JOPSS - Search Results

Journal Articles

Two-dimensional fall back flow and core cooling in the slab core test facility: SCTF

; ; ;

Proc.2nd Int.Topical Meeting on Nuclear Power Plant Thermal Hydraulics and Operations, p.2 - 129, 1986/00

no abstracts in English

Journal Articles

Recent study on two-dimensional thermal-hydraulic behavior in PWR core during the reflood phase of LOCA with the slab core test facility:SCTF

; ; ; ; ; Murao, Yoshio

Proc.2nd Int.Topical Meeting on Nuclear Power Plant Thermal Hydraulics and Operations, p.2 - 104, 1986/00

no abstracts in English

Journal Articles

Effect of pressure on slugging in steam/water two-phase flow in a large diameter horizontal pipe

; ; ; Koizumi, Yasuo; Tasaka, Kanji

Proc.2nd Int.Topical Meeting on Nuclear Power Plant Thermal Hydraulics and Operations, p.1 - 102, 1986/00

no abstracts in English

Journal Articles

The Dynamics of natural-circulation flow in a bent loop with a U-shaped type cooler; A simple nonlinear analysis

*; *; ; *; Hashimoto, Kazunori*;

Proc.2nd Int.Topical Meeting on Nuclear Power Plant Thermal Hydraulics and Operations, p.2 - 33, 1986/00

no abstracts in English

Journal Articles

Development of a two-dimensional core-wide heat-up code MUFLAR and its applicataion to analysis of TMI-2 core damage behavior

; ; *; *; *

Proc.2nd Int.Topical Meeting on Nuclear Power Plant Thermal Hydraulics and Operations, p.6 - 41, 1986/00

no abstracts in English

Journal Articles

Assessment of current safety evaluation analysis on the reflood phase during a LOCA in a PWR with the cold leg injection type ECCS, 1; System behavior

Murao, Yoshio; ; ; ; ; *

Proc.2nd Int.Topical Meeting on Nuclear Power Plant Thermal Hydraulics and Operations, p.2 - 82, 1986/00

no abstracts in English

Journal Articles

Analysis of LSTF 10% cold leg break experiment by RELAP5/MOD1 and MOD2

; Osakabe, Masahiro; Koizumi, Yasuo; Tasaka, Kanji

Proc.2nd Int.Topical Meeting on Nuclear Power Plant Thermal Hydraulics and Operations, p.2 - 210, 1986/00

no abstracts in English

Journal Articles

Evaluation of interfacial shear model for bubbly flow regime with the MINCS code

Hirano, Masashi; ; ; ; *; *; *;

Proc.2nd Int.Topical Meeting on Nuclear Power Plant Thermal Hydraulics and Operations, p.1 - 80, 1986/00

no abstracts in English

Journal Articles

Development of transient two-phase flow analyzer:MINCS

; Hirano, Masashi; ; ; *; *; *

Proc.2nd Int.Topical Meeting on Nuclear Power Plant Thermal Hydraulics and Operations, p.1 - 72, 1986/00

no abstracts in English

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Two-dimensional fall back flow and core cooling in the slab core test facility: SCTF

Recent study on two-dimensional thermal-hydraulic behavior in PWR core during the reflood phase of LOCA with the slab core test facility:SCTF

Effect of pressure on slugging in steam/water two-phase flow in a large diameter horizontal pipe

The Dynamics of natural-circulation flow in a bent loop with a U-shaped type cooler; A simple nonlinear analysis

Development of a two-dimensional core-wide heat-up code MUFLAR and its applicataion to analysis of TMI-2 core damage behavior

Assessment of current safety evaluation analysis on the reflood phase during a LOCA in a PWR with the cold leg injection type ECCS, 1; System behavior

Analysis of LSTF 10% cold leg break experiment by RELAP5/MOD1 and MOD2

Evaluation of interfacial shear model for bubbly flow regime with the MINCS code

Development of transient two-phase flow analyzer:MINCS