-
1
-
-
0022705668
-
Analytical study on thermal-hydraulic behavior of transient from forced circulation to natural circulation in JRR-3
-
Hirano, M., Sudo, Y.: Analytical study on thermal-hydraulic behavior of transient from forced circulation to natural circulation in JRR-3, J. Nucl. Sci. Technol., 23[4], 352-368 (1986).
-
(1986)
J. Nucl. Sci. Technol.
, vol.23
, Issue.4
, pp. 352-368
-
-
Hirano, M.1
Sudo, Y.2
-
2
-
-
0022113482
-
Experimental study of differences in DNB heat flux between upflow and downflow in vertical rectangular channel
-
Sudo, Y., Miyata, K., Ikawa, H., Kaminaga, M., Ohkawara, M.: Experimental study of differences in DNB heat flux between upflow and downflow in vertical rectangular channel, J. Nucl. Sci. Technol., 22[8], 604-618 (1985).
-
(1985)
J. Nucl. Sci. Technol.
, vol.22
, Issue.8
, pp. 604-618
-
-
Sudo, Y.1
Miyata, K.2
Ikawa, H.3
Kaminaga, M.4
Ohkawara, M.5
-
3
-
-
0027591724
-
A new CHF correlation scheme proposed for vertical rectangular channels heated from both sides in nuclear research reactors
-
Sudo, Y., Kaminaga, M.: A new CHF correlation scheme proposed for vertical rectangular channels heated from both sides in nuclear research reactors, Trans. ASME, J. Heat Transfer, 115, 426-434 (1993).
-
(1993)
Trans. ASME, J. Heat Transfer
, vol.115
, pp. 426-434
-
-
Sudo, Y.1
Kaminaga, M.2
-
4
-
-
0022099750
-
Core ther-mohydraulic design with 20% LEU fuel for upgraded research reactor JRR-3
-
Sudo, Y., Ando, H., Ikawa, H., Ohnishi, N.: Core ther-mohydraulic design with 20% LEU fuel for upgraded research reactor JRR-3, J. Nucl. Sci. Technol., 22[7], 551-564 (1985).
-
(1985)
J. Nucl. Sci. Technol.
, vol.22
, Issue.7
, pp. 551-564
-
-
Sudo, Y.1
Ando, H.2
Ikawa, H.3
Ohnishi, N.4
-
5
-
-
11544307167
-
Steady-state thermal hydraulic analysis and flow blockage accident analysis of JRR-4 silicide LEU core
-
[in Japanese]
-
Kaminaga, M., Yamamoto, K., Watanabe, S.: Steady-state thermal hydraulic analysis and flow blockage accident analysis of JRR-4 silicide LEU core, JAERI-Tech 96-039, (1996), [in Japanese].
-
(1996)
JAERI-Tech 96-039
-
-
Kaminaga, M.1
Yamamoto, K.2
Watanabe, S.3
-
6
-
-
11544369759
-
Safety analysis of JMTR-LEU cores (1)— Reactivity initiated accident analysis
-
Nagaoka Y., Komukai, B., Sakurai, F., Saito, M., Fu-tamura, Y.: Safety analysis of JMTR-LEU cores (1)— Reactivity initiated accident analysis, JAERI-M 92-095, (1992), [in Japanese]
-
(1992)
JAERI-M 92-095
-
-
Nagaoka, Y.1
Komukai, B.2
Sakurai, F.3
Saito, M.4
Fu-Tamura, Y.5
-
8
-
-
0025789222
-
Experimental study of the critical heat flux in a narrow vertical rectangular channel
-
Kaminaga, M., Sudo, Y., Murayama, Y., Usui, T.: Experimental study of the critical heat flux in a narrow vertical rectangular channel, Heat Transfer-Japanese Res., 20[1], 72-85 (1991).
-
(1991)
Heat Transfer-Japanese Res.
, vol.20
, Issue.1
, pp. 72-85
-
-
Kaminaga, M.1
Sudo, Y.2
Murayama, Y.3
Usui, T.4
-
9
-
-
85007693463
-
Experimental study of differences in CHF between upflow and downflow in vertical rectangular channels (Effect of subcooling)
-
[in Japanese]
-
Kaminaga, M., Sudo, Y.: Experimental study of differences in CHF between upflow and downflow in vertical rectangular channels (Effect of subcooling), Trans. JSME., Ser. B, 58[553], 2799-2804 (1992), [in Japanese].
-
(1992)
Trans. JSME., Ser. B
, vol.58
, Issue.553
, pp. 2799-2804
-
-
Kaminaga, M.1
Sudo, Y.2
-
10
-
-
11544314660
-
THYDE-W: RCS (reactor-coolant system) analysis code
-
Asahi, Y., Matsumoto, K., Hirano, M.: THYDE-W: RCS (reactor-coolant system) analysis code, JAERI-M 90-172, (1990).
-
(1990)
JAERI-M
, pp. 90-172
-
-
Asahi, Y.1
Matsumoto, K.2
Hirano, M.3
|