Results 201 to 210 of about 52,055 (257)

Leak-before-break in steam generator tubes

International Journal of Pressure Vessels and Piping, 1990
Abstract The steam generator tubing constitutes one of the main barriers against the release of activity to the environment. The capacity of the tubing to withstand safely the loads exerted on it during normal operation and faulted conditions is therefore the most important factor in steam generator safety evaluation.
B. Flesch, B. Cochet
openaire   +1 more source

Heat transfer performance of U-tube molten salt steam generator

, 2020
Heat transfer and thermal performance of U-tube molten salt steam generator was experimentally reported with inlet water flow rate of 22.4-89.6 L/h, water temperature of 20-100°C, salt flow rate of 1-2.2 m3/h and salt temperature of 306.5-395.3°C.
Yukun Zou, Jing Ding, Weilong Wang, Duu-Jong Lee, Jianfeng Lu   +4 more
semanticscholar   +1 more source

Development of a model for thermal-hydraulic analysis of helically coiled tube once-through steam generator based on Modelica

, 2020
The Helically coiled tube Once-Through Steam Generator (H-OTSG) is a critical component for compact small reactors. The present study developed and verified a model in Modelica language and simulated steady-state and transient situations of the model ...
H. Ding, Yaoli Zhang, Kai Ye, Gang Hong
semanticscholar   +1 more source

Vibration Damping of Stabilized Steam-Generator Tubes

Volume 4: Fluid Structure Interaction, 2005
The integrity of steam-generator tubes is an important aspect of the long-term reliable operation of nuclear power plants. In situations where a tube is judged to be at risk, it must be either plugged, or removed, or reliably stabilized in some manner to avoid excessive motion of the tube due to flow-induced vibration.
V. P. Janzen, Y. Han, B. A. W. Smith, S. M. Fluit   +3 more
openaire   +1 more source

An experimental review of steam generator tube rupture accident in lead-cooled fast reactors: Thermal-hydraulic experiments classification and methods introduction

Progress in nuclear energy (New series), 2023
Qifan Yu, S. Qiu, Chenglong Wang, Dalin Zhang, W. Tian, G. Su   +5 more
semanticscholar   +1 more source

Ginna Steam Generator Tube Rupture

1984
At 9:25 a. m. on January 25, 1982, a single steam generator tube ruptured in the “B” steam generator at the R. E. Ginna Nuclear Power Plant. Prior to the incident, the plant, a two-loop Westinghouse design, had been operating at full power with no indications of primary to secondary leakage.
openaire   +1 more source

Experimental and theoretical investigations on reverse flow characteristics in vertically inverted U-tube steam generator under transient condition

, 2020
Under natural circulation conditions, the primary circuit of a steam generator (SG) has a tendency to occur flow instabilities. These instabilities due to reverse flow in some vertically inverted U-tubes will increase the flow resistance coefficient and ...
Mingrui Li, J. Hao, Wenzhen Chen, Li Weitong   +3 more
semanticscholar   +1 more source

Inner tube optimization of double-tube once-through steam generator

International Journal of Heat and Mass Transfer, 2013
Abstract We present a double-tube once-through steam generator (DOTSG) with an outer straight tube and an inner helical tube in this paper. For the purpose of the compact structure and lower pressure drop, the inner helical tube is optimized. The tube length and the combined pressure drop are considered as the two objective functions, and the pitch ...
Xinyu Wei, Chunhui Dai, Li Wang, Fuyu Zhao   +3 more
openaire   +1 more source

CFD Simulation of Steam Generator Tube Rupture Thermal-Hydraulics

12th International Conference on Nuclear Engineering, Volume 1, 2004
The tube rupture accident is one among the most risk-dominant events at the nuclear power plants. Several steam generator tube rupture accidents have occurred at the plants in the past. In this paper the Computational Multi-Fluid Dynamics (CMFD) investigation of the horizontal steam generator thermal-hydraulics during the tube rupture accident is ...
Maslovarić, Blaženka, Prica, Sanja, Stevanović, Vladimir, Stošić, Zoran V.   +3 more
openaire   +2 more sources

Three-dimensional study on the hydraulic characteristics under the steam generator (SG) tube plugging operations for AP1000

Progress in nuclear energy (New series), 2019
Pressurized water reactors (PWRs) use Steam Generators (SG) to transfer the reactor core heat to the secondary loop. The SG contains thousands of heat transfer tubes and tubes plugging operation is always adopted to solve the heat transfer tubes rupture ...
Xiaohan Zhao, Mingjun Wang, Chong Chen, Xi Wang, Haoran Ju, W. Tian, S. Qiu, G. Su   +7 more
semanticscholar   +1 more source