Handling of radioactive waste at Soviet nuclear power stations

1969 ◽  
Vol 26 (5) ◽  
pp. 469-478
Author(s):  
B. S. Kolychev ◽  
A. N. Matveev ◽  
A. A. Khonikevich
Keyword(s):  
Radioactive Waste ◽  
Nuclear Power ◽  
Power Stations

Research and development activities for cleanup of the Fukushima Daiichi Nuclear Power Station

2013 ◽  
Vol 1518 ◽  
pp. 257-268
Author(s):  
Toshiki Sasaki ◽  
Shuji Kaminishi ◽  
Yasuaki Miyamoto ◽  
Hideyuki Funasaka
Keyword(s):  
Radioactive Waste ◽  
Research And Development ◽  
Nuclear Power Station ◽  
Nuclear Power ◽  
Hydrogen Generation ◽  
Power Station ◽  
Power Stations ◽  
Fukushima Daiichi ◽  
Different Characteristics ◽  
And Diffusion

ABSTRACTThe Fukushima Daiichi nuclear power station accident and restoration works have produced significant volume of radioactive waste. The waste has very different characteristics from usual radioactive waste produced in nuclear power stations and it requires extensive research and development for management of the waste. R&D works such as analysis of the waste properties, hydrogen generation by radiolysis and diffusion in a storage vessel and corrosion of storage vessels, etc. have been performed for characterization and safe storage of the waste. The detailed R&D plan for processing and disposal waste will be established by the end of FY2012.

European Communities

1961 ◽  
Vol 15 (2) ◽  
pp. 321-324 ◽  
Keyword(s):  
Radioactive Waste ◽  
Nuclear Power ◽  
Technical Committee ◽  
Atomic Energy ◽  
Research Project ◽  
Job Experience ◽  
Power Stations ◽  
Information Center ◽  
Energy Community

The Scientific and Technical Committee of the European Atomic Energy Community (Euratom), holding its tenth session in Brussels on October 4, 1960, approved the following undertakings: 1) the establishment of a European information center on the use of radioisotopes; 2) Euratom's participation in studies of the problems involved in using nuclear power for ships; 3) the completion of Euratom's reactor research project, carried out jointly with the French Commissariat à l'Energie Atomique (CEA); 4) the proposal to conclude agreements with companies building or operating nuclear-power stations where Community trainees could gain on-the-job experience in construction and operation; and 5) the study of methods for disposing of radioactive waste underground and in the sea.

Reprocessing spent fuel from nuclear power stations and liquid radioactive waste at the mayak processing center

Atomic Energy ◽  
1997 ◽  
Vol 83 (6) ◽  
pp. 904-909 ◽  
Author(s):  
Yu. V. Glagolenko ◽  
E. G. Dzekun ◽  
G. M. Medvedev ◽  
S. I. Povnyi ◽  
V. P. Ufimtsev ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Nuclear Power ◽  
Liquid Radioactive Waste ◽  
Spent Fuel ◽  
Power Stations

An evaluation of the equipment tagging process in nuclear power stations

1983 ◽  
Author(s):  
Peter Doyle ◽  
Lothar Schroeder ◽  
Stephen Brewer
Keyword(s):  
Nuclear Power ◽  
Power Stations

Environmental Protection Meets Security of Electricity Supply

2021 ◽  
pp. 1-18
Author(s):  
Ilina Cenevska
Keyword(s):  
Environmental Protection ◽  
Nuclear Power ◽  
Habitats Directive ◽  
Electricity Supply ◽  
The European Union ◽  
Power Stations ◽  
Court Of Justice ◽  
National Energy Policy ◽  
The Relationship ◽  
Practical Implications

Abstract This case comment explores the relationship between two intertwined objectives – ensuring security of electricity supply and environmental protection – in the context of the judgment of the Court of Justice of the European Union in Inter-Environnement Wallonie ASBL and Bond Beter Leefmilieu Vlaanderen ASBL v. Conseil des ministres. The analysis focuses on the application of the Environmental Impact Assessment Directive and the Habitats Directive to the facts of the case, which concerns the extension by a ten-year period of the operation of two Belgian nuclear power stations (Doel 1 and Doel 2) as part of a national energy policy strategy to ensure the security of Belgium's electricity supply. The case comment also considers the legal and practical implications that arise as a result of employing the ‘security of electricity supply’ exemption to enable derogation from the requirements of the aforementioned Directives in circumstances where a Member State considers the security of its electricity supply to be under threat.

Evaluation of the residual stress in stainless steel 304L hydraulically expanded joints

2020 ◽  
pp. 095440892096401
Author(s):  
Ying Hong ◽  
Xuesheng Wang ◽  
Yan Wang ◽  
Zhao Zhang ◽  
Yong Han
Keyword(s):  
Residual Stress ◽  
Stainless Steel ◽  
Yield Strength ◽  
Residual Stresses ◽  
Heat Exchangers ◽  
Nuclear Power ◽  
The Finite Element Method ◽  
Power Stations ◽  
Stainless Steel 304 ◽  
Initial Clearance

Stainless steel 304 L tubes are commonly used in the fabrication of heat exchangers for nuclear power stations. The stress corrosion cracking (SCC) of 304 L tubes in hydraulically expanded tube-to-tubesheet joints is the main reason for the failure of heat exchangers. In this study, 304 L hydraulically expanded joint specimens were prepared and the residual stresses of a tube were evaluated with both an experimental method and the finite element method (FEM). The residual stresses in the outer and inner surfaces of the tube were measured by strain gauges. The expanding and unloading processes of the tube-to-tubesheet joints were simulated by the FEM. Furthermore, an SCC test was carried out to verify the results of the experimental measurement and the FEM. There was good agreement between the FEM and the experimental results. The distribution of the residual stress of the tube in the expanded joint was revealed by the FEM. The effects of the expansion pressure, initial tube-to-hole clearance, and yield strength of the tube on the residual stress in the transition zone that lay between the expanded and unexpanded region of the tube were investigated. The results showed that the residual stress of the expanded joint reached the maximum value when the initial clearance was eliminated. The residual stress level decreased with the decrease of the initial tube-to-hole clearance and yield strength. Finally, an effective method that would reduce the residual stress without losing tightness was proposed.

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