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      KCI등재 SCIE SCOPUS

      Spent fuel simulation during dry storage via enhancement of FRAPCON-4.0: Comparison between PWR and SMR and discharge burnup effect

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      https://www.riss.kr/link?id=A108368213

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      다국어 초록 (Multilingual Abstract)

      Spent fuel behavior of dry storage was simulated in a continuous state from steady-state operation by modifying FRAPCON-4.0 to incorporate spent fuelespecific fuel behavior models. Spent fuel behavior of a typical PWR was compared with that of NuScale Power Module (NPM™). Current PWR discharge burnup (60 MWd/kgU) gives a sufficient margin to the hoop stress limit of 90 MPa. Most hydrogen precipitation occurs in the first 50 years of dry storage, thereby no extra phenomenological safety factor is identified for extended dry storage up to 100 years. Regulation for spent fuel management can be significantly alleviated for LWR-based SMRs. Hydride embrittlement safety criterion is irrelevant to NuScale spent fuels; they have sufficiently lower plenum pressure and hydrogen contents compared to those of PWRs.
      Cladding creep out during dry storage reduces the subchannel area with burnup. The most deformed cladding outer diameter after 100 years of dry storage is found to be 9.64 mm for discharge burnup of 70 MWd/kgU. It may deteriorate heat transfer of dry storage by increasing flow resistance and decreasing the view factor of radiative heat transfer. Self-regulated by decreasing rod internal pressure with opening gap, cladding creep out closely reaches the saturated point after ~50 years of dry storage.
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      Spent fuel behavior of dry storage was simulated in a continuous state from steady-state operation by modifying FRAPCON-4.0 to incorporate spent fuelespecific fuel behavior models. Spent fuel behavior of a typical PWR was compared with that of NuScale...

      Spent fuel behavior of dry storage was simulated in a continuous state from steady-state operation by modifying FRAPCON-4.0 to incorporate spent fuelespecific fuel behavior models. Spent fuel behavior of a typical PWR was compared with that of NuScale Power Module (NPM™). Current PWR discharge burnup (60 MWd/kgU) gives a sufficient margin to the hoop stress limit of 90 MPa. Most hydrogen precipitation occurs in the first 50 years of dry storage, thereby no extra phenomenological safety factor is identified for extended dry storage up to 100 years. Regulation for spent fuel management can be significantly alleviated for LWR-based SMRs. Hydride embrittlement safety criterion is irrelevant to NuScale spent fuels; they have sufficiently lower plenum pressure and hydrogen contents compared to those of PWRs.
      Cladding creep out during dry storage reduces the subchannel area with burnup. The most deformed cladding outer diameter after 100 years of dry storage is found to be 9.64 mm for discharge burnup of 70 MWd/kgU. It may deteriorate heat transfer of dry storage by increasing flow resistance and decreasing the view factor of radiative heat transfer. Self-regulated by decreasing rod internal pressure with opening gap, cladding creep out closely reaches the saturated point after ~50 years of dry storage.

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      참고문헌 (Reference)

      1 G. Sabol, "Zirconium in the Nuclear Industry : Twelfth International Symposium" ASTM International 2000

      2 E. Gilbert, "Update of CSFM Methodology for Determining Temperature Limits for Spent Fuel Dry Storage in Inert Gas" Pacific Northwest Lab 2001

      3 J. A. Fort, "Thermal Modeling of the TN-32B Cask for the High Burnup Spent Fuel Data Project" Pacific Northwest National Lab.(PNNL) 2019

      4 S. Bang, "Temperature-dependent Axial Mechanical Properties of Zircaloy-4 with Various Hydrogen Amounts and Hydride Orientations" Elsevier 2022

      5 ARIS, "Technical data"

      6 Maciej Serda, "Synteza i aktywno s c biologiczna nowych analog ow tiosemikarbazonowych chelator ow _ zelaza" 343-354, 2013

      7 Y. Kim, "Stress and temperature-dependent hydride reorientation of Zircaloy-4 cladding and its effect on the ductility degradation" 52 : 717-727, 2015

      8 P. Konarski, "Spent Nuclear Fuel in Dry Storage ConditionseCurrent Trends in Fuel Performance Modeling" Elsevier 2021

      9 J. H€am€al€ainen, "SAFIR2018-The Finnish Research Programme on Nuclear Power Plant Safety 2015-2018: Interim Report" VTT Technical Research Centre of Finland 387-, 2017

      10 V. V Rondinella, "Properties and Behaviour of Irradiated Fuel under Accident Conditions" International Atomic Energy Agency (IAEA) 2012

