Posiva's Site Investigations Programme

2003 ◽  
Vol 807 ◽  
Author(s):  
Veijo Ryhänen
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Waste Management ◽  
Nuclear Waste ◽  
Nuclear Power ◽  
Spent Nuclear Fuel ◽  
Crystalline Rock ◽  
Nuclear Waste Management ◽  
Spent Fuel ◽  
Medium Level

Four nuclear power plant units have been operated in Finland over 20 years. The plants are located at two sites, Olkiluoto and Loviisa. Responsibility for nuclear waste management lies on the utilities, which have established a joint company POSIVA to take care of spent fuel disposal and other expert tasks of nuclear waste management.Already in 1983 the Finnish Government set the objectives and the schedule for the national waste management programme. Since then, two shallow underground repositories have been constructed for low- and medium-level operating waste in crystalline rock at the power plant sites. At the end of 2002 the amount of operating waste emplaced in these two facilities was 4923 m3 (total accumulation 6724 m3).Spent nuclear fuel is stored in interim storage pools at the nuclear power plant sites. The total accumulation was 1228 tU at the end of 2002. Today, the main activities in nuclear waste management concern spent fuel disposal deep in the Finnish bedrock. Apart from technical and scientific issues, a major challenge faced has been the creation of sufficient public acceptance, which is a must in order to obtain favourable political decisions.

A Regulatory Authority's Needs for R&D to Develop Competence in Assessing Nuclear Waste Management Safety

1997 ◽  
Vol 506 ◽  
Author(s):  
Sören Norrby
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Waste Management ◽  
Nuclear Waste ◽  
Regulatory Authority ◽  
Nuclear Power ◽  
Nuclear Waste Management ◽  
Set Up

ABSTRACTA regulatory authority in the field of nuclear waste management will not be responsible for the waste management itself. The regulator will however be responsible for reviewing the safety of the waste management activities proposed and performed by nuclear power plant owners or special organisations set up to manage and dispose of nuclear waste. In this paper the regulator's need for R&D to develop competence in the assessment of nuclear waste management safety is discussed.

scholarly journals Effects of %FIMA on Storage-Safety Parameters of Spent Fuel from Experimental Pebble-Bed Reactor

2021 ◽  
Vol 50 (2) ◽  
pp. 525-536
Author(s):  
Aisyah Aisyah ◽  
Mirawaty Mirawaty ◽  
Dwi Luhur Ibnu Saputra ◽  
Risdiyana Setiawan ◽  
Pungky Ayu Artian ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Spent Nuclear Fuel ◽  
Spent Fuel ◽  
Pebble Bed ◽  
Energy Agency ◽  
Safety Level ◽  
Pebble Bed Reactor ◽  
Decay Heat

The back end of the utilization of nuclear technology is safety and management of spent fuel, which is a key element contributing to the success of the nuclear power plant program. Indonesia’s National Nuclear Energy Agency resolved to establish an experimental power reactor, called RDE, as a nuclear power plant demo. The fuel of this reactor is similar to that of German’s experimental pebble-bed reactor (PBR), Arbeitsgemeinschaft Versuchsreaktor(AVR). In this study, the spent fuel of AVR was studied to obtain the safety parameter data for storage of RDE spent fuel by varying the fission in the initial metallic atoms (%FIMA). These parameters that must be studied include the radioactivity, decay heat, proliferation threats of both 239Pu and 235U, and the presence of 137Cs, a dangerous fission product that can escape from damaged spent fuels. The calculation was conducted by ORIGEN 2.1. The result of the study demonstrates a higher %FIMA indicates a higher safety level that is required since the activity and decay heat of the spent fuel will increase and, as will be the total amounts of 239Pu and 137Cs. However, the 235U amount will decrease. For a 100 years storage of spent fuel, the optimum %FIMA is 8.2 with a canister capacity of 1,900 pebbles. Further, the activity and decay heat of the spent nuclear fuel are 2.013 × 1013 Bq and 6.065 W, respectively. The activities of 239Pu, 137Cs, and 235U are 5.187 ×1011, 7.100 × 1012, and 7.339 × 107 Bq, respectively.

