연구동향 분석

Development of mechanistic cladding rupture model for severe accident analysis and application in PHEBUS FPT3 experiment

Pengcheng Gao Bin Zhang Jishen Li Jianqiang Shan 2022년

논문상세정보
인용/피인용
' Development of mechanistic cladding rupture model for severe accident analysis and application in PHEBUS FPT3 experiment' 의 주제별 논문영향력
논문영향력 선정 방법
논문영향력 요약
주제
  • Cladding rupture
  • Code application & validation
  • Fuel behavior
  • PHEBUS FPT3
  • severe accident
동일주제 총논문수 논문피인용 총횟수 주제별 논문영향력의 평균
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' Development of mechanistic cladding rupture model for severe accident analysis and application in PHEBUS FPT3 experiment' 의 참고문헌

  • Transport and deposition in the Ph ebus FP circuit
    T. Haste [2013]
  • Thematic network for a phebus FPT-1 international standard problem
    B. Cl ement [2003]
  • Thematic network for a Phebus FPT1international standard problem(THENPHEBISP)
    B. Clement [2005]
  • The objectives of the Ph ebus FP experimental programme and main findings
    B. Cl ement [2013]
  • The fuel behaviour code FUROM and its high burn-up simulation capabilities
  • Simulation of the phebus FPT1 experiment with MELCOR 1.8.5
    M. Leskovar [2002]
  • Simulation OF the INpile behaviors evolution IN nuclear fuel rods with the irradiation damage effects
    Xin Gong [2014]
  • Severe accident phenomenology analyses and fission gas release in advanced nuclear reactors
  • Preliminary analyses of the phebus FPT3 experiment using severe accident codes (ATHLET-CD, ICARE/CATHARE, MELCOR)
  • Overview of the facility and experiments performed in Ph ebus FP
    P. March [2013]
  • Nuclear safety in light water reactors severe accident phenomeneology
  • Nuclear Safety Research : the Ph ebus FP severe accident experimental program
  • Nuclear Power Reactor Core Melt Accidents - Current State of Knowledge
    Irsn [2015]
  • Multi-dimensional simulation of LWR fuel behavior in the BISON fuel performance code
  • Module for thermomechanical modeling of LWR fuel in multiphysics simulations
    Timo Ikonen [2015]
  • Modeling burnup-induced fuel rod deformations and their effect on transient behavior of a VVER-440 reactor core
  • Model for melt blockage (slug) relocation and physico-chemical interactions during core degradation under severe accident conditions
  • Material Property Correlations:Comparisons between FRAPCON-4.0, FRAPTRAN-2.0, and MATPRO
  • MELCOR Computer Code Manuals Vol. 3: MELCOR Assessment Problems Version 2.1.7347
  • MELCOR Computer Code Manuals 1-2, version 1.8.6
  • MELCOR Best Practices as Applied in the State-Of-The-Art Reactor Consequence Analyses (SOARCA) Project
    Snl [2014]
  • MELCOR 2.2 Computer Code Manual - Volume 1 - User Guide
  • MELCOR 2.1 Computer Code Manual - Volume 3 - Code Assessment
  • L.L. Humphries
  • 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
    S. Suman [2021]
  • Final Report FPT1, PHEBUS PF, IPSN/JRC, Saint Paul-lez-Durance Cedex
  • FRAPTRAN-2.0: A Computer Code for the Transient Analysis of Oxide Fuel Rods
  • FRAPCON-4.0: A Computer Code for the Calculation of Steady-State, Thermal-Mechanical Behavior of Oxide Fuel Rods for High Burnup
    K. Geelhood [2015]
  • Division of Systems Analysis. Fuel Rod Behavior and Uncertainty Analysis by FRAPTRAN/TRACE/Dakota Code in Maanshan LBLOCA. Washington
  • Development of mechanistic cladding rupture model for integrated severe accident code ISAA. Part I : module verification and application in CAP1400
  • Development of MERCURY for simulation of multidimensional fuel behavior for LOCA condition
    H. Kim [2020]
  • DRACCAR: a multi-physics code for computational analysis of multi-rod ballooning, cool ability and fuel relocation during LOCA transients. Part Two: overview of modeling capabilities for LOCA
    T. Glantz [2018]
  • DEVELOPMENT OF MECHANISTIC CLADDING RUPTURE MODEL FOR SEVERE ACCIDENT ANALYSIS AND APPLICATION
    P. C. Gao [2020]
  • Core degradation simulation of the PHEBUS FPT3 experiment using COMPASS code
    Jun Ho Bae [2017]
  • Analysis of fuel rod behavior during loss-of-coolant accidents using the BISON code: cladding modeling developments and simulation of separate-effects experiments
  • Analysis of core degradation and fission products release in phebus FPT1 test at IRSN by detailed severe accidents analysis code, IMPACT/SAMPSON
    T. Ikeda [2003]
  • Accident Source Terms for Light-Water Nuclear Power Plants
    U.S. Nrc [1995]