Effect of de-regulation on operation of electrical grid and nuclear power generating stations

2001 ◽  
Author(s):  
N.K. Trehan
Keyword(s):  
Nuclear Power ◽  
Electrical Grid

Interaction of a Nuclear Power Plant With the Egyptian Electrical Grid Based on PSS/E

2010 ◽  
Author(s):  
S. Othman ◽  
H. M. Mahmoud ◽  
S. A. Kotb
Keyword(s):  
Power System ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Simulation Software ◽  
System Stability ◽  
Medium Term ◽  
Electrical Grid ◽  
Unit Model

The capacity of the electrical power system in Egypt will increase rapidly in the coming twenty years. In year 2018, nuclear power generation will be connecting to the Egyptian electrical grid. Consequently, the interaction of nuclear power plants and other systems becomes a very important issue, and a detailed nuclear power model for the medium-term and long-term power system stability should be developed. However, there is no nuclear unit model that can describe the detailed characteristics of the nuclear unit in the available commercial power system simulation software. In this paper, a detailed pressurized water reactor (PWR) nuclear unit model for medium-term and long-term power system transient stability is proposed. The model is implemented by a user defined program in PSS/E through PSS/E Matlab Simulink Interface. This model can be used to analyze the interaction of nuclear power plants and other power systems. The simulation results show that the proposed model is valid.

scholarly journals DYNAMIC STABILITY ANALYSIS FOR EGYPTIAN ELECTRICAL GRID WITH THE FIRST NUCLEAR POWER PLANT

2016 ◽  
Vol 11 (41) ◽  
pp. 1391-1400
Author(s):  
Mohamed Metwally ◽  
Mohamed Ali ◽  
Fahmy Bendary ◽  
Said Kutb ◽  
Yassin Ibrahem
Keyword(s):  
Stability Analysis ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Dynamic Stability ◽  
Nuclear Power ◽  
Electrical Grid

scholarly journals Electrical and Thermomechanical Co-Simulation Platform for NPP

Energies ◽  
2021 ◽  
Vol 14 (4) ◽  
pp. 939
Author(s):  
Poria Hasanpor Divshali ◽  
Pasi Laakso ◽  
Seppo Hänninen ◽  
Robert John Millar ◽  
Matti Lehtonen
Keyword(s):  
Power Systems ◽  
Nuclear Power ◽  
Power Plants ◽  
Electrical Power ◽  
Simulation Platform ◽  
Electrical System ◽  
Electrical Power Systems ◽  
Electrical Grid ◽  
Simulation Tools ◽  
Initial Survey

In order to analyze the safety of nuclear power plants (NPP), interactions between thermomechanical and automation processes, the on-site electrical grid, and the off-site transmission system should be studied in detail. However, an initial survey of simulation tools used for the modelling and simulation of NPP shows that existing simulation tools have some drawbacks in properly simulating the aforementioned interactions. In fact, they simulate detailed electrical power systems and thermomechanical systems but neglect the detailed interactions of the electrical system with thermomechanical and automation processes. To address this challenge, this paper develops an open-source co-simulation platform which connects Apros, a proprietary simulator of the thermomechanical and automation processes in NPP, to power system simulators. The proposed platform provides an opportunity to simulate both the electrical and thermomechanical systems of an NPP simultaneously, and study the interactions between them without neglecting any details. This detailed analysis can identify critical faults more accurately, and provides better support for probabilistic risk analyses (PRA) of NPP. To investigate the effectiveness of the proposed platform, detailed thermomechanical and electrical models of an NPP, located in Finland, are cosimulated. The preliminary results emphasize that neglecting the detailed interactions between domains of NPP may lead to inaccurate simulation results and may affect NPP safety.

scholarly journals STUDI KARAKTERISTIK PEMBENTUKAN UAP DALAM PEMBANGKIT UAP HELIKAL PADA REAKTOR MODULAR DAYA KECIL

2015 ◽  
Vol 17 (2) ◽  
pp. 59
Author(s):  
Susyadi Susyadi ◽  
Hendro Tjahjono ◽  
Sukmanto Dibyo ◽  
Jupiter Sitorus Pane
Keyword(s):  
Steam Generator ◽  
Nuclear Power ◽  
Superheated Steam ◽  
Saturation Temperature ◽  
Outer Side ◽  
Thermodynamic Efficiency ◽  
Feed Water ◽  
Primary System ◽  
Electrical Grid ◽  
Generator Design

