Robust observer based control for axial offset in pressurized-water nuclear reactors based on the multipoint reactor model using Lyapunov approach

Kerntechnik ◽  
2017 ◽  
Vol 82 (5) ◽  
pp. 586-597
Author(s):  
M. Zaidabadinejad ◽  
G. R. Ansarifar
Keyword(s):  
Nuclear Reactors ◽  
Reactor Model ◽  
Pressurized Water ◽  
Lyapunov Approach ◽  
Robust Observer

Atom-probe tomography of surface oxides and oxidized grain boundaries in alloys from nuclear reactors

2013 ◽  
Vol 1514 ◽  
pp. 107-118 ◽  
Author(s):  
Karen Kruska ◽  
David W Saxey ◽  
Takumi Terachi ◽  
Takuyo Yamada ◽  
Peter Chou ◽  
...  
Keyword(s):  
Grain Boundary ◽  
Grain Boundaries ◽  
Atom Probe Tomography ◽  
Nuclear Reactors ◽  
Bulk Material ◽  
Chemical Characterization ◽  
Atom Probe ◽  
Aqueous Environment ◽  
Pressurized Water ◽  
Surface Oxides

ABSTRACTThe preparation of site-specific atom-probe tomography (APT) samples containing localized features has become possible with the use of focused ion beams (FIBs). This technique was used to achieve the analysis of surface oxides and oxidized grain boundaries in this paper. Transmission electron microscopy (TEM), providing microstructural and chemical characterization of the same features, has also been used, revealing crucial additional information.The study of grain boundary oxidation in stainless steels and nickel-based alloys is required in order to understand the mechanisms controlling stress corrosion cracking in nuclear reactors. Samples oxidized under simulated pressurized water reactor primary water conditions were used, and FIB lift-out TEM and APT specimens containing the same oxidized grain boundary were prepared and fully characterized. The results from both techniques were found fully consistent and complementary.Chromium-rich spinel oxides grew at the surface and into the bulk material, along grain boundaries. Nickel was rejected from the oxides and accumulated ahead of the oxidation front. Lithium, which was present in small quantities in the aqueous environment during oxidation, was incorporated in the oxide. All phases were accurately quantified and the effect of different experimental parameters were analysed.

Pressurized Water Reactor Control Rods Worth Calibration Calculation by MCNP

2014 ◽  
Vol 539 ◽  
pp. 684-687
Author(s):  
Bo Yang ◽  
He Xi Wu ◽  
Qiang Lin Wei ◽  
Yi Bao Liu
Keyword(s):  
Neutron Flux ◽  
Flux Density ◽  
Operating Time ◽  
Pressurized Water Reactor ◽  
Reactor Model ◽  
Density Peak ◽  
Pressurized Water ◽  
Water Reactor ◽  
Neutron Flux Density ◽  
Control Rods

Control rods play an important role in nuclear power plant's reactivity control. In this paper, the study first establishes the pressurized water reactor model with Control rods by MCNP program, calculates the reactor keff by KCODE card and neutron flux density by F5:N card. The result shows that when control rods are not inserted, the neutron flux density distribution is similar to the cosine function. The control rods slowly but continuously move up with the reactor's increasing operating time, the neutron flux density peak gradually shifted to the top of reactor core. The simulation results agree with the nuclear fuel management program.

scholarly journals Anthropogenic Radiocarbon: Past, Present, and Future

Radiocarbon ◽  
1986 ◽  
Vol 28 (2A) ◽  
pp. 668-672 ◽  
Author(s):  
Pavel Povinec ◽  
Martin Chudý ◽  
Alexander Šivo
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Reactor ◽  
Nuclear Reactors ◽  
Pressurized Water Reactors ◽  
Anthropogenic Radionuclides ◽  
Pressurized Water ◽  
Heavy Water Reactor ◽  
Weapon Testing ◽  
Water Reactors

14C is one of the most important anthropogenic radionuclides released to the environment by human activities. Weapon testing raised the 14C concentration in the atmosphere and biosphere to +100% above the natural level. This excess of atmospheric C at present decreases with a half-life of ca 7 years. Recently, a new source of artificially produced 14C in nuclear reactors has become important. Since 1967, the Bratislava 14C laboratory has been measuring 14C in atmospheric 14CO2 and in a variety of biospheric samples in densely populated areas and in areas close to nuclear power plants. We have been able to identify a heavy-water reactor and the pressurized water reactors as sources of anthropogenic 14C. 14C concentrations show typical seasonal variations. These data are supported by measurements of 3H and 85Kr in the same locations. Results of calculations of future levels of anthropogenic 14C in the environment due to increasing nuclear reactor installations are presented.

A Review on Specific Features of Small and Medium Sized Nuclear Power Plants

2010 ◽  
Author(s):  
Salah Ud-din Khan ◽  
Minjun Peng ◽  
Muhammad Zubair ◽  
Shaowu Wang
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Reactor ◽  
Nuclear Reactors ◽  
Fixed Bed ◽  
Nuclear Industry ◽  
Energy Agency ◽  
Pressurized Water ◽  
Water Reactor ◽  
Energy Supply System

Due to global warming and high oil prices nuclear power is the most feasible solution for generating electricity. For the fledging nuclear power industry small and medium sized nuclear reactors (SMR’s) are instrumental for the development and demonstration of nuclear reactor technology. Due to the enhanced and outstanding safety features, these reactors have been considered globally. In this paper, first we have summarized the reactor design by considering some of the large nuclear reactor including advanced and theoretical nuclear reactor. Secondly, comparison between large nuclear reactors and SMR’s have been discussed under the criteria led by International Atomic Energy Agency (IAEA). Thirdly, a brief review about the design and safety aspects of some of SMR’s have been carried out. We have considered the specifications and parametric analysis of the reactors like: ABV which is the floating type integral Pressurized water reactor; Long life, Safe, Simple Small Portable Proliferation Resistance Reactor (LSPR) concept; Multi-Application Small Light Water Reactor (MASLWR) concept; Fixed Bed Nuclear Reactor (FBNR); Marine Reactor (MR-X) & Deep Sea Reactor (DR-X); Space Reactor (SP-100); Passive Safe Small Reactor for Distributed energy supply system (PSRD); System integrated Modular Advanced Reactor (SMART); Super, Safe, Small and Simple Reactor (4S); International Reactor Innovative and Secure (IRIS); Nu-Scale Reactor; Next generation nuclear power plant (NGNP); Small, Secure Transportable Autonomous Reactor (SSTAR); Power Reactor Inherently Safe Module (PRISM) and Hyperion Reactor concept. Finally we have point out some challenges that must be resolved in order to play an effective role in Nuclear industry.

Research on Algorithm of Sump Level Operator Assisted Support Program for PWR Nuclear Power Plant

2018 ◽  
Author(s):  
Liu Qiaofen ◽  
Xiao Sanping ◽  
Liu Yu ◽  
Liu Xichao ◽  
Jiang Xulun
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Nuclear Reactors ◽  
Support Program ◽  
Leakage Flow ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Calculation Results ◽  
Leak Before Break

Pressurized Water Reactor (PWR) nuclear power plant sump operator assisted program is applied to monitor unrecognized leaks of reactor coolant. It is very crucial to leak before break (LBB) protection and greatly affects the operational safety of nuclear reactors. In this paper, an algorithm of sump level operator assisted support program is proposed. Compared with the algorithm of traditional PWR, this algorithm adds the identification of working conditions and re-builds the leakage flow calculation method, which eliminates interference factors to the extent practical and improves the accuracy of the calculation results of unrecognized leakage flow.

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