Results 1 to 10 of about 36,185 (292)

Thermal Hydraulic Modeling of Once-Through Steam Generator by Two-Fluid U-Tube Steam Generator Code [PDF]

open access: yesAtom 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   +5 more sources

Analysis on Non-Uniform Flow in Steam Generator During Steady State Natural Circulation Cooling [PDF]

open access: yesAtom Indonesia, 2007
Investigation on non uniform flow behavior among U-tube in steam generator during natural circulation cooling has been conducted using RELAP5. The investigation is performed by modeling the steam generator into multi channel models, i.e.
Susyadi, T. Yonomoto
doaj   +2 more sources

Separate and integral effect tests of aerosol retention in steam generator during tube rupture accident

open access: yesNuclear Engineering and Technology, 2022
A steam generator tube rupture accompanying a core damage may cause the fission product to be released to environment bypassing the containment. In such an accident, the steam generator is the major path of the radioactive aerosol release.AEOLUS facility,
Byeonghee Lee   +2 more
doaj   +1 more source

Estimation of the effective length of microcracks occurring in the water-steam pipeline at cyclic operation mode of NPP steam generator

open access: yesГлобальная ядерная безопасность, 2023
During operation of water-water reactors including KLT-40 type reactors widely used nowadays on icebreakers and floating power units (FPU), the issue of the duration of safe operation of steam generators is acute.
A. P. Elokhin
doaj   +1 more source

Steam generator secondary pH during a steam generator tube rupture [PDF]

open access: yesNuclear Technology, 1991
The Nuclear Regulatory Commission requires utilizes to determine the response of a pressurized water reactor to a steam generator tube rupture (SGTR) as part of the safety analysis for the plant. The SGTR analysis includes assumptions regarding the partitioning of iodine between liquid and vapor in steam generator secondary.
Adams, J. P., Peterson, E. S.
openaire   +5 more sources

Numerical simulation of steam bubble dynamics at microcrack in LBE descending flow field

open access: yesHe jishu, 2022
BackgroundWhen steam generator tube rupture (SGTR) occurs in the lead-bismuth cooled fast reactor, high pressure water/steam flows into the primary side filled with high temperature liquid metal.
DONG Weijian   +5 more
doaj   +1 more source

Cavity-shaped direct solar steam generator employing conical helical tube for high-temperature application: Model development, experimental testing and numerical analysis

open access: yesEnergy Conversion and Management: X, 2023
Concentrating solar thermal technologies are drawing more attention since it can substantially contribute to a carbon-neutral society. The solar receivers are essential in this technology to convert solar energy efficiently into thermal energy. Moreover,
Yasuki Kadohiro   +6 more
doaj   +1 more source

Analysis of steam generator tube rupture accidents for the development of mitigation strategies

open access: yesNuclear Engineering and Technology, 2022
We analyzed mitigation strategies for steam generator tube rupture (SGTR) accidents using MARS code under both full-power and low-power and shutdown (LPSD) conditions.
Jungjin Bang   +5 more
doaj   +1 more source

Steam generator tube failures [PDF]

open access: yes, 1996
A review and summary of the available information on steam generator tubing failures and the impact of these failures on plant safety is presented. The following topics are covered: pressurized water reactor (PWR), Canadian deuterium uranium (CANDU) reactor, and Russian water moderated, water cooled energy reactor (VVER) steam generator degradation ...
MacDonald, P. E.   +3 more
openaire   +2 more sources

Coupled modeling of neutronics and thermal-hydraulics processes in LFR under SG-leakage condition [PDF]

open access: yesNuclear Energy and Technology, 2023
The lead cooled reactor BREST-OD-300 is developing as a part of Russian federal project “PRORYV”. Two- circuit scheme is used in the reactor for heat removal.
Yurii S. Khomyakov   +2 more
doaj   +3 more sources

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