Reaktor modular daya kecil (SMR) sangat cocok untuk  dibangun Indonesia, terutama pada lokasi-lokasi dengan kapasitas jaringan listrik yang rendah sehingga investigasi lebih jauh tentang reaktor ini sangat diperlukan. Umumnya SMR memiliki bentuk pembangkit uap yang kompak dan terintegrasi di dalam bejana tekan. Disain tersebut menyebabkan perbedaan pendekatan dalam memproduksi uap dibandingkan reaktor nuklir konvensional yang menggunakan pembangkit uap tabung-u terbalik. Oleh karena itu tujuan dari penelitian ini adalah untuk mengetahui karakteristik uap dan pola pembentukkannya di dalam pembangkit uap tipe helikal yang banyak digunakan oleh SMR. Metoda yang dipakai adalah dengan melakukan pemodelan dan perhitungan numerik menggunakan program RELAP5. Dalam pemodelan, aliran air umpan  bertekanan dan temperatur rendah dimasukkan ke dalam tabung helikal sementara aliran fluida bertekanan dan temperatur tinggi, yang mewakili pendingin sistem primer reaktor, berada di sisi luar tabung. Hasil perhitungan menunjukkan bahwa uap yang dihasilkan oleh pembangkit uap helikal bersifat lewat jenuh yakni sekitar 25 K di atas titik jenuhnya. Hal ini memberikan keunggulan komparatif dari segi disain dan operasional pada SMR dibanding reaktor konvensional karena uap lewat jenuh yang dihasilkan dapat mengurangi kerugian turbin dan sekaligus meningkatkan efisiensi termodinamika. Kata kunci: pembangkit uap helikal, SMR, PWR, uap lewat jenuh, RELAP5  Small modular reactor (SMR) is very suitable to be deployed in Indonesia especially for locations having low electrical grid capacity, so  further investigation on the characteritic of this reactor is needed. In general SMR has a compact and integrated-to-vessel steam generator design. This design implies different approach in producing steam as compared to conventional nuclear power plant  having inverted u-tube steam generator. For that reason, this research is intended to investigate the steam characteristic and how it is generated in the helical SG which is widely used in SMR. The method used is through numerical calculation of the SG model using RELAP5 code. In the model, the feed-water which has low pressure and temperature is flown into helical tubes while high pressure and temperatur fluid, which represents reactor primary system coolant, stays in outer side of the tube. Calculation result shows that the steam produced by helical steam generator is superheated, i.e. about 25 K above saturation temperature. This provides comparative advantage to SMR on the design and operational aspects compared to conventional  reactors because the superheated steam it produces can reduce turbine losses and at the same time increase thermodynamic efficiency. Keywords: helical steam generator, SMR, PWR, superheated steam, RELAP5

The Effects of Ion Implantation on the Surface Features of Inconel 600

1985 ◽  
Vol 43 ◽  
pp. 288-289
Author(s):  
John D. Rubio
Keyword(s):  
Grain Boundary ◽  
Ion Implantation ◽  
Nuclear Power ◽  
Power Plants ◽  
Surface Region ◽  
Selective Dissolution ◽  
Boundary Region ◽  
Near Surface ◽  
Inconel 600 ◽  
Steam Generator Tubing

The degradation of steam generator tubing at nuclear power plants has become an important problem for the electric utilities generating nuclear power. The material used for the tubing, Inconel 600, has been found to be succeptible to intergranular attack (IGA). IGA is the selective dissolution of material along its grain boundaries. The author believes that the sensitivity of Inconel 600 to IGA can be minimized by homogenizing the near-surface region using ion implantation. The collisions between the implanted ions and the atoms in the grain boundary region would displace the atoms and thus effectively smear the grain boundary.To determine the validity of this hypothesis, an Inconel 600 sample was implanted with 100kV N2+ ions to a dose of 1x1016 ions/cm2 and electrolytically etched in a 5% Nital solution at 5V for 20 seconds. The etched sample was then examined using a JEOL JSM25S scanning electron microscope.

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