals

          Project Type

          Coordinated Research Project

          Project Code

          T12032

          CRP

          2236

          Approved Date

          2019/12/12

          Project Status

          Closed

          Start Date

          2020/04/06

          Expected End Date

          2024/12/31

          Completed Date

          2025/05/26

          Participating Countries

          Argentina, Belgium, Bulgaria, Brazil, Belarus, Canada, China, Czech Republic, Germany, Spain, France, United Kingdom of Great Britain and Northern Ireland, Hungary, Iran, Islamic Republic of, Italy, Japan, Republic of Korea, Poland, Russian Federation, Slovakia, United States of America

          Description

          The proposed CRP will support interested IAEA Member States in their efforts to design and develop Accident Tolerant and Advanced Technology Fuels (ATF) for light water reactors (LWRs) to enhance the safety and sustainability of nuclear power. The design, fabrication and in-pile behaviour of currently operated and innovative nuclear fuels and materials to enable a reliable and safe operation of nuclear power plants is a recurrent priority of IAEA’s sub-programme "Nuclear Power Reactor Fuel Engineering". Development and validation of computer codes for fuel design and in-pile behaviour analysis under normal and off-normal conditions (including Design Extension Conditions, DEC) are possible only if high-quality experimental data are made available. That is why international cooperation in this area is highly desirable, and in particular among IAEA Member States interested in enhancing their computer code capabilities to predict nuclear fuel behaviour under Design Basis (DB) and Design Extension (DE) Conditions.
          The CRP will bring together specialists from IAEA MSs with active ATF R&D programmes to share their national efforts and to?contribute in any of the following objectives of the CRP:
          Round Robin tests on different ATF cladding concepts (e.g. coated Zr cladding, FeCrAl, SiC);
          Bundle tests under DB/DEC with ATF materials (e.g. with coated Zry-4 rods under SA and/or LOCA conditions);
          Collection of irradiation tests data;
          Code benchmarking against existing data, relevant for advanced fuel and cladding concepts from other experimental Programmes, as well as new tests data obtained during the CRP;
          LOCA evaluation methodology development for NPP applications including uncertainty and sensitivities studies.

          Objectives

          To support Member States to understand and address factors affecting the design, fabrication and in-pile behaviour of currently operating and innovative nuclear fuels and materials for power reactors, to increase technology readiness for candidate ATF materials.

          Specific Objectives

          To perform experimental tests including single rod and bundle tests on ATFs' performance under normal, DB and DE conditions

          To benchmark fuel codes against new test data either obtained during the CRP or from existing data relevant to advanced fuel and cladding concepts from Member States' experimental Programmes.

          To develop LOCA evaluation methodology for ATF performance with a view for NPP applications.

          To perform experimental tests including single rod and bundle tests on ATFs' performance under normal, DB and DE conditions

          To benchmark fuel codes against new test data either obtained during the CRP or from existing data relevant to advanced fuel and cladding concepts from Member States' experimental Programmes.

          To develop LOCA evaluation methodology for ATF performance with a view for NPP applications.

          Impact

          The CRP efficiently supported the participating Member States in their efforts to analyse and better understand the behavior of accident tolerant fuels in both normal operation and accident conditions through producing and sharing experimental data and best practices in application of fuel modelling computer codes.
          A dynamic network of experts has been established to continue to address the technical issues associated with ATF materials and application of fuel performance codes and SA codes to ATFs.

          Relevance

          ? There is a growing interest from MSs in the deployment of ATF fuel materials to enhance the safety and sustainability of nuclear power, but limited number of experimental datasets, fuel behavior codes and published benchmark exercises exist
          ? The CRP enhanced Member States' capabilities in modelling, predicting and improving the understanding of the behaviour of nuclear fuel, in response to Member States' request expressed in Resolution GC(68)/RES/11, Paragraphs B.3.3, B.3.8 , B.6.17 and B.8.10.
          ? It also contributed to the objective of the IAEA Project 1.2.2.001: Nuclear power reactor fuel engineering and performance, to support IAEA Member States to understand and address factors affecting the design, fabrication and in-pile behaviour of currently operated and innovative nuclear fuels and materials for power reactors.

