scholarly journals Long-term storage of nuclear fuel in spent fuel casks

2019 ◽  
Author(s):  
Pavlo Kosiak ◽  
Martin Lovecky
Keyword(s):  
Nuclear Fuel ◽  
Spent Fuel ◽  
Long Term Storage ◽  
Term Storage

Sorption of Actinides in Well-Defined Oxidation States on Geologic Media

1981 ◽  
Vol 11 ◽  
Author(s):  
B. Allard ◽  
U. Olofsson ◽  
B. Torstenfelt ◽  
H. Kipatsi ◽  
K. Andersson
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Oxidation States ◽  
Spent Fuel ◽  
Long Term Storage ◽  
Term Storage ◽  
Geologic Media

The long-lived actinides and their daughter products largely dominate the biological hazards from spent nuclear fuel already from some 300 years after the discharge from the reactor and onwards . Therefore it is essential to make reliable assessments of the geochemistry of these elements in any concept for long-term storage of spent fuel or reprocessing waste, etc.

scholarly journals Recycling versus Long-Term Storage of Nuclear Fuel: Economic Factors

2013 ◽  
Vol 2013 ◽  
pp. 1-7 ◽  
Author(s):  
B. Yolanda Moratilla Soria ◽  
Maria Uris Mas ◽  
Mathilde Estadieu ◽  
Ainhoa Villar Lejarreta ◽  
David Echevarria-López
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Economic Factors ◽  
International Studies ◽  
Closed Cycle ◽  
Spent Fuel ◽  
Long Term Storage ◽  
Open Cycle ◽  
Term Storage

The objective of the present study is to compare the associated costs of long-term storage of spent nuclear fuel—open cycle strategy—with the associated cost of reprocessing and recycling strategy of spent fuel—closed cycle strategy—based on the current international studies. The analysis presents cost trends for both strategies. Also, to point out the fact that the total cost of spent nuclear fuel management (open cycle) is impossible to establish at present, while the related costs of the closed cycle are stable and known, averting uncertainties.

Preparing the Spent Nuclear Fuel for Long-Term Storage and Final Disposal by Encapsulating It Into Glass-Ceramic Waste Forms

2001 ◽  
Author(s):  
Sergey Yu. Sayenko ◽  
G. A. Kholomeyev ◽  
B. A. Shilyaev ◽  
A. V. Pilipenko ◽  
E. P. Shevyakova ◽  
...  
Keyword(s):  
Nuclear Fuel ◽  
Glass Ceramic ◽  
Spent Nuclear Fuel ◽  
Spent Fuel ◽  
Geological Disposal ◽  
Final Disposal ◽  
Ceramic Composition ◽  
Long Term Storage ◽  
Term Storage

Abstract This paper describes the research work carried out at the NSC KIPT to develop and apply a final waste form in the shape of a monolithic solid block for the containment of spent nuclear fuel. To prepare radioactive waste for long-term storage and final deep geological disposal, investigations into the development of methods of immobilizing HLW simulators in protective solid matrices are being conducted at the NSC KIPT. For RBMK spent nuclear fuel it is proposed and justified to encapsulate the spent fuel bundles into monolithic protective blocks, produced with the help of hot isostatic pressing (HIP) of powder materials. In accordance with this approach, as a material for the protective block made up of the glass-ceramic composition prepared by sintering at isostatic pressure, the powder mixture of such natural rocks as granite and clay has been chosen. Concept approach and characterization of waste form, technological operations of manufacturing and performance assessment are presented. The container with spent fuel for long-term storage and final disposal presents a three barrier protective system: ceramic fuel UO2 in cladding tube, material of the glass-ceramic block, material of the sealed metal capsule. Investigations showed that the produced glass-ceramic material is characterized by high stability of chemical and phase compositions, high resistance in water medium, low porosity (compared with the porosity of natural basalt). With the help of mathematical calculations it was shown that the absorbed dose of immobilizing material by RBMK spent fuel irradiation for 1000 years of storage in the geological disposal after 10 years of preliminary cooling will be ∼ 3.108 Gy, that is 2–3 orders of magnitude less than the values corresponding to preserving radiation resistance and functional parameters of glasses and ceramics. The average value of velocity of linear corrosion in water medium of the protective layer made up of the glass-ceramic composition determined experimentally makes up ∼ 15 mm per year. This allows to use glass-ceramic compositions effectively as an engineering barrier in the system of spent fuel geological disposal and to increase the lifetime of the waste container, in particular, up to 3000 years with the layer thickness ∼ 40 mm. The possible release of radionuclides from the waste container during its interim storage in the open air (near-surface storage) is estimated. The calculations are made by taking into account the possible increase of coefficients of radionuclide diffusion from 10−16 to 10−14 m2/c as a result of spent fuel radiation affecting the protective layer. The obtained results showed that the protective barrier (about 40 mm) at the base of the glass-ceramic composition, ensures reliable isolation from the environment against the release of radionuclides from the controlled near-surface long-term storage far up to 1000 years. The relatively limited release of radionuclides will make up about 1% for the period of more than 400 years, and 10% - in 1000 years. During this period of time, the radionuclides 90Sr and 137Cs will completely turn into stable 90Zr and 137Ba and the decay of many transuranium elements will occur. The results from laboratory scale experiments, tests and calculations carried out so far, show that the proposed glass-ceramic materials may be used as basic materials for manufacturing the monolithic protective block in which the spent fuel elements will be embedded with the aim of further long-term storage or final disposal.

Two Periods of Long-Term Storage of Thorium Spent Fuel

2001 ◽  
Author(s):  
Aleksander S. Gerasimov ◽  
Boris R. Bergelson ◽  
Tamara S. Zaritskaya
Keyword(s):  
Nuclear Fuel ◽  
Fuel Cycle ◽  
Heat Power ◽  
Spent Fuel ◽  
Decay Heat ◽  
Type Reactor ◽  
Long Term Storage ◽  
Uranium Fuel ◽  
Term Storage

Abstract Radiotoxicity and decay heat power of actinides from spent thorium-uranium nuclear fuel of VVER-1000 type reactor during 100 000 year storage are discussed. Actinide accumulation in thorium fuel cycle is much less than in uranium fuel cycle. The radiotoxicity of actinides of thorium-uranium fuel by air is 5.5 times less and radiotoxicity by water is 3.5 times less than radiotoxicity of actinides of uranium fuel. Extraction of most important nuclides for transmutation permits to reduce radiologic danger of wastes remaining in storage.

scholarly journals Decay heat power of spent nuclear fuel of power reactors with high burnup at long-term storage

2017 ◽  
Vol 153 ◽  
pp. 07035 ◽  
Author(s):  
Mikhail Ternovykh ◽  
Georgy Tikhomirov ◽  
Ivan Saldikov ◽  
Alexander Gerasimov
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Heat Power ◽  
Decay Heat ◽  
Long Term Storage ◽  
High Burnup ◽  
Term Storage

scholarly journals Modeling of decay heat removal from CONSTOR RBMK-1500 casks during long-term storage of spent nuclear fuel

Energy ◽  
2019 ◽  
Vol 170 ◽  
pp. 978-985 ◽  
Author(s):  
R. Poškas ◽  
V. Šimonis ◽  
H. Jouhara ◽  
P. Poškas
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Heat Removal ◽  
Decay Heat ◽  
Long Term Storage ◽  
Term Storage

Long-term storage of spent nuclear fuel

2015 ◽  
Vol 14 (3) ◽  
pp. 252-257 ◽  
Author(s):  
Rodney C. Ewing
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Long Term Storage ◽  
Term Storage
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