scholarly journals Preferred Site Selection Using GIS and AHP: Case Study in Bangka Island NPP Site

2021 ◽  
Vol 23 (1) ◽  
pp. 51
Author(s):  
Ari Nugroho ◽  
Eko Kusratmoko ◽  
Tito L. Indra
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Site Selection ◽  
Nuclear Power ◽  
Power Plants ◽  
Cooling System ◽  
Final Decision ◽  
Unstable Flow ◽  
Energy Agency

PREFERRED SITE SELECTION USING GIS AND AHP: CASE STUDY IN BANGKA ISLAND NPP SITE. Industrial growth affects the increasing demand for electricity in various places, this also occurs on the island of Bangka. So far, electricity supply has only been obtained from fossil fuel power plants with inadequate capacity, unstable flow and depending on fuel supplies from outside the island. For this reason, it is necessary to build a Nuclear Power Plant (PLTN) which is believed to be reliable and able to overcome these problems. In order to prepare a safe and economical nuclear power plant site, influential parameters such as population density, cooling system, land clearing, cut and fill, and granite for the foundation have been analyzed. The novelty of this analysis lies in 2 methods which gradually used before come up with a final decision, namely spatial analysis and pairwise comparison using Geographic Information Systems (GIS) and Analytical Hierarchy Process (AHP), respectively. The scope of study area is based on the site vicinity (1:5.000) scale, located in the districts of West and South Bangka. The siting process refers to the rules set by the International Atomic Energy Agency (IAEA). Based on the final results of the analysis using the expert choice program, the numerical weights for West Bangka and South Bangka were 0.709 and 0.291, respectively, with a consistency value of 0.03.

Human reliability in non-destructive inspections of nuclear power plant components: modeling and analysis

2019 ◽  
Vol 7 (2B) ◽  
Author(s):  
Vanderley Vasconcelos ◽  
Wellington Antonio Soares ◽  
Raissa Oliveira Marques ◽  
Silvério Ferreira Silva Jr ◽  
Amanda Laureano Raso
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Human Factors ◽  
Nuclear Power ◽  
Power Plants ◽  
Failure Modes ◽  
Cooling System ◽  
Human Reliability ◽  
Non Destructive ◽  
Plant Components

Non-destructive inspection (NDI) is one of the key elements in ensuring quality of engineering systems and their safe use. This inspection is a very complex task, during which the inspectors have to rely on their sensory, perceptual, cognitive, and motor skills. It requires high vigilance once it is often carried out on large components, over a long period of time, and in hostile environments and restriction of workplace. A successful NDI requires careful planning, choice of appropriate NDI methods and inspection procedures, as well as qualified and trained inspection personnel. A failure of NDI to detect critical defects in safety-related components of nuclear power plants, for instance, may lead to catastrophic consequences for workers, public and environment. Therefore, ensuring that NDI is reliable and capable of detecting all critical defects is of utmost importance. Despite increased use of automation in NDI, human inspectors, and thus human factors, still play an important role in NDI reliability. Human reliability is the probability of humans conducting specific tasks with satisfactory performance. Many techniques are suitable for modeling and analyzing human reliability in NDI of nuclear power plant components, such as FMEA (Failure Modes and Effects Analysis) and THERP (Technique for Human Error Rate Prediction). An example by using qualitative and quantitative assessesments with these two techniques to improve typical NDI of pipe segments of a core cooling system of a nuclear power plant, through acting on human factors issues, is presented.

Belarusian Ostrovets nuclear power plant: the challenge of cross-border negotiations to balance economic development and environmental protection†

2020 ◽  
Vol 13 (2) ◽  
pp. 157-168
Author(s):  
Aslan Khuseinovich Abashidze ◽  
Vladimir Mikhailovich Filippov ◽  
Alexander Mikhailovich Solntsev
Keyword(s):  
Economic Development ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Environmental Protection ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
International Environmental Agreements ◽  
Environmental Agreements ◽  
Energy Agency

Abstract States have sovereign rights that allow them to construct nuclear power plants. Moreover, engaging with nuclear power generation makes possible the achievement of the Sustainable Development Goals (2016–30) in combatting climate change, paramount to the Paris Agreement’s initiatives. In the same vein, however, constructing and operating power plants pose strict dangers to both general safety of the public and to national security. Thus, plant operations should strictly abide by the International Atomic Energy Agency (IAEA) standards and international law. As a result, it is important to consider the potential transboundary impacts of nuclear power plants and to conduct an appropriate transboundary environmental impact assessment (EIA). The article examines the construction of the Ostrovets Nuclear Power Plant by Belarus, close to the border of the Republic of Lithuania. The question in focus, however, is as follows: what international procedure can be used to coordinate issues of potentially negative transboundary impacts? Lithuania, in order to avoid the operation of the nuclear power plant, thus sought peaceful settlement of the dispute making use of the dispute resolution mechanisms based on international environmental agreements. The authors of this study show that the treaty bodies, established on the basis of international environmental agreements, provide important assistance in this matter in coordination with the IAEA. The use of these quasi-judicial means of resolving interstate disputes proves effective in pursuing a compromise between economic development and environmental protection. In the absence of such mechanisms at a universal level, one should consider utilizing such mechanisms in other regions of the world.

