Results 91 to 100 of about 2,093 (208)

Evaluation of target-wastage in consideration of sodium-water reaction environment formed on the periphery of an adjacent tube in steam generator of sodium-cooled fast reactor

Nihon Kikai Gakkai ronbunshu, 2018
Wastage on adjacent tubes (target-wastage) arise from water/steam leak in steam generators of sodium-cooled fast reactors (sodium-water reaction). Target-wastage is likely to be caused by liquid droplet impingement erosion (LDI) and Na-Fe composite ...
Akikazu KURIHARA, Ryota UMEDA, Kazuhito SHIMOYAMA, Shin KIKUCHI   +3 more
doaj   +1 more source

Fretting wear damage mechanism of Inconel 690 alloy tube in nuclear power plant

Cailiao gongcheng
The steam generator is subjected to the action of high temperature and high-pressure steam， and the flow induced vibration phenomenon of its heat transfer tube is caused by the secondary lateral flow.
CHEN Runluo, YE Jinmiao, ZHENG Lei, XU Yangfeng, LIN Hanbo, XIE Linjun   +5 more
doaj   +1 more source

Reactor Loose Part Damage Assessments on Steam Generator Tube Sheets [PDF]

, 2010
PROCTOR, WILLIAM CYRUS. Reactor Loose Part Damage Assessments on Steam Generator Tube Sheets. (Under the direction of Joseph Michael Doster). Damage from loose parts inside reactor systems can potentially cause integrity issues that jeopardize the ...
Proctor, William Cyrus
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Status and Proposal Studies on Thermal-Hydraulic Phenomena to Steam Generator Tube Rupture Accident in LFR and ADS [PDF]

, 2010
This article reviews the studies on steam generator tube rupture (SGTR) accident in lead alloy-cooled fast reactors (LFR) and the accelerator-driven transmutation system (ADS) including proposal for visualization test in injection of water into molten ...
Minoru Takahashi, Rongyuan Sa
core   +1 more source

Application of a dynamic event tree methodolgy to steam generator tube rupture sequences [PDF]

, 2012
The Integrated Safety Assessment (ISA) methodology, developed by the Spanish Nuclear Safety Council (CSN), has been applied to a thermo-hydraulical analysis of a Westinghouse 3-loop PWR plant by means of the dynamic event trees (DET) for Steam Generator ...
Hortal Reymundo, Javier, Queral Salazar, José Cesar, Sánchez Perea, Miguel, Rebollo, M.J., Izquierdo Rocha, José María, Gómez Magán, J.J., Jiménez Varas, Gonzalo, Ibañez, L., Gil, Jesús, Fernández, Iván, Meléndez Asensio, Enrique, Marrao, Hugo   +11 more
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Experiment data report for Semiscale Mod-1 Test S-28-5 (steam generator tube rupture test). [PWR] [PDF]

, 1977
Recorded test data are presented for Test S-28-5 of the Semiscale Mod-1 steam generator tube rupture test series. These tests are among several Semiscale Mod-1 experiments conducted to investigate the thermal and hydraulic phenomena accompanying a ...

core   +1 more source

Experimental models of medium break loss of coolant accidents with and without steam generator tube rupture [PDF]

, 2012
This paper reports model experiments simulating medium break loss of coolant accidents, with and without steam generator tube rupture (SGTR), in pressurized water reactors.
Marn, Jure, Škerget, Leopold, Delić, Marjan   +2 more
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System and method for mitigating dispersion of radioactive substance in steam generator tube rupture accidents [PDF]

, 2020
본 발명은 증기발생기 전열관 파단 중대사고 대응을 위한 방사성물질 확산방지 시스템 및 방법에 관한 것으로서, 더욱 상세하게는 증기발생기 전열관 파단(steam generator tube rupture, SGTR) 중대사고 발생시에 강력하게 방출되는 증기와 이에 따른 방사성물질의 누출에 효과적으로 대응하기 위해 오픈형 포집장치를 이용하고, 또한 이러한 오픈형 포집장치를 이용하여 방출되는 방사성물질을 효과적으로 포집하여 확산을 방지하는 방법에 관한 것이다.
강성우, Sana Ullah, 변현호, 임만성, 왕웅재   +4 more
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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