연구동향 분석

Study on the effect of flow blockage due to rod deformation in QUENCH experiment

Gao Pengcheng Zhang Bin Shan Jianqiang 2022년

논문상세정보
인용/피인용
' Study on the effect of flow blockage due to rod deformation in QUENCH experiment' 의 주제별 논문영향력
논문영향력 선정 방법
논문영향력 요약
주제
  • Code application & validation
  • Flow blockage
  • Fuel behavior
  • Peak cladding temperature
  • QUENCH-LOCA-0
동일주제 총논문수 논문피인용 총횟수 주제별 논문영향력의 평균
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' Study on the effect of flow blockage due to rod deformation in QUENCH experiment' 의 참고문헌

  • reliminary Analysis of Air Ingress Experiment QUENCH-16 Using RELAP/SCDAPSim3.5 and MELCOR 1.8.6
  • Validation of ASTECV2.1 based on the QUENCH-08 experiment
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    Y. Guo [2018]
  • The R&D PERFROI project on Thermal mechanical and thermal hydraulics behaviors of a fuel rod assembly during a Loss of Coolant Accident
    G. Repetto [2015]
  • Recent Revisions to MAAP4 for US EPR Severe Accident Applications
    E. Williams [2008]
  • RELAP5/MOD3 Code Manual
  • Preliminary safety analysis on loss of flow accidents and external source transients for LBE cooled ADSR core
    T. Lu [2016]
  • Nuclear Fuel Behaviour in Loss-Of-Coolant Accident (LOCA) Conditions, State-of-the-art Report
  • Natural convection of melted core at the bottom of nuclear reactor vessel in a severe accident
    H. K. Park [2018]
  • Measurements of the Length Changes of UO2 Fuel Pellets during Irradiation
    E. Rolstad [1974]
  • Material Property Correlations:Comparisons between FRAPCON-4.0, FRAPTRAN-2.0, and MATPRO
  • MELCOR Computer Code Manuals 1-2, Version 1.8.6, Sandia National Laboratories
  • International Energy Outlook 2016
    J. Conti [2016]
  • Handbook of Hydraulic Resistance
  • Experimental thermal hydraulics study of the blockage ratio effect during the cooling of a vertical tube with an internal steam-droplets flow
    B. Jdpca [2019]
  • Experimental Results of the Commissioning Bundle Test QUENCH-L0 Performed in the Framework of the QUENCH-LOCA Program
    J. Stuckert [2015]
  • Development of mechanistic cladding rupture model for integrated severe accident code ISAA
  • Coolability of blocked regions in a rod bundle after ballooning under LOCA conditions
  • Application of thermal hydraulic and severe accident code SOCRAT/V3 to bottom water reflood experiment QUENCH-LOCA-0
  • Application of Best Estimate Approach for Modelling of QUENCH-03 and QUENCH-06 Experiments
  • Analysis of QUENCH-10 and -16 air ingress experiments with SCDAPSim3.5
  • Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors, 10 Code of Federal Register, Part 50
  • ASTEC V2 severe accident integral code main features, current V2.0 modelling status, perspectives
  • A newly developed suppression pool model based on the ISAA code
    B. Zhang [2021]
  • A State-Of-The-Art Review of Past Programs Devoted to Fuel Behaviour under LOCA Conditions - Part One: Clad Swelling and Rupture Assembly Flow Blockage