scholarly journals Assessment of Adequate Margin to Liquefaction for Nuclear Power Plants

2018 ◽  
Vol 2018 ◽  
pp. 1-7 ◽  
Author(s):  
Tamás János Katona
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Ground Acceleration ◽  
Design Basis ◽  
Essential Question ◽  
Radioactive Release ◽  
Adequate Margin

Design of nuclear power plant shall provide an adequate margin to protect items ultimately necessary to prevent an early large radioactive release in the case of earthquakes exceeding those considered in the design. An essential question is how large the margin should be to be accepted as adequate. In the practice, depending on the country regulation, a plant margin of at least 1.4 or 1.67 times the design basis peak ground acceleration is required to be demonstrated. The catastrophe at the Fukushima Daiichi Nuclear Power Plant revealed the fundamental experience that the plants designed in compliance with nuclear standards can survive the effects of the vibratory ground motion due to disastrous earthquake but may fail due to effects of phenomena accompanying or generated by the earthquakes. Liquefaction is one of those secondary effects of beyond-design basis earthquakes that should be investigated for NPPs at soil sites. However, the question has not been investigated up to now, whether a “margin earthquake”, vibratory effects of which the plant can withstand thanks to design margin, will not induce liquefaction at soil sites and will not result in loss of safety functions. In the paper, a procedure is proposed for calculation of the probability and margin to liquefaction. Use of the procedure is demonstrated on a case study with realistic site-plant parameters. Criteria for probability for screening and acceptable probabilistic margin to liquefaction are proposed. The possible building settlement due to margin earthquake is also assessed.

Nuclear Power Plant Site Selection: A Case Study

1985 ◽  
Vol 69 (1) ◽  
pp. 7-13 ◽  
Author(s):  
Yaakov Lugasi ◽  
Abraham Mehrez ◽  
Zilla Sinuany-Stern
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Site Selection ◽  
Nuclear Power ◽  
Plant Site

scholarly journals A two‐stage decision framework for inland nuclear power plant site selection based on GIS and type‐2 fuzzy PROMETHEE II: Case study in China

2020 ◽  
Vol 8 (6) ◽  
pp. 1941-1961 ◽  
Author(s):  
Yunna Wu ◽  
Fangtong Liu ◽  
Yong Huang ◽  
Chuanbo Xu ◽  
Buyuan Zhang ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Site Selection ◽  
Nuclear Power ◽  
Two Stage ◽  
Promethee Ii ◽  
Plant Site ◽  
Fuzzy Promethee

scholarly journals Safety Assessment of Low-Contaminated Equipment Dismantling at Nuclear Power Plants

2015 ◽  
Vol 2015 ◽  
pp. 1-11 ◽  
Author(s):  
Egidijus Babilas ◽  
Eugenijus Ušpuras ◽  
Sigitas Rimkevičius ◽  
Gintautas Dundulis ◽  
Mindaugas Vaišnoras
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Safety Assessment ◽  
Power Plants ◽  
Structural Integrity ◽  
Building Structures ◽  
Nuclear Facilities ◽  
Energy Agency ◽  
Force Calculation

The decommissioning of nuclear facilities requires adequate planning and demonstration that dismantling and decontamination activities can be conducted safely. Existing safety standards require that an appropriate safety assessment be performed to support the decommissioning plan for each facility (International Atomic Energy Agency, 2006). This paper presents safety assessment approach used in Lithuania during the development of the first dismantling and decontamination project for Ignalina NPP. The paper will mainly focus on the identification and assessment of the hazards raised due to dismantling and decontamination activities at Ignalina Nuclear Power Plant and on the assessment of the nonradiological and radiological consequences of the indicated most dangerous initiating event. The drop of heavy item was indicated as one of most dangerous initiating events for the discussed Ignalina Nuclear Power Plant dismantling and decontamination project. For the analysis of the nonradiological impact the finite element model for the load drop force calculation was developed. The radiological impact was evaluated in those accident cases which would lead to the worst radiological consequences. The assessments results show that structural integrity of the building and supporting columns of building structures will be maintained and radiological consequences are lower than the annual regulatory operator dose limit.

scholarly journals Early quantification of reliability for a safety critical and control system: a case study of reactor core cooling system

2018 ◽  
Vol 7 (2.12) ◽  
pp. 248
Author(s):  
Vinay Kumar ◽  
Suraj Gupta ◽  
Anil Kumar Tripathi
Keyword(s):  
Control System ◽  
Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Cooling System ◽  
Reactor Core ◽  
Safety Critical ◽  
Core Cooling ◽  
And Control

Using Probabilistic Reliability analysis for Quantifying reliability of a system is already a common practice in Reliability Engineering community. This method plays an important role in analyzing reliability of nuclear plants and its various components. In Nuclear Power Plants Reactor Core Cooling System is a component of prime importance as its breakdown can disrupt Cooling System of power plant. In this paper, we present a framework for early quantification of Reliability and illustrated with a Safety Critical and Control System as case study which runs in a Nuclear Power Plant.  

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