Proceeding of Advanced Course in Heat Transfer in Nuclear Reactor Safety
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Published By Begellhouse

9780891162230

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1.8 Emergency Cooling Heat Transfer Problem of Nuclear Reactors

Proceeding of Advanced Course in Heat Transfer in Nuclear Reactor Safety ◽

10.1615/ichmt.1982.advcourheattransfnucreactsaf.90 ◽

1980 ◽

Author(s):

N. G. Rassohin

Keyword(s):

Heat Transfer ◽

Nuclear Reactors ◽

Transfer Problem ◽

Heat Transfer Problem

2.2 Steady and Unsteady Film Boiling Heat Transfer at Subatmospheric and Elevated Pressures

Proceeding of Advanced Course in Heat Transfer in Nuclear Reactor Safety ◽

10.1615/ichmt.1982.advcourheattransfnucreactsaf.140 ◽

1980 ◽

Cited By ~ 2

Author(s):

Akira Sakurai ◽

Masahiro Shiotsu ◽

Koichi Hata

Keyword(s):

Heat Transfer ◽

Boiling Heat Transfer ◽

Film Boiling ◽

Elevated Pressures

1.9 An Assessment of LMFBR Safety

Proceeding of Advanced Course in Heat Transfer in Nuclear Reactor Safety ◽

10.1615/ichmt.1982.advcourheattransfnucreactsaf.100 ◽

1980 ◽

Author(s):

Hans K. Fauske

4.7 Predictions of GKSS 3-Vent Tests with the Integral-Code DRASYS for Pressure Suppression Systems

Proceeding of Advanced Course in Heat Transfer in Nuclear Reactor Safety ◽

10.1615/ichmt.1982.advcourheattransfnucreactsaf.430 ◽

1980 ◽

Author(s):

B. Schwinges

Keyword(s):

Suppression Systems

4.5 Effect of Confinement in Rewetting Phenomena

Proceeding of Advanced Course in Heat Transfer in Nuclear Reactor Safety ◽

10.1615/ichmt.1982.advcourheattransfnucreactsaf.410 ◽

1980 ◽

Author(s):

Y. P. Lee ◽

A. Kim ◽

S. Y. Shim

4.2 Reduced Scale, Semi-Quantitative Modelling of Accident Behaviour in Water Reactor Primary Circuits Using Refrigerant 12

Proceeding of Advanced Course in Heat Transfer in Nuclear Reactor Safety ◽

10.1615/ichmt.1982.advcourheattransfnucreactsaf.380 ◽

1980 ◽

Author(s):

M. W. E. Coney

Keyword(s):

Quantitative Modelling ◽

Water Reactor ◽

Reduced Scale

3.9 Boiling Water Reactor LOCA/ECCS Integral Tests at ROSA-III Facility of JAERI

Proceeding of Advanced Course in Heat Transfer in Nuclear Reactor Safety ◽

10.1615/ichmt.1982.advcourheattransfnucreactsaf.350 ◽

1980 ◽

Cited By ~ 2

Author(s):

Kunihisa Soda ◽

Kanji Tasaka ◽

Masayoshi Shiba

Keyword(s):

Boiling Water ◽

Boiling Water Reactor ◽

Water Reactor

2.13 Breakdown and Evaporation of Thin Shear Driven Liquid Films

Proceeding of Advanced Course in Heat Transfer in Nuclear Reactor Safety ◽

10.1615/ichmt.1982.advcourheattransfnucreactsaf.250 ◽

1980 ◽

Author(s):

Jerzy R. Moszynski ◽

Jaroslaw Mikielewicz

Keyword(s):

Liquid Films

2.10 A Review on Gas-Liquid Countercurrent Flow through Multiple Paths

Proceeding of Advanced Course in Heat Transfer in Nuclear Reactor Safety ◽

10.1615/ichmt.1982.advcourheattransfnucreactsaf.220 ◽

1980 ◽

Author(s):

C. P. Liu ◽

Chang-Lin Tien

Keyword(s):

Countercurrent Flow ◽

Multiple Paths ◽

Flow Through

2.9 Critical Flow of Flashing Water through Long Tubes

Proceeding of Advanced Course in Heat Transfer in Nuclear Reactor Safety ◽

10.1615/ichmt.1982.advcourheattransfnucreactsaf.210 ◽

1980 ◽

Author(s):

Jean-Marie Seynhaeve ◽

M. Giot

Keyword(s):

Critical Flow

Proceeding of Advanced Course in Heat Transfer in Nuclear Reactor SafetyLatest Publications

TOTAL DOCUMENTS

H-INDEX

Published By Begellhouse

1.8 Emergency Cooling Heat Transfer Problem of Nuclear Reactors

2.2 Steady and Unsteady Film Boiling Heat Transfer at Subatmospheric and Elevated Pressures

1.9 An Assessment of LMFBR Safety

4.7 Predictions of GKSS 3-Vent Tests with the Integral-Code DRASYS for Pressure Suppression Systems

4.5 Effect of Confinement in Rewetting Phenomena

4.2 Reduced Scale, Semi-Quantitative Modelling of Accident Behaviour in Water Reactor Primary Circuits Using Refrigerant 12

3.9 Boiling Water Reactor LOCA/ECCS Integral Tests at ROSA-III Facility of JAERI

2.13 Breakdown and Evaporation of Thin Shear Driven Liquid Films

2.10 A Review on Gas-Liquid Countercurrent Flow through Multiple Paths

2.9 Critical Flow of Flashing Water through Long Tubes

Proceeding of Advanced Course in Heat Transfer in Nuclear Reactor Safety
Latest Publications