-
1
-
-
0002521134
-
Design concept of once-through cycle supercritical-pressure light water cooled reactors
-
Tokyo, Japan, Nov. 6-9, 2000
-
stInt. Symp. on Supercritical Water Cooled Reactors, Design and Technology, Tokyo, Japan, Nov. 6-9, 2000, p. 1 (2000).
-
(2000)
Proc. 1St Int. Symp. On Super critical Water Cooled Reactors, Design and Technology
, pp. 1
-
-
Oka, Y.1
Koshizuka, S.2
-
2
-
-
85010620313
-
Elements of design consideration of once-through cycle, supercritical-pressure light water cooled reactor
-
Hollywood, Florida, June 913, 2002, Sec. 3.04
-
Y. Oka, S. Koshizuka, Y. Ishiwatari, A. Yamaji, “Elements of design consideration of once-through cycle, supercritical-pressure light water cooled reactor,” Proc. Int. Conf. on Advanced Nuclear Power Plants (ICAPP), Hollywood, Florida, June 913, 2002, Sec. 3.04 (2002).
-
(2002)
Proc. Int. Conf. On Advanced Nuclear Power Plants (ICAPP)
-
-
Oka, Y.1
Koshizuka, S.2
Ishiwatari, Y.3
Yamaji, A.4
-
3
-
-
2642533248
-
Conceptual core design of a 1000 MWe supercritical-pressure light water cooled and moderated reactor
-
March 29-April 1, 2001, Texas, USA
-
A. Yamaji, Y. Oka, S. Koshizuka, “Conceptual core design of a 1000 MWe supercritical-pressure light water cooled and moderated reactor,” Proc. Am. Nucl. Soc. and Health Phys. Soc. Student Conf., March 29-April 1, 2001, Texas, USA, (2001).
-
(2001)
Proc. Am. Nucl. Soc. And Health Phys. Soc. Student Conf
-
-
Yamaji, A.1
Oka, Y.2
Koshizuka, S.3
-
4
-
-
84933180751
-
Progress of development project of supercritical water cooled power reactor, 2003
-
Cordoba, Spain, May 4-7, 2003, Paper
-
K. Kataoka, S. Shiga, K. Moriya, et al., “Progress of development project of supercritical water cooled power reactor, 2003,” Proc. Int. Conf. on Advanced Nuclear Power Plants (ICAPP), Cordoba, Spain, May 4-7, 2003, Paper 3258 (2003).
-
(2003)
Proc. Int. Conf. On Advanced Nuclear Power Plants (ICAPP)
, pp. 3258
-
-
Kataoka, K.1
Shiga, S.2
Moriya, K.3
-
5
-
-
0035364256
-
‘Startup thermal considerations for supercritical pressure light water cooled reactors
-
T. Nakatsuka, Y. Oka, S. Koshizuka, “Startup thermal considerations for supercritical pressure light water cooled reactors, '' Nucl. Technol., 134, 221 (2000).
-
(2000)
Nucl. Technol.
, vol.134
, pp. 221
-
-
Nakatsuka, T.1
Oka, Y.2
Koshizuka, S.3
-
6
-
-
33644565901
-
Control and Startup of supercritical-pressure light water cooled reactors
-
T. Nakatsuka, “Control and Startup of supercritical-pressure light water cooled reactors,” Ph.D. thesis, University of Tokyo, Japan, 1999 (1999).
-
(1999)
Ph.D. Thesis, University of Tokyo, Japan
, pp. 1999
-
-
Nakatsuka, T.1
-
7
-
-
85010554992
-
Stability analysis of supercritical pressure light water cooled reactor in constant pressure operation
-
Nice, France, April 8-12, 2001, ASME, ICONE-9306
-
S. Ji, H. Shirahama, S. Koshizuka, Y. Oka, “Stability analysis of supercritical pressure light water cooled reactor in constant pressure operation,” Proc. Ninth Int. Conf. on Nuclear Engineering, Nice, France, April 8-12, 2001, ASME, ICONE-9306, (2001).
-
(2001)
Proc. Ninth Int. Conf. On Nuclear Engineering
-
-
Tin Tin Yi, Y.1
Ji, S.2
Shirahama, H.3
Koshizuka, S.4
Oka, Y.5
-
8
-
-
2642525335
-
Preliminary stability analysis for supercritical water reactors
-
New Orleans, November 16-20, 2003
-
W. S. Yang, N. Navaljevski, “Preliminary stability analysis for supercritical water reactors,” Proc. Global 2003, New Orleans, November 16-20, 2003, p. 1772 (2003).
-
(2003)
Proc. Global 2003
, pp. 1772
-
-
Yang, W.S.1
Navaljevski, N.2
-
9
-
-
0029395125
-
Numerical analysis of deterioration phenomena in heat transfer to supercritical water
-
S. Koshizuka, N. Takano, Y. Oka, “Numerical analysis of deterioration phenomena in heat transfer to supercritical water,” Int. J. Heat Mass Transfer, 38, 3077 (1995).