      1 G. Sabol, "Zirconium in the Nuclear Industry : Twelfth International Symposium" ASTM International 2000

      2 E. Gilbert, "Update of CSFM Methodology for Determining Temperature Limits for Spent Fuel Dry Storage in Inert Gas" Pacific Northwest Lab 2001

      3 J. A. Fort, "Thermal Modeling of the TN-32B Cask for the High Burnup Spent Fuel Data Project" Pacific Northwest National Lab.(PNNL) 2019

      4 S. Bang, "Temperature-dependent Axial Mechanical Properties of Zircaloy-4 with Various Hydrogen Amounts and Hydride Orientations" Elsevier 2022

      5 ARIS, "Technical data"

      6 Maciej Serda, "Synteza i aktywno s c biologiczna nowych analog ow tiosemikarbazonowych chelator ow _ zelaza" 343-354, 2013

      7 Y. Kim, "Stress and temperature-dependent hydride reorientation of Zircaloy-4 cladding and its effect on the ductility degradation" 52 : 717-727, 2015

      8 P. Konarski, "Spent Nuclear Fuel in Dry Storage ConditionseCurrent Trends in Fuel Performance Modeling" Elsevier 2021

      9 J. H€am€al€ainen, "SAFIR2018-The Finnish Research Programme on Nuclear Power Plant Safety 2015-2018: Interim Report" VTT Technical Research Centre of Finland 387-, 2017

      10 V. V Rondinella, "Properties and Behaviour of Irradiated Fuel under Accident Conditions" International Atomic Energy Agency (IAEA) 2012

      11 F. Feria, "On the Way to Enabling FRAPCON-3 to Model Spent Fuel under Dry Storage Conditions: the Thermal Evolution" Elsevier 2015

      12 N. E. Todreas, "Nuclear Systems Volume II : Elements of Thermal Hydraulic Design" CRC Press 2021

      13 NuScale Power, "NuFuel-HTP2™ Fuel and Control Rod Assembly Designs" NuScale Power, LLC 2017

      14 P. Bouffioux, "Interim dry storage of PWR spent fuel assemblies: development of a long term creep law to assess the fuel cladding integrity" 201-205, 2020

      15 W. Lyon, "Impact of fuel-cladding bonding on the response of high burnup spent fuel subjected to transportation accidents" 2018

      16 S. Kim, "Hydride Embrittlement Resistance of Zircaloy-4 and Zr-Nb Alloy Cladding Tubes and its Implications on Spent Fuel Management" Elsevier 2022

      17 K. J. Geelhood, "FRAPCON-4.0: A Computer Code for the Calculation of Steady-State, Thermal-Mechanical Behavior of Oxide Fuel Rods for High Burnup, vol. 1" Pacific Northwest National Laboratory 2015

      18 International Atomic Energy Agency, "Durability of Spent Nuclear Fuels and Facility Components in Wet Storage" International Atomic Energy Agency (IAEA) 1998

      19 D. Kim, "Development of an Image Analysis Code for Hydrided Zircaloy Using Dijkstra's Algorithm and Sensitivity Analysis of Radial Hydride Continuous Path" Elsevier 2022

      20 GLYN ROSSITER, "DEVELOPMENT OF THE ENIGMA FUEL PERFORMANCE CODE FOR WHOLE CORE ANALYSIS AND DRY STORAGE ASSESSMENTS" 한국원자력학회 43 (43): 489-498, 2011

      21 E. P. Simonen, "DATING: A Computer Code for Determining Allowable Temperatures for Dry Storage of Spent Fuel in Inert and Nitrogen Gases" Pacific Northwest Lab 1988

      22 Y. Rashid, "Creep Modeling and Analysis Methodology for Spent Fuel in Dry Storage" Electric Power Research Institute 2001

      23 P. A. C. Raynaud, "Cladding stress during extended storage of high burnup spent nuclear fuel" 464 : 304-312, 2015

      24 U.S. NRC, "Cladding considerations for the transportation and storage of spent fuel"

      25 L. E. Herranz, "CFD analysis of a cask for spent fuel dry storage : model fundamentals and sensitivity studies" 76 : 54-62, 2015

      26 A. Mieloszyk, "An Improved Structural Mechanics Model for the FRAPCON Nuclear Fuel Performance Code" Massachusetts Institute of Technology 2012

      27 D. Kim, "Accurate Prediction of Threshold Stress for Hydride Reorientation in Zircaloy-4 with Directly Measured Interface Orientation Relationship" Elsevier 2022

      28 김주성 ; 윤학규 ; 국동학 ; 김용수, "A Study on the Initial Characteristics of Domestic Spent Nuclear Fuels for Long Term Dry Storage" 한국원자력학회 45 (45): 377-384, 2013

      29 G. M. O'Donnell, "A New Comparative Analysis of LWR Fuel Designs" Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear 2001

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