Results 71 to 80 of about 52,055 (257)

Steam generator tube rupture scenarios (SGTR)

, 2003
The Steam Generator Tube Rupture (SGTR) scenarios project was carried out in the framework of the research and training programme, EURATOM, in the field of nuclear energy during years 2000-2002. The first objective of the project was to generate a comprehensive database on fission product retention in a steam generator.
Jokiniemi, Jorma, Lähde, Anna, Auvinen, Ari, Tuomisto, H., Routamo, T., Lundström, P., Dienstbier, J., Güntay, S, Suckow, Detlef, Dehbi, A., Slootman, M., Herranz, L., Peyres, V., Polo, J.   +13 more
  +5 more sources

Analysis of Thermal-Hydraulics Parameters During Steam Generator Tube Rupture Event of VVER-1200 NPP Using PCTRAN Simulator

Applications of Modelling and Simulation, 2022
The overall performance of steam generators plays a significant role in ensuring the safety of a nuclear power plant (NPP) operation. The analysis of thermal-hydraulic parameters during a steam generator tube rupture (SGTR) event of VVER-1200 NPP is ...
Muhammed Mufazzal Hossen
doaj  

Study on the effect of geometry and material property on collapse pressure of a helical steam generator tube under external pressure

Nuclear Engineering and Technology
In this paper, a numerical study was conducted to analyze the effect of the geometry (tube thickness, ovality, and helical diameter) and material properties of once through steam generator tubes subjected to external pressure on collapse pressure.
Gyo-Geun Youn, Kwanghyun Ahn, Myeong-Woo Lee   +2 more
doaj   +1 more source

Dryout occurrence in a helically coiled steam generator for nuclear power application

EPJ Web of Conferences, 2014
Dryout phenomena have been experimentally investigated in a helically coiled steam generator tube. The experiences carried out in the present work are part of a wide experimental program devoted to the study of a GEN III+ innovative nuclear power plant ...
Santini L., Cioncolini A., Lombardi C., Ricotti M.   +3 more
doaj   +1 more source

Development of a computer code for thermal–hydraulic design and analysis of helically coiled tube once-through steam generator

, 2017
The Helically coiled tube Once-Through Steam Generator (H-OTSG) is a key piece of equipment for compact small reactors. The present study developed and verified a thermal–hydraulic design and performance analysis computer code for a countercurrent H-OTSG
Yaoli Zhang, Duo Wang, Jian-Yuan Lin, Junwei Hao   +3 more
semanticscholar   +1 more source

Effect of bending on the geometry and collapse pressure of helical steam generator tubes: Numerical study

Nuclear Engineering and Technology
This study investigates the effects of bending processes on the geometry and collapse pressure of helical steam generator tubes used in Small Modular Reactors (SMRs).
M. Park, M.W. Lee, K. Ahn, G.G. Youn
doaj   +1 more source

Degradations of Incoloy 800 Steam Generator Tubing

, 2011
In our days, the nuclear energy becomes more and more important. The efficient operation of a Nuclear Power Plant (NPP) supposes the assurance of the performances established by design for all entire life of the NPP key components. Steam Generator (SG) is one of the key components for a NPP because this equipment assures the separation boundary between
openaire   +3 more sources

Study on Thermal-hydraulic Steady-state Comprehensive Performance of Fast Reactor Sodium-water Steam Generator

Yuanzineng kexue jishu
The sodium-heated once-through steam generator (OTSG) plays an important role in separating the second and third circuits of sodium cooled fast reactor (SFR).
XIAO Changzhi1, YANG Hongyi1, ZHANG Dalin2, SHEN Geyu1, QIU Suizheng2, LU Yuan1, ZHANG Kui2, HUANG Yuanbin1
doaj   +1 more source

Development of Differential Type Eddy Current Probe for NDT Evaluation of the Steam Generator Tube [PDF]

, 2005
Sung Yoon Jung
openalex   +1 more source

Precision Measuring System for Tube Support Plate of Steam Generator

, 2016
蒋鑫 JIANG Xin, 李华 LI Hua, 朱辉 ZHU Hui, 刘杰 LIU Jie   +3 more
openalex   +2 more sources