-
(1995)
Int. J. Heat Mass Transfer
, vol.38
, pp. 3077
-
-
Koshizuka, S.1
Takano, N.2
Oka, Y.3
-
11
-
-
0001904923
-
The 1995 look-up table for critical heat flux in tubes
-
D. C. Groeneveld, et al., “The 1995 look-up table for critical heat flux in tubes,” Nucl. Eng. Des., 163, 1 (1996).
-
(1996)
Nucl. Eng. Des.
, vol.163
, pp. 1
-
-
Groeneveld, D.C.1
-
14
-
-
0015482943
-
Forced convective heat transfer to supercritical water flowing in tubes
-
K. Yamagata, K. Nishikawa, S. Hasegawa, T. Fujii, S. Yoshida, “Forced convective heat transfer to supercritical water flowing in tubes,” Int. J. Heat Mass Transfer, 15, 2575 (1972).
-
(1972)
Int. J. Heat Mass Transfer
, vol.15
, pp. 2575
-
-
Yamagata, K.1
Nishikawa, K.2
Hasegawa, S.3
Fujii, T.4
Yoshida, S.5
-
15
-
-
85010485442
-
Thermal-hydraulic analysis of supercritical pressure light water reactors
-
Hollywood, Florida, June 9-13, 2002, Sec. 3.04
-
X. Cheng, T. Schulenberg, et al., “Thermal-hydraulic analysis of supercritical pressure light water reactors,” Proc. Int. Conf. on Advanced Nuclear Power Plants (ICAPP), Hollywood, Florida, June 9-13, 2002, Sec. 3.04 (2002).
-
(2002)
Proc. Int. Conf. On Advanced Nuclear Power Plants (ICAPP)
-
-
Cheng, X.1
Schulenberg, T.2
-
16
-
-
0038148446
-
‘Design analysis of core assemblies for supercritical pressure conditions
-
X. Cheng, T. Schulenberg, et al., “Design analysis of core assemblies for supercritical pressure conditions, '' Nucl. Eng. Des., 223[3], 279 (2003).
-
(2003)
Nucl. Eng. Des.
, vol.223
, Issue.3
, pp. 279
-
-
Cheng, X.1
Schulenberg, T.2
-
19
-
-
0001921715
-
Coupled thermohydraulic-neu-tronic instabilities in boiling water nuclear reactors: A review of the state of the art
-
J. March-Leuba, J. M. Rey, “Coupled thermohydraulic-neu-tronic instabilities in boiling water nuclear reactors: a review of the state of the art, ” Nucl. Eng. Des., 145, 97 (1993).
-
(1993)
Nucl. Eng. Des.
, vol.145
, pp. 97
-
-
March-Leuba, J.1
Rey, J.M.2
-
20
-
-
85010593011
-
-
Second ed., ANS, La Grange Park, Illinois
-
R. T. Lahey Jr., F. J. Moody, The Thermal-Hydraulics of a Boiling Water Nuclear Reactor, Second ed., ANS, La Grange Park, Illinois, (1993).
-
(1993)
The Thermal-Hydraulics of a Boiling Water Nuclear Reactor
-
-
Lahey, R.T.1
Moody, F.J.2
-
23
-
-
0033114908
-
A study on boiling water reactor stability behavior
-
D. Hennig, “A study on boiling water reactor stability behavior, ” Nucl. Technol., 126[4], 10 (1999).
-
(1999)
Nucl. Technol.
, vol.126
, Issue.4
, pp. 10
-
-
Hennig, D.1
-
24
-
-
0043260267
-
“On the analysis of various instabilities in two-phase flows
-
Hemisphere Press
-
R. T. Lahey Jr., M. Z. Podowski, “On the analysis of various instabilities in two-phase flows, Multiphase Science and Technology, Vol. 4, Hemisphere Press, p. 183-370 (1989).
-
(1989)
Multiphase Science and Technology
, vol.4
, pp. 183-370
-
-
Lahey, R.T.1
Podowski, M.Z.2
-
25
-
-
0022693463
-
“The development of a closed-form analytical model for the stability analysis of nuclear-coupled density wave oscillations in boiling water nuclear reactors
-
G. Park, et al., “The development of a closed-form analytical model for the stability analysis of nuclear-coupled density wave oscillations in boiling water nuclear reactors, Nucl. Eng. Des., 92, 253 (1986).
-
(1986)
Nucl. Eng. Des.
, vol.92
, pp. 253
-
-
Park, G.1
-
26
-
-
0003474751
-
-
Second ed., Cambridge University Press
-
W. H. Press, et al., Numerical Recipes in Fortran 77, Second ed., Cambridge University Press, (1992).
-
(1992)
Numerical Recipes in Fortran
, vol.77
-
-
Press, W.H.1
|