scholarly journals Analysis of Heat Transfer in The VVER-1200 Reactor’s Heat Channel

2017 ◽  
Vol 33 (3) ◽  
Author(s):  
Thin Dinh Van ◽  
Loat Van Bui ◽  
Hong Thi Bui
Keyword(s):  
Heat Transfer ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
High Reliability ◽  
Modern Method ◽  
Safe Operation ◽  
The World ◽  
The Government ◽  
First Time

In early 2015, the Government of Vietname has decided to choose VVER-1200 Russian-made technology for building at the Nuclear Power Plant in Ninh Thuan 1, this is the advanced reactor generation III + and the only one has been completed for the first time in the world in August 2016. Vietnam is facing a major challenge, which is how to ensure the acquired technology transfer process, then the safe operation of thisunit. This article analyzes some of the heat changes occur in reactor when there are changes of the heatflux. This is an issue directly related to the workof predictingincidents and give ways to fix the problem when the plant is in conditions such as  startup, normal and abnormaloperations. For analysis, the authors used CFD methods, this is a very modern method and have high reliability. The results received have fit well when compared with the safety analysis report of Rosatom published.

scholarly journals REVIEW OF FIRE HAZARD ANALYSIS OF IGNALINA NUCLEAR POWER PLANT

2004 ◽  
Vol 10 (3) ◽  
pp. 169-175
Author(s):  
Aleksandr Alejev ◽  
Mečislovas Griškevičius ◽  
Ritoldas Šukys ◽  
Ian Frith ◽  
Antti Norta
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Fire Safety ◽  
Nuclear Power ◽  
Fire Hazard ◽  
Hazard Analysis ◽  
Plant Operation ◽  
Type Reactor ◽  
The World ◽  
First Time

Fire safety is important throughout the lifetime of a plant, from design to construction and commissioning, throughout plant operation and to decommissioning. The article is the document that will present the review results of the documents by VATESI during licensing Unit 1, 2 and provides information how Ignalina NPP to meet State requirements and international recommendations to achieve and maintain satisfactory fire safety. Fire hazard analysis of operation RBMK‐1500 type reactor is done for first time in the world practice.

Distrust in government and its relationship with mental health after the Fukushima nuclear power plant accident

2020 ◽  
pp. 002076402096812
Author(s):  
Maiko Fukasawa ◽  
Norito Kawakami ◽  
Maki Umeda ◽  
Tsuyoshi Akiyama ◽  
Naoko Horikoshi ◽  
...  
Keyword(s):  
Mental Health ◽  
Depressive Symptoms ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Residential Area ◽  
National Government ◽  
Nuclear Power Plant Accident ◽  
Fukushima Prefecture ◽  
The Government

Background: Distrust in authorities has negative effects on mental health. Aims: In this study, we aimed to explore whether the impact of distrust in government on mental health became stronger in the area heavily affected by the 2011 Fukushima nuclear power plant accident. Methods: We examined the effects of distrust in the national government on depressive symptoms three years after the accident among community residents in Fukushima prefecture using those in the Kanto area (the area surrounding Tokyo) as a control. A questionnaire survey was administered to a random sample of 1000 residents in Fukushima prefecture and 1650 residents in the Kanto area. Distrust in the national government was assessed using a four-point single-item scale. Depressive symptoms were measured using the Patient Health Questionnaire-9. The associations of residential area (i.e. living in Fukushima prefecture or in the Kanto area) and distrust in the national government with depressive symptoms were examined, controlling for socio-demographic characteristics and disaster-related experiences using multivariate linear regression analyses. We used the interaction term of residential area and distrust in the government to explore the difference in the association between the respondents in Fukushima prefecture and those in the Kanto area. Results: Valid responses were obtained from 976 (36.8%) residents. Distrust in the government was associated with depressive symptoms and the association was stronger in Fukushima prefecture than in the Kanto area. Conclusion: The deleterious effects of distrust in the government on mental health may become more serious after a nuclear power plant accident and require careful attention during support activities in an affected area.

scholarly journals The institutional structure for decommissioning Fukushima Daiichi nuclear power plant

2021 ◽  
pp. 014664532110153
Author(s):  
Hajimu Yamana
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Institutional Structure ◽  
Legal Responsibility ◽  
Radiological Protection ◽  
Ministry Of Education ◽  
Sports Science ◽  
Fukushima Daiichi ◽  
The Government

This paper does not necessarily reflect the views of the International Commission on Radiological Protection. This article describes the institutional structure established for decommissioning Fukushima Daiichi nuclear power plant. To deal with the aftermath of the unprecedented nuclear accident in Fukushima, several responsible institutions such as Ministry of Economy, Trade and Industry (METI), Ministry of Education, Culture, Sports, Science and Technology (MEXT) have worked together at the initiative of the Government of Japan. In this structure, Tokyo Electric Power Company Holdings (TEPCO) implements the decommissioning due to its legal responsibility, while the essential direction and milestones are set by the Nuclear Emergency Response Headquarters of the Government of Japan. Nuclear Damage Compensation and Decommissioning Facilitation Corporation, a government-affiliated organisation, oversees and facilitates the decommissioning by TEPCO, and the Nuclear Regulatory Authority regulates safety from an independent standpoint. The main basic elements essential for the success of this long-term project have been developed, such as the technical strategy, financial system, and organisational capability. Decommissioning is making progress.

