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Akimoto, Hajime
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Akimoto, Hajime
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1
Assessment of TRAC-BF1 1D reflood model with CCTF and SCTF data Hajime Akimoto ... [et al.].
by
Akimoto
,
Hajime
Published 1993
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2
Assessment of TRAC-PF1/MOD1 code for thermal-hydraulic behavior in pressure vessel during reflood in SCTF test with a radial power distribution Akira Ohnuki, Hajime Akimoto, Yoshio...
by
Ohnuki, Akira
Published 1993
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3
Critical heat flux of forced flow boiling in a narrow one-side heated rectangular flow channel Limin Zheng ... [et al.].
by
Zheng, Limin
Published 1997
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Hajime
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4
Evaluation report on CCTF core-II reflood test C2-1 (run 55) : effect of pressure on reflood phenomena Tadashi Iguchi ... [et al.].
by
Iguchi, Tadashi
Published 1991
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5
Evaluation report on CCTF core-II reflood test C2-15 (run 75) : investigation of flecht-set coupling test results Tsutomu Okubo ... [et al.].
by
Okubo, Tsutomu
Published 1992
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6
Evaluation report on SCTF core-III test S3-22 : investigation of water break-through and core cooling behaviors under alternate ECC water delivery from hot legs to upper plenum dur...
by
Okubo, Tsutomu
Published 1991
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Related Subjects
Reactor safety
Boiling Curve
Code simulation
Core Cooling
Gap Effect
Heat Transfer
One-side Heated Rectangular Channel
PWR
Quenching
Reflooding
Steam Binding
Void Fraction
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