Environmental safety aspects of the new solid radioactive waste management and storage facility at the Ignalina Nuclear Power Plant

Kerntechnik ◽  
2011 ◽  
Vol 76 (5) ◽  
pp. 315-323 ◽  
Author(s):  
V. Ragaisis ◽  
P. Poskas ◽  
V. Simonis ◽  
J. E. Adomaitis
Author(s):  
Tero Lytsy ◽  
Mia Ylä-Mella

Fennovoima is Finland’s third nuclear power company founded in 2007. Fennovoima will build a new nuclear power plant, Hanhikivi 1, in Pyhäjoki municipality located in Northern Finland. Currently Fennovoima is evaluating bids from reactor suppliers. Originally two suppliers, AREVA and Toshiba Heavy Industries were invited to bid for the plant but later also a bid from Rosatom were invited. The plant supplier will be selected in 2013. Platom is a Finnish company with extensive experience in radioactive waste management. In the beginning of 2008, Platom was assigned by Fennovoima as radioactive waste management consultant and to develop radioactive waste management strategy and to support Fennovoima in negotiations with plant suppliers in waste management aspects. Since Fennovoima has started, there have been some changes to the regulatory requirements which had to be taken into account while developing the strategy. One important change is due to the Government Degree 27.11.2008/736 which establishes a new waste category of very low-level waste following international development and the “new” IAEA waste classification. Other important change was introduced by the change 342/2008 to the Nuclear Energy Act allowing some nuclear waste to be delivered to another country for treatment. These and many more requirements had to be considered when developing the strategy. Early work by Platom was mostly done to support development of application for Decision-in-Principle. This was the first important licensing step for Fennovoima. Work started with studies and plans which were used by Fennovoima to gather the know-how required to draw up the application. Descriptions of waste streams and waste management technologies were developed as well as preliminary waste inventories and studies for final disposal, including preliminary dimensioning of the repository facilities. Based on these plans nuclear regulator’s preliminary safety assessment was performed. The work was successfully completed as in 2010 the Government of Finland granted Fennovoima a permit to build a new nuclear power plant. The work continued in 2012 when bids were received for EPR and ABWR type reactors. Plans developed earlier were elaborated into a detailed strategy and the proposed waste management solutions were evaluated. This allowed feedback from the bids into the strategy and to the bid specification and they both were developed. Also waste inventories were elaborated which allowed development of reactor design specific disposal strategies. The main objective of work has been to establish basis for safe and efficient radioactive waste management which meets all the relevant national and international recommendations, requirements and regulations, takes advantage of best available and state-of-art technologies and offers fit-for-purpose solutions. All the work was performed to accommodate requirement based management system.


2009 ◽  
Vol 49 (3) ◽  
pp. 341-350 ◽  
Author(s):  
E. Maceika ◽  
V. Remeikis ◽  
L. Juodis ◽  
A. Gudelis ◽  
A. Plukis ◽  
...  

Author(s):  
Udo Sach ◽  
Goswin Schreck ◽  
Max Ritter ◽  
Jean-Pierre Wenger

Abstract At present, Switzerland has no final repository for radioactive wastes. Very early, the Swiss nuclear power plant operators were aware of the necessity to expand interim storage capacity for spent fuel elements and operational wastes. Already in 1991, Nordostschweizerische Kraftwerke AG (NOK) therefore started building a reactor-site interim storage facility (ZWIBEZ) at its Beznau power plant site. Moreover, as early as in 1990, “ZWILAG Zwischenlager Würenlingen AG”, a company established by the nuclear power plant operators had initiated the licensing procedure for a central interim storage facility in Switzerland. This central interim storage facility is designed for the storage of all categories of radioactive wastes and includes a conditioning facility for low-level and medium-level waste. Eleven years later, in July 2001, the first transport and storage cask loaded with irradiated fuel elements was stored in this facility. For both of the stores the concept of dry interim storage in suitable storage casks in a storage hall was chosen for the storage of irradiated fuel elements and vitrified high-level wastes from reprocessing. Cooling is established through natural circulation. Leaktightness of the casks is continuously monitored by means of a cask monitoring system. The other wastes arising from nuclear power plant operation and reprocessing are stored in a ventilated storage hall which provides shielding and — depending on the radioactive inventory — protection against external impact. The conditioned radioactive wastes, packaged in drums, are placed into open storage containers with identical base and having the same sling points as ISO containers. These containers are stacked up in free-standing stacks up to a height of 16 m. The storage concept varies, depending on the radioactive inventory; for the ZWIBEZ reactor-site interim store, a storage hall for low-level waste has been built without partition walls, whereas the store for the medium and high-level waste in the central interim store ZWILAG has been designed with partition walls dividing the hall into several storage shafts which are closed by shielding slabs. By including a hot cell into the ZWILAG facility, the purpose of this facility has been expanded beyond interim storage of radioactive waste to cover also the visual inspection of fuel elements and vitrified waste canisters as well as the reloading of fuel elements and canisters from smaller transport casks into combined transport and storage casks. Furthermore, the hot cell enables inspection and/or repair work to be performed in the cask lid area of loaded transport and storage casks, the replacement of the lid seals of storage casks and the conditioning of medium-level waste.