          CRP Publications

          KIT (Germany), CRIEPI, CTU, IAEA
          Conference proceedings
          2024
          Juri Stuckert, et al., Behavior of bundles with Cr coated claddings under BDBA conditions at the DEGREE facility, Proceedings of the TopFuel 2024 conference, 2024.
          CRIEPI (Japan), KIT (Germany), CTU (Czech Republic)
          Conference proceedings
          2024
          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.
          Korea Atomic Energy Research Institute
          Journal paper
          2024
          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
          CIEMAT
          Conference paper ( TOP FUEL)
          2024
          CIEMAT’s main outcomes of the LOCA fuel safety evaluation methodology for ATF performance in the IAEA/CRP ATF-TS.
          KIT (Germany)
          Journal publication
          2024
          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
          KIT (Germany), HUN-REN EK, IAEA
          Conference proceedings
          2024
          Juri Stuckert, et al., IAEA ATF-TS benchmark for simulation of bundle tests, Proceedings of the TopFuel 2024 conference, 2024
          Korea Atomic Energy Research Institute
          Proceeding
          2024
          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
          UPM-Caminos
          Conference paper
          2024
          Integridad estructural de vainas de combustible ATF; Conference paper submitted to the 50th anual meeting of the spanish nuclear society
          KIT (Germany),
          Conference proceedings
          2024
          Juri Stuckert, et al., Limiting degradation mechanisms for high-temperature oxidation resistance of promising ATF cladding solutions, Proceedings of the TopFuel 2024 conference, 2024.
          Korea Atomic Energy Research Institute
          Proceeding
          2023
          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.
          CIEMAT
          Journal paper (PNE)
          2022
          Modelling FeCrAl cladding thermo-mechanical performance. Part I: Steady-state conditions
          Tractebel (Belgium), UPM (Spain)
          Conference proceedings
          2024
          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
          Korea Atomic Energy Research Institute
          Proceeding
          2024
          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.
          HUN-REN Centre for Energy Research
          Conference proceedings
          2024
          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
          KIT (Germany), CTU (Czech Republic), SNU (China)
          Journal publication
          2024
          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.
          UPM-Caminos
          Conference paper
          2024
          Mechanical behaviour of Cr-coated ATF cladding; Conference paper submitted to the Top-Fuel Conference. European Nuclear Society
          Tractebel (Belgium), INL (USA), IAEA
          Conference proceedings
          2024
          . 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
          Poland/INCT
          journal article
          2022
          Multi-Elemental Coatings on Zirconium Alloy for Corrosion Resistance Improvement, published on Coatings 2022, 12, 1112.
          HUN-REN Centre for Energy Research
          Conference proceedings
          2023
          Róbert Farkas, Nóra Vér, Berta Bürger, Péter Szabó, Zoltán Hózer: The CODEX-ATF Experiment, 28th International QUENCH Workshop
          Korea/KAERI
          journal article
          Measurement of Local Mechanical Properties for Cr-Coated Accident Tolernt Fuel Cladding, published on J. of Nuclear Materials 579 (2023) 154407
          Korea Atomic Energy Research Institute
          Proceeding
          2023
          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.
          CRIEPI (Japan), KIT (Germany), CTU (Czech Republic)
          Conference proceedings
          2024
          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.
          CRIEPI (Japan), KIT (Germany), CTU (Czech Republic)
          Conference proceedings
          2023
          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.
          Tractebel (Belgium), IAEA
          Conference proceedings
          2024
          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
          Tractebel (Belgium), CTU (Czech Republic), IAEA
          Journal publication
          2024
          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,
          Tractebel (Belgium), UPM (Spain)
          Conference proceedings
          2024
          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.
          CIEMAT
          Journal paper (PNE)
          2023
          Modelling FeCrAl cladding thermo-mechanical performance. Part II: Comparative analysis with Zircaloy under LOCA conditions
          Atomic Energy Organization of Iran (AEOI)
          Conference paper (Joint article with Centre for Energy Research, Budapest, Hungary)
          2023
          INNOVATIVE HIGH TEMPERATURE BALLOONING AND BURST TESTS OF CLADDING MATERIALS ; 2023 WATER REACTOR FUEL PERFORMANCE MEETING; Xi'an, China. (Paper No. WRFPM 2023-0002)
          UPM-Caminos
          Scientific Paper
          2024
          R&D in advanced technology fuels (ATFs) in Spain
          CIEMAT
          Journal paper (NED)
          2025
          Modelling FeCrAl cladding thermo-mechanical performance: CIEMAT’s contribution to IAEA/CRP ATF-TS
          CIEMAT
          Conference paper ( NuMat 2022)
          2022
          Analysis of FeCrAl cladding thermo-mechanical performance under LOCA conditions.
          CIEMAT
          Conference paper (Top Fuel)
          2024
          Hot rod thermo-mechanical assessment of Cr-coated Zircaloy in accident scenarios with FRAPTRAN-TUmech.
          CIEMAT
          Conference paper (Top Fuel)
          2023
          Progress on modelling the thermo-mechanical performance of accident-tolerant fuels.
          Korea Atomic Energy Research Institute
          Proceeding
          2023
          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.
          UPM-Caminos
          Conference paper
          2025
          Ensayos de compresión diametral en vainas de combustible nuclear avanzado cromadas, Conference paper submitted to the 50th anual meeting of the spanish nuclear society
          Korea Atomic Energy Research Institute
          Proceeding
          2024
          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.
          CRIEPI (Japan), KIT (Germany), CTU (Czech Republic)
          Conference proceedings
          2024
          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
          Belgium/TRACTEBEL
          conference paper
          2022
          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
          Korea Atomic Energy Research Institute
          Proceeding
          2023
          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.
          Belgium/TRACTEBEL
          conference paper
          2022
          From FUMAC and ACTOF to ATF-TS: Contribution of IAEA CRPs to Advanced Technology Fuel Testing, Modelling and Simulation, presented at TOPFUEL 2022.
          Korea Atomic Energy Research Institute
          Journal paper
          2023
          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.
          KIT (Germany), CTU (Czech Republic), IAEA
          Conference proceedings
          2024
          Juri Stuckert, et al., Experimental programme within the IAEA ATF-TS - separate effect and bundle tests with ATF cladding materials, Proceedings of the TopFuel 2024 conference, 2024
          Tractebel (Belgium), CTU (Czech Republic), IAEA
          Conference proceedings
          2024
          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
          Atomic Energy Organization of Iran (AEOI)
          Journal paper
          2022
          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.
          Korea/KAERI
          conference paper
          2023
          Investigation of Thermal Creep properties of Chromium Coated Cladding with MERCURY, published on Trans of the Korean Nuclear Society Spring Meeting, 2023
          UPM-Caminos
          Conference paper
          2023
          Hidruración de vainas ATF con recubrimiento de Cr; Conference paper submitted to the 48th anual meeting of the Spanish nuclear society
          Tractebel (Belgium),
          Conference proceedings
          2024
          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.
          Tractebel (Belgium)
          Conference proceedings
          2022
          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

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