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      KCI등재 SCIE SCOPUS

      Ductile tearing criteria and failure probability estimation of hydrided Zircaloy-4 cladding under axial loads

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      https://www.riss.kr/link?id=A108580197

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      다국어 초록 (Multilingual Abstract)

      To maintain a safe management of spent nuclear fuel (SNF), it is necessary to understand the characteristics of fuel cladding associated with material degradation and failure criteria. This study aims to establish strain-based failure criteria for Zir...

      To maintain a safe management of spent nuclear fuel (SNF), it is necessary to understand the characteristics of fuel cladding associated with material degradation and failure criteria. This study aims to establish strain-based failure criteria for Zircaloy-4 cladding from uniaxial tensile tests considering hydride distribution. An investigation of the hydrogen effect on mechanical properties of cladding was presented using the design of experiment method. The applicability of the proposed criteria for transverse tearing failure mode was demonstrated in energy-limited events using finite element analysis. The failure probabilities of cladding were estimated for normal transportation and hypothetical accident conditions. The proposed failure criteria provide an advancement on the existing studies that only implemented transverse tearing failure mode by considering hydride distribution. This effort could be particularly valuable to the regulatory institutes and those utility planners who are evaluating structural integrity concerning the critical characteristics of SNF for potential licensing considerations.

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      참고문헌 (Reference) 논문관계도

      1 "U.S. NRC Interim StaffGuidance-11 Rev. 3, Cladding Considerations for the Transportation and Storage of Spent Fuel"

      2 "U.S. NRC 10 CFR Part 72, Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater than Class c Waste"

      3 "U.S. NRC 10 CFR Part 71, Packaging and Transportation of Radioactive Material"

      4 방신효 ; 김호아 ; 노재수 ; 김동욱 ; 금경환 ; 이유호, "Temperature-dependent axial mechanical properties of Zircaloy-4 with various hydrogen amounts and hydride orientations" 한국원자력학회 54 (54): 1579-1587, 2022

      5 "Standard Review Plan for Dry Cask Storage Systems" U. S. Nuclear Regulatory Commission 1997

      6 A. J. Machiels, "Spent Fuel Transportation Applications: Global Forces Acting on Spent Fuel Rods and Deformation Patterns Resulting from Transportation Accidents" EPRI 2005

      7 R. James, "Spent Fuel Transportation Applications: Fuel Rod Failure Evaluation under Simulated Cask Side Drop Conditions" EPRI 2005

      8 J. Rashid, "Spent Fuel Transportation Applications-Assessment of Cladding Performance: A Synthesis Report" EPRI 2007

      9 국동학 ; 최종원 ; 김주성 ; 김용수, "Review of Spent Fuel Integrity Evaluation for Dry Storage" 한국원자력학회 45 (45): 115-124, 2013

      10 IAEA Safety Standards, "Regulations for the Safe Transport of Radioactive Material" 2012

      1 "U.S. NRC Interim StaffGuidance-11 Rev. 3, Cladding Considerations for the Transportation and Storage of Spent Fuel"

      2 "U.S. NRC 10 CFR Part 72, Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater than Class c Waste"

      3 "U.S. NRC 10 CFR Part 71, Packaging and Transportation of Radioactive Material"

      4 방신효 ; 김호아 ; 노재수 ; 김동욱 ; 금경환 ; 이유호, "Temperature-dependent axial mechanical properties of Zircaloy-4 with various hydrogen amounts and hydride orientations" 한국원자력학회 54 (54): 1579-1587, 2022

      5 "Standard Review Plan for Dry Cask Storage Systems" U. S. Nuclear Regulatory Commission 1997

      6 A. J. Machiels, "Spent Fuel Transportation Applications: Global Forces Acting on Spent Fuel Rods and Deformation Patterns Resulting from Transportation Accidents" EPRI 2005

      7 R. James, "Spent Fuel Transportation Applications: Fuel Rod Failure Evaluation under Simulated Cask Side Drop Conditions" EPRI 2005

      8 J. Rashid, "Spent Fuel Transportation Applications-Assessment of Cladding Performance: A Synthesis Report" EPRI 2007

      9 국동학 ; 최종원 ; 김주성 ; 김용수, "Review of Spent Fuel Integrity Evaluation for Dry Storage" 한국원자력학회 45 (45): 115-124, 2013

      10 IAEA Safety Standards, "Regulations for the Safe Transport of Radioactive Material" 2012

      11 K. J. Geelhood, "PNNL Stress/Strain Correlation for Zircaloy" Pacific Northwest National Laboratory (PNNL) 2008

      12 A. T. Motta, "Hydrogen in zirconium alloys : a review" 518 : 440-460, 2019

      13 B. Almomani, "Failure probability assessment of SNF cladding transverse tearing under a hypothetical transportation accident" 379 : 111265-, 2021

      14 S. Kang, "Comparative stress analyses of dropped spent nuclear fuel assembly in a prototypal cask" ASME 2020

      15 "ASTM E8/E8M-21, Standard Test Methods for Tension Testing of Metallic Materials"

      16 ABAQUS, "ABAQUS User’s Manual Ver. 2020" Dassault Systemes 2020

      17 E. Eidelpes, "A probabilistic assessment of PWR SNF pinching failure considering hydride-related cladding embrittlement" 351 : 116-130, 2019

      18 E. Eidelpes, "A probabilistic assessment of PWR SNF cladding pinching failure considering potential transportation accident conditions" 358 : 110423-, 2020

      19 T. L. Sanders, "A Method for Determining the Spent-Fuel Contribution to Transport Cask Containment Requirements" Sandia National Labs 1992

      20 N. A. Klymyshyn, "30 cm Drop Modeling" Pacific Northwest National Laboratory 2020

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