文献
J-GLOBAL ID:201702257739523692
整理番号:17A1171822
加圧鉛直円環チャネル内のサブクール沸騰流の局所気泡パラメータの実験的評価【Powered by NICT】
Experimental evaluation of local bubble parameters of subcooled boiling flow in a pressurized vertical annulus channel
著者 (7件):
Chu In-Cheol
(Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yuseong-gu, Daejeon 303-353, Republic of Korea)
,
Lee Seung-Jun
(Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yuseong-gu, Daejeon 303-353, Republic of Korea)
,
Youn Young Jung
(Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yuseong-gu, Daejeon 303-353, Republic of Korea)
,
Park Jong Kuk
(Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yuseong-gu, Daejeon 303-353, Republic of Korea)
,
Choi Hae Seob
(Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yuseong-gu, Daejeon 303-353, Republic of Korea)
,
Euh Dong-Jin
(Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yuseong-gu, Daejeon 303-353, Republic of Korea)
,
Song Chul-Hwa
(Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yuseong-gu, Daejeon 303-353, Republic of Korea)
資料名:
Nuclear Engineering and Design
(Nuclear Engineering and Design)
巻:
312
ページ:
172-183
発行年:
2017年
JST資料番号:
E0189B
ISSN:
0029-5493
資料種別:
逐次刊行物 (A)
記事区分:
原著論文
発行国:
オランダ (NLD)
言語:
英語 (EN)