Shape Estimation of Defects on Steam Generator Tubes
, 1998 Most of the nuclear power plants(NPPs) now in service in Japan are based on either of two reactor technologies — PWR and BWR. While the PWR plant requires steam generators(SG), the BWR plant needs no separate SG because of its capability to produce steam directly.
Shiraishi, Kozo +2 more
openaire +3 more sources
Nuclear Engineering and TechnologyThis 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
Steam generator tube rupture effects on a LOCA [PDF]
, 1979 A problem currently experienced in commercial operating pressurized water reactors (PWR) in the United States is the degradation of steam generator tubes.
LaChance, J. L.
core
Dynamic simulation of a Westinghouse PWR four-loop plant during steam generator tube rupture event [PDF]
This study addresses the application of a full reactor system computer code to simulate the reactor primary and secondary loop thermal hydraulics, plant control and protection systems during the steam generator tube rupture (SGTR) events.
Sui, Yueh Chun
core
Yuanzineng kexue jishuThe 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
A condition-based probabilistic safety assessment framework for the estimation of the frequency of core damage due to an induced steam generator tube rupture [PDF]
, 2019 Condition-Based Probabilistic Safety Assessment (CB-PSA) makes use of information on the components health conditions during operation to dynamically update the risk estimators (e.g., Core Damage Frequency (CDF)).
Antonello F. +5 more
core
The Effect of the Number of Condensed Phases Modeled on Aerosol Behavior During an Induced Steam Generator Tube Rupture Sequence [PDF]
, 1998 VICTORIA is a mechanistic computer code designed to analyze fission product behavior within a nuclear reactor coolant system (RCS) during a severe accident.
Bixler, N. E., Schaperow, J. H.
core
Multiphase flow phenomena of steam generator tube rupture in a lead-cooled reactor system : A scoping analysis [PDF]
, 2008 The paper is concerned with understanding and quantification of intense multiphase interactions in a Steam Generator Tube Rupture (SGTR) scenario in advanced lead-cooled reactor systems.
Dinh, Truc-Nam,
core
CRACKING IN EGCR STEAM GENERATOR TUBE SHEET
, 1961 During fabrication of the EGCR steam generator cracking occurred in tube sheet of 1 1/4 Cr-1/2 Mo steel. Cracks were found at the torch-cut surface of the tube sheet following oxyacetylene torch cutting and a subsequent 1300 deg F stress relief. Metallographic examination of specimens containing the cracks showed that the tube sheet had fractured ...
openaire +2 more sources
Discussion of Phenomena and Computational Modeling for Flow Through Steam Generator Tube Leaks [PDF]
, 2022 Fabian Silber (MPA University of Stuttgart, Stuttgart) +3 more
core