Local Negotiation on Compensation: Siting of the Spent Nuclear Fuel Repository in Finland

2007 ◽  
Author(s):  
Matti Kojo
Keyword(s):  
Waste Management ◽  
Nuclear Fuel ◽  
Nuclear Waste ◽  
Nuclear Power ◽  
Spent Nuclear Fuel ◽  
Negotiation Process ◽  
Background Information ◽  
Nuclear Waste Management ◽  
Power Company ◽  
The Relationship

The aim of the paper is to analyse the local negotiation process between the Municipality of Eurajoki and the nuclear power company Teollisuuden Voima (TVO) and the nuclear waste management company Posiva Oy. The aim of the negotiations was to find an acceptable form of compensation for siting a spent nuclear fuel repository in Olkiluoto, Finland. The paper includes background information on the siting process in Finland, the local political setting in the Municipality of Eurajoki and a description of the negotiation process. The analysis of the negotiations on compensation is important for better understanding the progress of the Finnish siting process. The paper describes the picture of the contest to host the spent nuclear fuel repository. It also provides more information on the relationship between the Municipality of Eurajoki and the power company TVO. The negotiations on compensation and the roles of various players in the negotiations have not been studied in detail because the minutes of the Vuojoki liaison group were not available before the decision of the Supreme Administrative Court in May 2006.

scholarly journals Az atomenergia alkalmazására vonatkozó legfőbb nemzetközi, európai uniós és hazai jogi előírások

2020 ◽  
Vol 15 (28) ◽  
pp. 202-259
Author(s):  
Bianka Flekácsné Kocsis
Keyword(s):  
European Union ◽  
Comparative Analysis ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Waste ◽  
Nuclear Power ◽  
Atomic Energy ◽  
Nuclear Waste Management ◽  
Legal Rules ◽  
Industrial Project

This study aims to present the main international, European Union and domestic legal rules on use of atomic energy by applying the method of comparative analysis. Current reason of this topic is the ongoing Paks 2 project. An industrial project like this requires a highly complex and lengthy licensing process and the nuclear power plant units need to comply with several international, European Union and domestic regulations not only during the licensing process, but throughout erection and operation periods as well. Connected with that, this study examines various legal rules on safety application of using atomic energy, underlining the following topics: liability, safety, and nuclear waste management. In Hungary the Hungarian Atomic Energy Authority is liable for adaptation of the relating regulation. It supplies its tasks by cooperating with several international and European Union authorities.

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 Microbial enrichment and gene functional categories revealed on the walls of a spent fuel pool of a nuclear power plant

PLoS ONE ◽  
2018 ◽  
Vol 13 (10) ◽  
pp. e0205228 ◽  
Author(s):  
Rosane Silva ◽  
Darcy Muniz de Almeida ◽  
Bianca Catarina Azeredo Cabral ◽  
Victor Hugo Giordano Dias ◽  
Isadora Cristina de Toledo e Mello ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Spent Fuel ◽  
Functional Categories ◽  
Spent Fuel Pool

scholarly journals Seismic safety evaluation during site selection for the nuclear power plants in Bangladesh

2018 ◽  
Vol 4 (4) ◽  
pp. 251-256 ◽  
Author(s):  
Sergey Shcheklein ◽  
Ismail Hossain ◽  
Mohammad Akbar ◽  
Vladimir Velkin
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Spent Nuclear Fuel ◽  
Heat Removal ◽  
Good Time ◽  
Diagnostics System ◽  
Seismic Impacts

Bangladesh lies in a tectonically active zone. Earlier geological studies show that Bangladesh and its adjoining areas are exposed to a threat of severe earthquakes. Earthquakes may have disastrous consequences for a densely populated country. This dictates the need for a detailed analysis of the situation prior to the construction of nuclear power plant as required by the IAEA standards. This study reveals the correlation between seismic acceleration and potential damage. Procedures are presented for investigating the seismic hazard within the future NPP construction area. It has been shown that the obtained values of the earthquake’s peak ground acceleration are at the level below the design basis earthquake (DBE) level and will not lead to nuclear power plant malfunctions. For the most severe among the recorded and closely located earthquake centers (Madhupur) the intensity of seismic impacts on the nuclear power plant site does not exceed eight points on the MSK-64 scale. The existing predictions as to the possibility of a super-earthquake with magnitude in excess of nine points on the Richter scale to take place on the territory of the country indicate the necessity to develop an additional efficient seismic diagnostics system and to switch nuclear power plants in good time to passive heat removal mode as stipulated by the WWER 3+ design. A conclusion is made that accounting for the predicted seismic impacts in excess of the historically recorded levels should be achieved by the establishment of an additional efficient seismic diagnostics system and by timely switching the nuclear power plants to passive heat removal mode with reliable isolation of the reactor core and spent nuclear fuel pools.

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