-
1
-
-
0037738847
-
Three-dimensional numerical simulation of flow and heat transport in high temperature nuclear reactors
-
Becker S., and Laurien E. Three-dimensional numerical simulation of flow and heat transport in high temperature nuclear reactors. Nuclear Engineering and Design 222 (2003) 189-201
-
(2003)
Nuclear Engineering and Design
, vol.222
, pp. 189-201
-
-
Becker, S.1
Laurien, E.2
-
2
-
-
47849086540
-
-
Bolnov, V.A., et al., 2004a. GT-MHR code description and potential. In: Proceedings of the 2nd International Topical Meeting on High Temperature Reactor Technology, Beijing, China, September 22-24, Paper C27.
-
Bolnov, V.A., et al., 2004a. GT-MHR code description and potential. In: Proceedings of the 2nd International Topical Meeting on High Temperature Reactor Technology, Beijing, China, September 22-24, Paper C27.
-
-
-
-
3
-
-
47849093771
-
-
Bolnov, V.A., et al., 2004b. Simulator development for GT-MHR reactor plant designing. In: Proceedings of the 2nd International Topical Meeting on High Temperature Reactor Technology, Beijing, China, September 22-24, Paper D28.
-
Bolnov, V.A., et al., 2004b. Simulator development for GT-MHR reactor plant designing. In: Proceedings of the 2nd International Topical Meeting on High Temperature Reactor Technology, Beijing, China, September 22-24, Paper D28.
-
-
-
-
4
-
-
34247143759
-
A simple dynamic model of the primary circuit in VVER plants for controller design purposes
-
Fazekas C., Szederkenyi G., and Hangos K.M. A simple dynamic model of the primary circuit in VVER plants for controller design purposes. Nuclear Engineering and Design 237 (2007) 1071-1087
-
(2007)
Nuclear Engineering and Design
, vol.237
, pp. 1071-1087
-
-
Fazekas, C.1
Szederkenyi, G.2
Hangos, K.M.3
-
5
-
-
0036783867
-
Thermal hydraulic calculation of the HTR-10 for the initial and equilibrium core
-
Gao Z., and Shi L. Thermal hydraulic calculation of the HTR-10 for the initial and equilibrium core. Nuclear Engineering and Design 218 (2002) 51-64
-
(2002)
Nuclear Engineering and Design
, vol.218
, pp. 51-64
-
-
Gao, Z.1
Shi, L.2
-
6
-
-
0036784252
-
Thermal hydraulic transient analysis of the HTR-10
-
Gao Z., and Shi L. Thermal hydraulic transient analysis of the HTR-10. Nuclear Engineering and Design 218 (2002) 65-80
-
(2002)
Nuclear Engineering and Design
, vol.218
, pp. 65-80
-
-
Gao, Z.1
Shi, L.2
-
7
-
-
0038414946
-
Design of a physical model of the PBMR with the aid of Flownet
-
Greyvenstein G.P., and Rousseau P.G. Design of a physical model of the PBMR with the aid of Flownet. Nuclear Engineering and Design 222 (2003) 203-213
-
(2003)
Nuclear Engineering and Design
, vol.222
, pp. 203-213
-
-
Greyvenstein, G.P.1
Rousseau, P.G.2
-
8
-
-
47849115312
-
-
Huang, X., 2000. Modeling and Simulation Research of the Modular High Temperature Gas-Cooled Reactor and the development of numerical real-time simulation system. Technical Report, Tsinghua University (in Chinese).
-
Huang, X., 2000. Modeling and Simulation Research of the Modular High Temperature Gas-Cooled Reactor and the development of numerical real-time simulation system. Technical Report, Tsinghua University (in Chinese).
-
-
-
-
10
-
-
47849125562
-
-
INET, 2001. Thermal Hydraulics Design Report of the 10 MW high temperature gas-cooled reactor. Technical Report, Institute of Nuclear Energy Technology, Tsinghua University (in Chinese).
-
INET, 2001. Thermal Hydraulics Design Report of the 10 MW high temperature gas-cooled reactor. Technical Report, Institute of Nuclear Energy Technology, Tsinghua University (in Chinese).
