Results 11 to 20 of about 45,538 (258)

The study of sorption of caesium radionuclides by "t-55" ferrocyanide sorbent from various types of liquid radioactive wastes [PDF]

open access: yes, 2012
The sorption of caesium by T-55 sorbent from different types of liquid radioactive wastes is studied. It is shown that the sorbent can be used for extraction of caesium from high level acidic and saline solutions and also for decontamination of caesium ...
Bykov, A. A.   +2 more
core   +1 more source

An experimental methodology to assess the impact of desaturation on gas diffusion in clay based materials [PDF]

open access: yesE3S Web of Conferences, 2023
The transport of gas in clay-based materials is dominated by diffusion. SCK CEN has studied and recorded an extensive data set of diffusion coefficients of gases in various saturated clays (Boom Clay, Opalinus Clay, Callovo-Oxfordian claystone and ...
Gowrishankar Aadithya   +4 more
doaj   +1 more source

Management of Radioactive Waste From Operation of Nuclear Power Plant -Perspective for Indonesian Program- [PDF]

open access: yes, 2010
MANAGEMENT OF RADIOACTIVE WASTE FROM OPERATION OF NUCLEAR POWER PLANT -PERSPECTIVE FOR INDONESIAN PROGRAM-. Nuclear power is the only energy industry which takes full responsibility for all its wastes, and costs this into the product.
Wisnubroto, D. S. (Djarot)
core   +2 more sources

Investigation of the Source of 238U, 232Th and 40K Radiation of in the Neyshabour Turquoise Mine and its Environmental Impacts

open access: yesJournal of Economic Geology, 2021
Introduction The Neyshabour Turquoise Mine is located at 55 km North West of Neyshabour in latitude of E58◦, 23ꞌꞌ and longitude of N36◦, 23ꞌꞌ. This area is situated at the Cenozoic continental magmatic arc in the north of Sabzevar ophiolite sequence and
Alireza Mazloumi Bajestani, Akram Fahim
doaj   +1 more source

Lanthanide (Ce, Nd, Eu) environments and leaching behavior in borosilicate glasses

open access: yesScientific Reports, 2021
Borosilicate glasses will be used to stabilize the high-level radioactive wastes for disposal in a geological repository. Understanding the effects of actinide addition to a borosilicate glass matrix is of great importance in view of waste immobilization.
M. Fabian   +4 more
doaj   +1 more source

Production and Supply of 252Cf, 238Pu and 237Np

open access: yesJournal of Isotopes, 2021
252Cf, 238Pu and 237Np are important radioisotopes in deep space exploration and nuclear electric power generation. These radionuclides have been mainly imported from overseas, and their supply chains are limited.
LUO Feng
doaj   +1 more source

Effects of Thermal Shock on the Microstructures and Mechanical Properties Evolution of 310S Welded Joints at 1100 °C

open access: yesMetals, 2022
In order to reveal the effects of the glass solidification bottling process of high-level liquid radioactive wastes on the welded joints of containers, the microstructure evolution and mechanical properties of 310S stainless steel welded joints were ...
Yunlu Jiang   +3 more
doaj   +1 more source

Study of cesium sorption by a Brazilian bentonite

open access: yesBrazilian Journal of Radiation Sciences, 2021
Engineered and natural barriers compose the disposal system of near surface repository to store low and intermediate level radioactive wastes. Waterproofing barriers are constituted of clays, such as the bentonite, in order to avoid or to limit the ...
Daisy Mary Marchezini dos Santos   +1 more
doaj   +1 more source

Safety Aspects in Radioactive Waste Management [PDF]

open access: yesActa Montanistica Slovaca, 2007
In recent years, within the framework of national as well as international programmes, notable advances and considerable experience have been reached, particularly in minimising of the production of radioactive wastes, conditioning and disposal of short ...
Peter W. Brennecke
doaj  

Evolution of swelling pressure properties of bentonite-sand-graphite buffer materials under action of temperature and salt/alkali

open access: yesYantu gongcheng xuebao, 2023
The buffer materials are the last engineering barrier for the repository of high-level radioactive wastes. It is necessary to have a deep understanding of the swelling characteristics of unsaturated buffer materials under the action of temperature and ...
LIU Xiaoyan 1, 3, 4, LIU Lulu 2, 3, 4, CAI Guojun 3, 4, LIU Songyu 4
doaj   +1 more source

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