Search Results1-20 of  20

  • DODA NORIHIRO ID: 9000392095064

    Japan Atomic Energy Agency (2010 from CiNii)

    Articles in CiNii:1

    • Development of Evaluation Methods for Decay Heat Removal by Natural Circulation under Transient Conditions:(17)Development of Evaluation Methods for Hot Spot in Core (5th Report) (2010)
  • DODA NORIHIRO ID: 9000392099211

    Japan Atomic Energy Agency (2009 from CiNii)

    Articles in CiNii:1

    • Development of Evaluation Methods for Decay Heat Removal by Natural Circulation under Transient Conditions:(10) Development of evaluation methods for the hot spot temperature in core (3rd Report) (2009)
  • DODA NORIHIRO ID: 9000392118964

    JAEA (2010 from CiNii)

    Articles in CiNii:1

    • Development of Evaluation Methods for Decay Heat Removal by Natural Circulation under Transient Conditions:(11) Development of Evaluation Methods for Hot Spot in Core (4th Report) (2010)
  • DODA NORIHIRO ID: 9000392128141

    JAEA (2012 from CiNii)

    Articles in CiNii:1

    • Development of Natural Circulation Evaluation Methods for Decay Heat Removal System:(5)In-core Hot Spot Evaluation Method (2nd report):Sensitivity Analysis of Uncertainty Contributors (2012)
  • DODA NORIHIRO ID: 9000392130008

    Japan Atomic Energy Agency (2011 from CiNii)

    Articles in CiNii:1

    • Development of Natural Circulation Evaluation Methods for Decay Heat Removal System:(2) In-core Hot Spot Evaluation Method (1st Report) : Development of PIRT for Stochastic Evaluation (2011)
  • DODA Norihiro ID: 9000000327132

    Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology (2001 from CiNii)

    Articles in CiNii:1

    • Prediction of Release Rate of Burnt Sodium as Aerosol (2001)
  • DODA Norihiro ID: 9000001696966

    Japan Nuclear Cycle Development Institute, O-arai Engineering Center (2003 from CiNii)

    Articles in CiNii:1

    • Sodium Leak and Fire Control in Fast Breeder Reactors (2003)
  • DODA Norihiro ID: 9000016507459

    Japan Atomic Energy Agency (2012 from CiNii)

    Articles in CiNii:6

    • Development of Core Hot Spot Evaluation Method for Decay Heat Removal by Natural Circulation under Transient Conditions in Sodium-Cooled Fast Reactor(<Special Issue>The 14th National Symposium on Power and Energy System) (2010)
    • E204 Development of Core Hot Spot Evaluation Method for Decay Heat Removal by Natural Circulation under Transient Conditions in Sodium-cooled Fast Reactor (2009)
    • 908 Development of Evaluation Method for Hot Spot in Core of Fast Reactor under Natural Circulation (2009)
  • DODA Norihiro ID: 9000019981065

    Japan Atomic Energy Agency (2012 from CiNii)

    Articles in CiNii:1

    • Development of PIRT for Fast Reactor under Natural Circulation Decay Heat Removal Operations (2012)
  • DODA Norihiro ID: 9000020017692

    Japan Atomic Energy Agency (2012 from CiNii)

    Articles in CiNii:1

    • Numerical Analysis of JOYO MK-II Natural Circulation Test with Fast Reactor Plant Dynamics Code Super-COPD (2012)
  • DODA Norihiro ID: 9000305621411

    Japan Atomic Energy Agency (2011 from CiNii)

    Articles in CiNii:1

    • ICONE19-44124 Development of PIRT for Fast Reactor under Natural Circulation Decay Heat Removal Operations (2011)
  • DODA Norihiro ID: 9000350559199

    Japan Atomic Energy Agency (2017 from CiNii)

    Articles in CiNii:1

    • Study on applicability of fast reactor plant dynamics analysis code to core thermal hydraulics under natural circulation decay heat removal conditions (2017)
  • DODA Norihiro ID: 9000392095028

    JAEA (2010 from CiNii)

    Articles in CiNii:1

    • Development of Super-COPD Code for Plant Dynamics:(IX) Numerical Simulation of Natural Circulation Test in JOYO with MK-II Core (2010)
  • DODA Norihiro ID: 9000392121063

    Japan Atomic Energy Agency (2011 from CiNii)

    Articles in CiNii:1

    • Numerical Analysis of JOYO MK-II Natural Circulation Test with Plant Dynamics Code Super-COPD (2011)
  • DODA Norihiro ID: 9000392125851

    JAEA (2011 from CiNii)

    Articles in CiNii:1

    • Development of Super-COPD Code for Plant Dynamics:(X) Numerical Simulation of Natural Circulation Test in JOYO with MK-II Core (2nd Report) (2011)
  • DODA Norihiro ID: 9000392413641

    Japan Atomic Energy Agency (2016 from CiNii)

    Articles in CiNii:1

    • Validation of plant dynamics analysis code for fast reactor core thermal hydraulics under natural circulation conditions (2016)
  • DODA Norihiro ID: 9000399363015

    Japan Atomic Energy Agency (2018 from CiNii)

    Articles in CiNii:1

    • Development of Numerical Analysis Method for Core Thermal-hydraulics during Natural Circulation Decay Heat Removal in SFR:(1) Validation of ASFRE Code in Estimation of Radial Heat Transfer Phenomena (2018)
  • Doda Norihiro ID: 9000258304574

    Japan Atomic Energy Agency (2013 from CiNii)

    Articles in CiNii:1

    • Mixing Factor for Sub-channel Analysis of Wire-Wrapped Large Diameter Fuel Pin Bundle of Sodium-cooled Fast Reactors:Effects of Wire-wrap Lead Length (2013)
  • Doda Norihiro ID: 9000392094146

    Japan Atomic Energy Agency (2009 from CiNii)

    Articles in CiNii:1

    • Development of evaluation methods for decay heat removal by natural circulation under transient conditions:(2)Development of evaluation methods for hot spot in core (2nd Report) (2009)
  • Doda Norihiro ID: 9000392128245

    Japan Atomic Energy Agency (2012 from CiNii)

    Articles in CiNii:1

    • Mixing Factor for Sub-channel Analysis of Wire-Wrapped Large-Diameter Fuel Pin Bundle:- Analyses on Re number dependency - (2012)
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