Steam generator tube integrity program. Phase I report. [PWR] [PDF]
, 1979 The results are presented of the pressure tests performed as part of Phase I of the Steam Generator Tube Integrity (SGTI) program at Battelle Pacific Northwest Laboratory.
Alzheimer, J. M. +3 more
core +1 more source
Design of steam generator tube bundle [PDF]
, 2012 Diploma thesis is focused on analisis of the steam generator tube bundle on the basis calculation by the finite elements method and softwaru ANSYS. Next it will also také account of job descriptions and methods of operation of the equipment propřed plan ...
Klíma, Martin
core +2 more sources
Numerical Simulation of Impurity Deposition and Blockage in Tube Support Plate of Steam Generator
Yuanzineng kexue jishu, 2022 In the process of long-term operation of steam generators, although the secondary side of the water quality is strictly controlled, in the complex thermal hydraulic conditions, impurities will also accumulate in the steam generator.
MU Defang;WANG Mingjun;TIAN Wenxi;QIU Suizheng;SU Guanghui
doaj
Experiment data report for semiscale Mod-1 test S-28-4 (steam generator tube rupture test) [PDF]
, 1977 Recorded test data are presented for Test S-28-4 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 ...
Esparza, V., Sackett, K.E.
core +1 more source
Yuanzineng kexue jishu, 2022 Helical coil steam generator has the advantages of compact structure, high heat transfer efficiency, strong resistance to thermal expansion stress, and has been widely applied in energy and power engineering, chemical industry and other fields.
LIU Kai;WANG Mingjun;ZHANG Jing;TIAN Wenxi;QIU Suizheng;SU Guanghui
doaj
Free vibration analysis of a steam generator tube bundle with and without lateral support. [PWR] [PDF]
, 1979 The vibrational modes and frequency characteristics of a pressurized water reactor (PWR) steam generator tube bundle assembly with and without lateral support in a fluid environment are analyzed.
D.M. King, King, Dennis M.
core +1 more source
Experiment data report for Semiscale Mod-1 test S-28-6 (steam generator tube rupture test) [PDF]
, 1977 Recorded test data are presented for Test S-28-6 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 ...
Patton, M. L. +2 more
core +1 more source
Numerical Study of Natural Circulation Flow in Reactor Coolant System during a Severe Accident
Science and Technology of Nuclear Installations, 2022 The rupturing of steam generator tubes leads to serious accidents in nuclear power plants. It causes radioactive materials to leak into the secondary system and release outside the reactor containment region.
Dae Kyung Choi +5 more
doaj +1 more source
Thermal Hydraulic Modeling of Once-Through Steam Generator by Two-Fluid U-Tube Steam Generator Code
Atom Indonesia, 2017 The THERMIT U-tube steam generator (THERMIT-UTSG) code was used for evaluation for the parametric study of a scaled once-through pressurized water reactor steam generator (OTSG) made by Babcock & Wilcox.
A. Zeighami +3 more
doaj +1 more source
The Effect of Clamping Force on the Wear Behavior of a Steam Generator Tube
Applied Sciences, 2022 Anti-vibration bars (AVBs) are essential components of a steam generator (SG) and are used to prevent steam generator tubes (SGTs) from vibrating intensely because of flow-induced vibration.
Xuxin Dong +6 more
doaj +1 more source