Results 51 to 60 of about 2,093 (208)

Investigation of the Impact of Changing the Heat Exchange Area on PHV-1000 Steam Generator Productivity

Energy Engineering and Control Systems
The PHV-1000 steam generator is one of the main heat exchangers in the primary circuit of the power unit of nuclear power plants with a WWER-1000 reactor.
Marta Kuznetsova, Halyna Matiko, Oleksandr Liashyk   +2 more
doaj   +1 more source

Subcooled choked flow through steam generator tube cracks [PDF]

, 2012
The work presented here describes an experimental investigation into the choked flow of initially subcooled water through simulated steam generator tube cracks at pressures up to 6.9 MPa.
Wolf, Brian J
core  

Thermal-hydraulic response and iodine transport during a steam generator tube rupture [PDF]

, 1988
Recent reanalyses of the offsite dose consequences following a steam generator tube rupture have identified a possible non-conservatism in original FSAR analyses.
R.A. Callow, Callow, R.A.
core   +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

Assessment of Subcooled Choking Flow Models in RELAP5 with Experimental Data in Simulated Steam Generator Tube Cracks [PDF]

, 2019
Choking flow plays an integral part not only in the engineered safeguards of a nuclear power plant (NPP), but also to everyday operation. Current pressurized water reactor steam generators operate on the leak-before-break approach. The ability to predict
Mark A. Brown (5930558)
core   +1 more source

Numerical Investigation of Fluid–Structure Interaction of Foreign Objects in Steam Generator Tube Bundles

Journal of Nuclear Engineering
As a critical component of nuclear and thermal energy conversion systems, the long-term safe operation of a steam generator depends on the structural integrity of its tube bundles.
Yuhua Hang, Heng Wang, Yuanqing Liu, Zhen Cai, Bin Zhu, Jinna Mei, Guorui Zhu   +6 more
doaj   +1 more source

PWR steamline break analysis assuming concurrent steam generator tube rupture [PDF]

, 1980
Results are presented for a steamline break analysis for a typical, two-loop, 2560 MW(t) pressurized water reactor. The calculations were performed using the IRT reactor system transient analysis code.
Shier, W. G., Levine, M. M.
core  

Analysis and Evaluation on the Foreign Objects on the Steam Generator Tube Sheet of a Nuclear Power Plant [PDF]

, 2022
The residual foreign objects on the steam generator tube sheet of a nuclear power plant were analyzed and evaluated by ARCHARD wear physical model and impact energy calculation method for collision analysis.Results showed that if the conservative ...
WANG Hao, WANG Chen, GAO Jun, WEI Shenghui, ZHU Zhibin
core   +1 more source