Results 141 to 150 of about 695 (193)

Start-up characteristics for the test facility of a prototype sodium heated OTSG

Nuclear Engineering and Design, 2021
Abstract The test facility of the prototype sodium heated once-through steam generator (OTSG) is used to verify the accuracy and reliability of the design for the sodium heated OTSG. Besides, according to the test data, the structure and parameters of steam generator can be improved.
Wenxi Tian, Rongshuan Xu, Shibao Wang
exaly   +3 more sources

Effects of inclined condition on LOCA for a small offshore reactor with OTSG

Nuclear Engineering and Design, 2021
Abstract A small offshore reactor called SMR-50 is conceptually designed for power supply in the ocean. The SMR-50 is a compact pressurized water reactor with two symmetrically arranged once-through-steam-generators (OTSGs). In this paper, the effect of inclined condition on the thermal–hydraulic behavior of the reactor during a postulated loss-of ...
Wenxi Tian
exaly   +3 more sources

Power Rising and Descending Transient for the OTSG of a Small PWR

Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, 2020
Abstract As key heat transfer system in small and medium size pressurized water reactors, once-through steam generators are important parts of energy exchange between primary and secondary circuits, and are very important for the design and operation of reactors.
Baihui Jiang, Zhiwei Zhou, Zhaoyang Xia, Qian Sun   +3 more
exaly   +3 more sources

Evaluation of single heated channel and subchannel modeling of a nuclear once through steam generator (OTSG)

Kerntechnik, 2020
Abstract Steam generators are one of the most important components of pressurized-water reactors. This component plays the role of heat transfer and pressure boundary between primary and secondary side fluids. The Once Through Steam Generator (OTSG) is an essential component of the integrated nuclear power system.
A. Hamedani, O. Noori-Kalkhoran, R. Ahangari, M. Gei   +3 more
semanticscholar   +4 more sources

Research of flow instability in OTSG under low load conditions

Annals of Nuclear Energy, 2015
Abstract Integrated reactors generally use once-through steam generators (OTSGs). There are a lot of parallel channels in OTSG interior, and heat transfer tube secondary side sees severe boiling and phase transition phenomenon. At low load conditions, the feed water flow is small.
Minjun Peng, Xue Du, Genglei Xia
exaly   +3 more sources

Time-Domain Nonlinear Investigation of Two-Phase Flow Instability in HTGR OTSG Using SIMULINK

Volume 6: Thermal-Hydraulics and Safety Analysis
Abstract Two-phase flow instability may occur in the once-through steam generator (OTSG) of High-Temperature Gas-cooled Reactors (HTGR). A time-domain theoretical model of HTGR OTSG was established to investigate this phenomenon. The heat transfer tube of OTSG was divided into three regions, namely the subcooled water region, the ...
Yang Su, Xiaowei Li, Xinxin Wu
exaly   +3 more sources

Analysis of Flow Instability for OTSG in Movable Nuclear Power Devices

Advanced Materials Research, 2013
The instability occurring in OTSG (Once-Through Steam Generator) of movable nuclear power plants is presented by the multivariable frequency domain theory. As concerning coupling interactions of OTSG tubing, it is more efficient for analyzing the instability of OTSG compared the common single variable method.
Qing Hua Zhang
exaly   +3 more sources

Saturated Output Feedback Dissipation Steam Temperature Control for the OTSG of MHTGRs

IEEE Transactions on Nuclear Science, 2011
The modular high-temperature gas-cooled nuclear reactor (MHTGR) is seen as one of the best candidates for the next generation of nuclear power plants. The once through steam generator (OTSG) is a crucial element for any MHTGR power plants with steam cycle.
Xiaojin Huang, Zhe Dong
exaly   +3 more sources

Analysis of the flow instability among channels of the OTSG in the naval craft NPP

Kerntechnik, 2014
Abstract The instability occurring of the OTSG (Once-Through Steam Generator) in naval craft nuclear power plants is presented by the multivariable frequency domain theory. As concerning coupling interactions of the OTSG tubing, it is more accurate for analyzing the instability of OTSG compared to the common single variable method.
Hou Su-xia, Luo Ji-jun, Xu Jun, Liu Jie-yu   +3 more
exaly   +3 more sources

Characteristic Optimization of the Double-Tube OTSG

18th International Conference on Nuclear Engineering: Volume 4, Parts A and B, 2010
The OTSG (Once-Through Steam Generator) is usually used in the integral nuclear power equipment which requires smaller size and better effect of heat transfer. The OTSG with double-side heat transfer component is presented in this paper. The heat transfer component is composed of straight tube outside and helix tube inside.
Xinyu Wei, Fuyu Zhao, Yun Tai, Chunhui Dai   +3 more
openaire   +2 more sources