Electrochemical decontamination of irradiated nuclear graphite from corrosion and fission products using molten salt

2021 ◽  
Author(s):  
Tatiana Grebennikova ◽  
Abbie N Jones ◽  
Clint Alan Sharrad
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Waste Management ◽  
Molten Salt ◽  
Nuclear Power ◽  
Fission Products ◽  
Nuclear Graphite ◽  
Irradiated Graphite ◽  
The World ◽  
The Uk

Irradiated graphite waste management is one of the major challenges of nuclear power-plant decommissioning throughout the world and significantly in the UK, France and Russia where over 85 reactors employed...

scholarly journals Neutronic safety analysis of proposed reactor technologies for Ghana’s nuclear power plant using the MCNP code

2019 ◽  
Vol 34 (3) ◽  
pp. 238-242
Author(s):  
Rex Abrefah ◽  
Prince Atsu ◽  
Robert Sogbadji
Keyword(s):  
High Pressure ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Nuclear Reactor ◽  
Atomic Energy Commission ◽  
Clean Energy ◽  
Safety Analysis ◽  
Operating Conditions ◽  
The Government

In pursuance of sufficient, stable and clean energy to solve the ever-looming power crisis in Ghana, the Nuclear Power Institute of the Ghana Atomic Energy Commission has on the agenda to advise the government on the nuclear power to include in the country's energy mix. After consideration of several proposed nuclear reactor technologies, the Nuclear Power Institute considered a high pressure reactor or vodo-vodyanoi energetichesky reactor as the nuclear power technologies for Ghana's first nuclear power plant. As part of technology assessments, neutronic safety parameters of both reactors are investigated. The MCNP neutronic code was employed as a computational tool to analyze the reactivity temperature coefficients, moderator void coefficient, criticality and neutron behavior at various operating conditions. The high pressure reactor which is still under construction and theoretical safety analysis, showed good inherent safety features which are comparable to the already existing European pressurized reactor technology.

Research of Screening and Grading Method of Ageing Sensitive Objectives in Nuclear Power Plant

2014 ◽  
Vol 543-547 ◽  
pp. 858-861
Author(s):  
Xiao Tian Liu ◽  
Yong Wang ◽  
Shao Rui Niu ◽  
Yan Zhao Zhang ◽  
Zhen Hao Shi ◽  
...  
Keyword(s):  
Fuzzy Logic ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Lessons Learned ◽  
Nonlinear Coupling ◽  
Highly Nonlinear ◽  
Ageing Management ◽  
First Time

This first step of ageing management in nuclear power plant is to determine the objectives and their priorities. The characteristics of the objectives are complex and highly nonlinear coupling. A fuzzy logic based screening and grading method have been developed in this research for the first time which combined the genetic ageing lessons learned and field expert experience to resolve the problem. The method have been approved of highly applicability and applied to ageing management in multiple nuclear power plants.

Decontamination of the Special Drainage System at NPP A-1

2001 ◽  
Author(s):  
Ján Rezbárik ◽  
Dušan Majerský ◽  
Stanislav Sekely
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Specific Activity ◽  
Drainage System ◽  
Solid Particles ◽  
Technological Systems ◽  
Solid Product ◽  
High Tendency ◽  
First Time

Abstract The first Czecho-slovak nuclear power plant A-1 was shut down after an accident in 1977 and it is now under decommissioning. In spite of that, some technological systems in nuclear power plant must remain in operation. The planned service life of these systems has already been exceeded and their technical design is not suitable for present requirements. These operated technological systems must be repaired and reconstructed. The special drainage system is one of the technological systems that must be in operation during the decommissioning process. After twenty-nine-year’-s of operation it became necessary to carry out the repairs, adaptations and replacements of some parts of this system with the aim to ensure more reliable operation and higher safety. Radioactive sludge from the bottom of the collecting tank and drain pit was pumped out using an ejector and it was caught in drums. The fixed contamination on the inner surface of the collecting tank was removed by the chemical loop decontamination method using an external circulating decontamination device. The surface of the drain pit was decontaminated with evenly spread decontamination gel that disrupted the fixed contamination. The contamination was then washed down using a water jet system with attached rotary brushes. At NPP A-1, an immobilisation method for the treatment of radioactive sludge and solid particles based on the addition of silicates was successfully used by AllDeco for the first time. This sludge is often sticky with the high tendency to settle out the liquid and has a specific activity three orders of magnitude higher than are the limits for the Conditioning Centre (with high content of alpha radionuclides) and because it is not sound and effective to treat it by technologies generally used for another type of wastes. The immobilisation of the sludge was performed at room temperature. The resulting solid product has suitable properties for temporary storage. Procedures for the verification of the treatment of further sludge from NPP A-1 have been started.

Application of RFID to High-Reliability Nuclear Power Plant Construction

2006 ◽  
Author(s):  
Kenji Akagi ◽  
Masayuki Ishiwata ◽  
Kenji Araki ◽  
Jun-Ichi Kawahata
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Mass Production ◽  
Nuclear Power ◽  
High Reliability ◽  
Construction Technology ◽  
Rfid Technology ◽  
Plant Construction ◽  
Under Construction ◽  
Production Industry

In nuclear power plant construction, countless variety of parts, products, and jigs more than one million are treated under construction. Furthermore, strict traceability to the history of material, manufacturing, and installation is required for all products from the start to finish of the construction, which enforce much workforce and many costs at every project. In an addition, the operational efficiency improvement is absolutely essential for the effective construction to reduce the initial investment for construction. As one solution, RFID (Radio Frequent Identification) application technology, one of the fundamental technologies to realize a ubiquitous society, currently expands its functionality and general versatility at an accelerating pace in mass-production industry. Hitachi believes RFID technology can be useful of one of the key solutions for the issues in non-mass production industry as well. Under this situation, Hitachi initiated the development of next generation plant concept (ubiquitous plant construction technology) which utilizes information and RFID technologies. In this paper, our application plans of RFID technology to nuclear power is described.

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