-
-
-
-
11
-
-
47849086537
-
-
Stempniewicz, M.M., 2002. Steady-state and accident analyses of PBMR with the computer code SPECTRA. In: Proceedings of the Conference on High Temperature Reactors, Petten, NL, April 22-24, 2002-404.
-
Stempniewicz, M.M., 2002. Steady-state and accident analyses of PBMR with the computer code SPECTRA. In: Proceedings of the Conference on High Temperature Reactors, Petten, NL, April 22-24, 2002-404.
-
-
-
-
12
-
-
47849099247
-
-
Rademer, T., Bernnat, W., Lohnert, G., 2004. Coupling of neutronics and thermal-hydraulics codes for the simulation of transients of pebble bed HTR reactors. In: Proceedings of the 2nd International Topical Meeting on High Temperature Reactor Technology, Beijing, China, September 22-24, Paper C22.
-
Rademer, T., Bernnat, W., Lohnert, G., 2004. Coupling of neutronics and thermal-hydraulics codes for the simulation of transients of pebble bed HTR reactors. In: Proceedings of the 2nd International Topical Meeting on High Temperature Reactor Technology, Beijing, China, September 22-24, Paper C22.
-
-
-
-
14
-
-
47849114507
-
-
Tauveron, N., et al., 2002. Thermal hydraulic simulations on high temperature reactors. In: Proceedings of the Conference on High Temperature Reactors, Petten, NL, April 22-24, 2002-403.
-
Tauveron, N., et al., 2002. Thermal hydraulic simulations on high temperature reactors. In: Proceedings of the Conference on High Temperature Reactors, Petten, NL, April 22-24, 2002-403.
-
-
-
-
15
-
-
47849132662
-
-
The Mathworks, Inc., 2007. .
-
The Mathworks, Inc., 2007. .
-
-
-
-
16
-
-
47849109214
-
-
Van Ravenswaay, J.P., et al., 2004. Verification and validation of the HTGR systems CFD code FLOWNEX. In: Proceedings of the 2nd International Topical Meeting on High Temperature Reactor Technology, Beijing, China, September 22-24, Paper C30.
-
Van Ravenswaay, J.P., et al., 2004. Verification and validation of the HTGR systems CFD code FLOWNEX. In: Proceedings of the 2nd International Topical Meeting on High Temperature Reactor Technology, Beijing, China, September 22-24, Paper C30.
-
-
-
-
17
-
-
38249018061
-
High temperature reactor core physics and reactor dynamics
-
Wolf L. High temperature reactor core physics and reactor dynamics. Nuclear Engineering and Design 121 (1990) 227-240
-
(1990)
Nuclear Engineering and Design
, vol.121
, pp. 227-240
-
-
Wolf, L.1
-
19
-
-
47849100636
-
-
Xu, Y., 2002a. The Chinese point and status. In: Proceedings of the Conference on High Temperature Reactors. Petten, NL, April 22-24.
-
Xu, Y., 2002a. The Chinese point and status. In: Proceedings of the Conference on High Temperature Reactors. Petten, NL, April 22-24.
-
-
-
-
20
-
-
0036783501
-
Overview of the 10 MW high temperature gas cooled reactor-test module project
-
Xu Y., and Zuo K. Overview of the 10 MW high temperature gas cooled reactor-test module project. Nuclear Engineering and Design 218 (2002) 13-23
-
(2002)
Nuclear Engineering and Design
, vol.218
, pp. 13-23
-
-
Xu, Y.1
Zuo, K.2
-
21
-
-
14944382802
-
HTGR advances in China
-
Xu Y. HTGR advances in China. Nuclear Engineering International 50 608 (2005) 22-25
-
(2005)
Nuclear Engineering International
, vol.50
, Issue.608
, pp. 22-25
-
-
Xu, Y.1
-
22
-
-
0036783506
-
Future HTGR developments in China after the criticality of the HTR-10
-
Zhang Z., and Yu S. Future HTGR developments in China after the criticality of the HTR-10. Nuclear Engineering and Design 218 (2002) 249-257
-
(2002)
Nuclear Engineering and Design
, vol.218
, pp. 249-257
-
-
Zhang, Z.1
Yu, S.2
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