نتایج جستجو برای: nuclear reactor steam generator

تعداد نتایج: 323732  

2010
Hugo da Silva

This report describes our investigation of steam generator behavior during a postulated tube rupture accident. Our study was performed using the steam generator, thermal-hydraulic analysis code THERMIT-UTSG. The purpose of our work was to provide an independent assessment of the Los Alamos National Laboratory system code TRAC-PF1 with respect to steam generator tube rupture analysis. Results of...

2016
S. A. Kotb M. M. Metwally K. M. Rady

ABSTRACT The pressurized water reactor type power plant has a sophisticated automatic control systems. On the primary side, The Control rod system and the Soluble boron control the core neutron flux. On the secondary side, output steam is controlled by the turbine control valve and steam dump system. During the automatic control mode, the two sides work in a synchronized way so that transition ...

Journal: : 2022

The main lessons of the major accident at Fukushima-Daiichi NPP in 2011 for nuclear power industry identify need to model, analyze and develop emergency measures relatively unlikely events with catastrophic environmental consequences, taking into account multiple failures safety systems. Steam-gas explosions became one causes consequences Chernobyl Fukushima accidents. Criteria conditions occur...

Journal: :ITM web of conferences 2022

The implementation logic of different ISI items steam generator during the refueling outage nuclear power plant was studied. Based on relationship between window and main line plan outage, some optimization suggestions planning, preparation relevant were given, aimed at reducing inspection time SG collective dose inspectors.

2008
I. Kadenko N. Sakhno

Steam generator (SG) tube integrity is of great importance for safe and reliable nuclear power plant (NPP) operation. The application of eddy current testing (ET) to evaluate SG tube integrity is recognized worldwide and has been used over several decades. However, at times, ET results are considered questionable. A decision to leave a defective SG tube in operation is made based on the ET resu...

2003
H. Shekhar R. Polikar

An automated algorithm is presented for the analysis and classification of eddy current bobbin probe data obtained from nuclear power plant steam generator tubes (SGT). This algorithm attempts to find a balance between the two seemingly conflicting requirements of SGT eddy current data analysis, namely, detecting and identifying as many of the actual defects as possible, whilst limiting the num...

2008
F. Eid

Previous work [1] has shown that MEMS technology has significant potential to create more compact, higherperforming hardware for chemical oxygen iodine lasers (COIL). In COILs, the laser medium is a flowing gas that must be pumped through the system at high mass flow rates to ensure proper system operation. As a result, compact pumps with high pumping rates are a key element of the COIL system....

Journal: :iranian journal of hydrogen & fuel cell 2015
elham omidbakhsh amiri

a micro-channel heat exchanger reactor with different micro-baffle shapes has been studied numerically. governing equations were solved base on the finite volume method with fluent software. in upper section, oxidation reaction of methanol was occurred and in lower section, steam reforming of methanol was done. two sections were separated with solid part which played as heat exchanger and trans...

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