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2 research outputs found

Modeling of distribution parameter, void fraction covariance and relative velocity covariance for upward steam-water boiling flow in vertical rod bundle

Author: Atomic Energy Society of Japan (AESJ)
Atomic Energy Society of Japan (AESJ)
Borkowski JA
Boyack B
Information System Laboratories (ISL)
Morooka S
Neykov B
Nuclear Power Engineering Corporation
Nuclear Power Engineering Test Center
Nylund O
Nylund O
Nylund O
Nylund O
Takashi Hibiki
Tetsuhiro Ozaki
U.S. NRC.
Publication venue: 'Informa UK Limited'
Publication date
Field of study

Development of drift-flux model based on 8 × 8 BWR rod bundle geometry experiments under prototypic temperature and pressure conditions

Author: Anoda Y
Atomic Energy Society of Japan
Borkowski J A
Boyack B
Chexal B
Deruaz R
Dreier J
Hiroyuki Mashiko
Information Systems Laboratories.
Inoue A
Ishii M
Ishii M
Ishii M.
Kondo M
Maier D
Morooka S
Nuclear Power Engineering Corporation
Nuclear Power Engineering Test Center
Paranjape S
Riichiro Suzuki
Sharma S L
Takashi Hibiki
Tetsuhiro Ozaki
US Nuclear Regulatory Commission
Publication venue: 'Informa UK Limited'
Publication date
Field of study

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