2011 ◽  
Vol 101 (4) ◽  
pp. 431-441 ◽  
Author(s):  
Boris Y. Oskolkov ◽  
Mikhail D. Bondarkov ◽  
Lubov I. Zinkevich ◽  
Nikolai I. Proskura ◽  
Eduardo B. Farfán ◽  
...  

Author(s):  
Iftekhar Ahmed ◽  
Hriday Dhar Joni ◽  
Hridita Nowrin Pranti

The nuclear power plant is required to supply a substantial amount of electricity for a densely populated country like Bangladesh. The government of Bangladesh has attached to a commitment to implement the Rooppur Nuclear Power Plant, and so Bangladesh will be the 33rd nuclear power-producing country after the successful construction of this plant. Bangladesh has planned to construct two power units (Rooppur-1 & Rooppur-2) with a capacity of 1200 MW, each of and is expected to go into operation in 2023. Russian Rosatom State Atomic Energy Corporation is constructing this nuclear power plant, which is the generation-3+ VVER-1200 model. But the main concern is how a third world country like Bangladesh can handle the tons of radioactive waste of RNNP. Radioactive waste i.e., a variety of solids, liquids, and gases which are produced during the generation of nuclear energy in a nuclear reactor. Depending on activity content, solid and liquid waste are disposed of in near-surface or deep geological facilities, and gaseous waste is dissolved by following some filtering process. If not properly disposed of or recycled, irradiation from radioactive waste will cause major problems for the environment. Various stages should be required for the removal of a tremendous amount of radioactive waste in a cost-effective way. This paper mainly delineates the proximate of radioactive waste management of RNNP and gives an account of (1) Radioactivity and radiation level, (2) Classification, (3) Treatment of solid, liquid and gaseous radioactive waste, (4) Reprocessing and packaging, (5) Storage and (6) Disposal.


Author(s):  
Naoko Watanabe ◽  
Ryohei Miyoshi ◽  
Tamotsu Kozaki ◽  
Shingo Tanaka ◽  
Satoshi Yanagihara

Decommissioning cost including radioactive waste management for 1100 MWe nuclear power plant (BWR) was analyzed comparing multiple scenarios. The total cost of decommissioning nuclear power plant was first estimated including the radioactive waste management cost for the standard Japanese decommissioning case with 30 years of the project duration including approximately 20 years in safe storage. It showed that the cost relating to waste management accounts for more than half of the total cost. Focusing on the radioactive waste management cost, the duration of safe storage was varied as a parameter. The timing of waste disposal was a key parameter determining the waste management cost due to the decay of radioactive nuclides resulting in the decrease in the total volume of the radioactive waste, and the change in the ratio of the waste volume in the three radioactive waste categories (intermediate-level, low-level, and extremely low-level). The total cost showed the minimum value at around 60 years of the project duration balancing the waste management cost and period dependent cost for safe storage.


Author(s):  
Tatiana Grebennikova ◽  
Abbie N Jones ◽  
Clint Alan Sharrad

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...


2021 ◽  
Vol 24 (3) ◽  
pp. 291-301
Author(s):  
Akhmad Tri Prasetyo ◽  
Muslim Muslim ◽  
Heny Suseno

The study of radioactive dispersion in the ocean should be conducted to prepare the construction of nuclear power plant (NPP) in Gosong Coast, West Kalimantan. This study estimated the distribution of 137Cs radioactive from various scenarios of radioactive waste dumping if nuclear emergency is occurred during NPP’s operation. These scenarios were distinguished based on their volume discharges of radioactive waste into the ocean, included 10 m3 (Scenario I), 50 m3 (Scenario II), and 100 m3 (Scenario III).  Model dispersions were constructed for 15 days by Delft3D-Flow module. The simulation showed that ocean current directions were not significantly different among spring and neap tide, instead the ocean current during the spring period dominantly increased rather than neap period. Ocean currents at Gosong Coast flowed parallel to the shoreline towards Singkawang Coastal Area during ebb tide. Meanwhile, during flood tide, ocean currents at Gosong Coast flowed offshore through Burung Archipelagic. The dispersed model showed the distribution of 137Cs radioactive for 15 days reaching to coastal areas of Burung Archipelagic, Singkawang, and Southern Sambas Coast. Each scenario of the disposal system did not influence the marine pollution of the West Kalimantan Sea.


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