Results 31 to 40 of about 52,055 (257)

Small modular reactors (SMRs): Comparison of saturated versus superheated steam Rankine cycle under equal thermodynamic constraints

Nuclear Engineering and Technology
With part-load operation is increasingly becoming important issue for small modular reactors (SMRs), two secondary Rankine cycles for a 500 MWth pressurized-water-reactor small modular reactor were compared under identical thermodynamic constraints: a ...
Gyudong Kim, Yong Jae Chae, Takhyun Chun, Jeong Ik Lee   +3 more
doaj   +1 more source

Parameter Analysis of Two-phase Flow Stability in HTGR Helical Tube Once Through Steam Generator Based on Variable Tube Diameter Model

Yuanzineng kexue jishu, 2022
As the fourth generation nuclear power technology, high temperature gas-cooled reactor (HTGR) has good prospects due to its inherent safety and high temperature.
SU Yang;LI Xiaowei;WU Xinxin
doaj  

Design of Coil-Wound Once-Through Steam Generator System for Concentrating Solar Power Plants

SolarPACES Conference Proceedings
The viability of solar tower plants is endangered owing to multiple failures, mainly in their steam generators. These failures produce unscheduled shutdowns with significant economic losses that increase the financing costs of this technology due to its
Dario Pardillos-Pobo, Pedro-Ángel González-Gómez, María Berbey-Burgos, Domingo Santana   +3 more
doaj   +1 more source

Markov stochastic process modeling for evolution of wear depth in steam generator tubes

Advances in Mechanical Engineering, 2019
Reliability of steam generator is a serious concern in the operation of nuclear power plants, especially for steam generator tubes that experience a variety of degradation mechanisms including wear damage. It is necessary to develop a model to accurately
Xing He, Xiaojiao Xu, Wei Tian, Yuebing Li, Weiya Jin, Mingjue Zhou   +5 more
doaj   +1 more source

Fiber Fabry-Perot Force Sensor with Small Volume and High Performance for Assessing Fretting Damage of Steam Generator Tubes

Sensors, 2017
Measuring the radial collision force between the steam generator tube (SGT) and the tube support plate (TSP) is essential to assess the fretting damage of the SGT. In order to measure the radial collision force, a novel miniaturized force sensor based on
Peijian Huang, Ning Wang, Junying Li, Yong Zhu, Jie Zhang   +4 more
doaj   +1 more source

LMFBR steam generator development: duplex bayonet tube steam generator. Volume II [PDF]

, 1975
This report represents the culmination of work performed in fulfillment of ERDA Contract AT(11-1)-2426, Task Agreement 2, in which alternate steam generator designs were developed and studied. The basic bayonet tube generator design previously developed by C-E under AEC Contract AT(11-1)-3031 was expanded by incorporating duplex heat transfer tubes to ...
openaire   +2 more sources

Investigation of heat transfer in a steam generator bayonet tube for the development of PbLi technology for EU DEMO fusion reactor

Fusion engineering and design, 2020
In the frame of the EUROfusion roadmap for the development of the DEMO power plant, a research activity was carried out to develop a Lithium–Lead/water heat exchanger.
E. Martelli, A. D. Nevo, P. Lorusso, F. Giannetti, V. Narcisi, M. Tarantino   +5 more
semanticscholar   +1 more source

Thermal-hydraulic Code Development and Analysis of HTGR Helical Tube Supercritical Steam Generator

Yuanzineng kexue jishu, 2022
Supercritical steam generator can further improve the power generation efficiency of high temperature gas-cooled reactor (HTGR). A supercritical steam generator design is proposed based on the experience of the subcritical once through steam generator ...
FAN Hongyi;LI Xiaowei;WU Xinxin;SUN Libin
doaj  

Impingement wastage experiment with SUS 316 in a printed circuit steam generator

Nuclear Engineering and Technology
The sodium cooled fast reactor (SFR) is one of the Gen-IV reactors with the most operating experience accumulated. Although the technology level is the most mature among the Gen-IV reactors, there is still a safety problem that has not been solved, which
Siwon Seo, Bowon Hwang, Sangji Kim, Jaeyoung Lee   +3 more
doaj   +1 more source

A study on increase of vapor in PWR steam generator (Improvement of heat transfer coefficient by fin and twisted tape introduction)

Nihon Kikai Gakkai ronbunshu, 2016
Increasing the electric power of nuclear power plant is important for the economy and the environment. Pressurized water reactor (PWR) exchanges the heat of primary system with secondary system in the steam generator (SG) to generate vapor. In this study,
Kenta FUJI, Shinichi MOROOKA
doaj   +1 more source