A case study on the soil-water characteristics of the vadose zone and the migration of intermediate-level nuclides in a planned spent-fuel reprocessing plant site

2021 ◽  
Vol 284 ◽  
pp. 124743
Author(s):  
Yu Zhang ◽  
Yanjun Zhang ◽  
Xuhong Wang ◽  
Jihua Hu ◽  
Xue Zhang ◽  
...  
Keyword(s):  
Soil Water ◽  
Vadose Zone ◽  
Intermediate Level ◽  
Spent Fuel ◽  
Water Characteristics ◽  
Plant Site ◽  
Spent Fuel Reprocessing ◽  
Reprocessing Plant ◽  
Fuel Reprocessing

Transfer of radiocarbon liquid releases from the AREVA La Hague spent fuel reprocessing plant in the English Channel

2006 ◽  
Vol 90 (3) ◽  
pp. 173-196 ◽  
Author(s):  
Bruno Fiévet ◽  
Claire Voiseux ◽  
Marianne Rozet ◽  
Michel Masson ◽  
Pascal Bailly du Bois
Keyword(s):  
English Channel ◽  
Spent Fuel ◽  
Spent Fuel Reprocessing ◽  
Reprocessing Plant ◽  
Fuel Reprocessing

scholarly journals Development of New Waste Forms to Immobilize Iodine-129 Released from a Spent Fuel Reprocessing Plant

2010 ◽  
Vol 73 ◽  
pp. 158-170 ◽  
Author(s):  
Hiromi Tanabe ◽  
Tomofumi Sakuragi ◽  
Kenji Yamaguchi ◽  
Taemi Sato ◽  
Hitoshi Owada
Keyword(s):  
Radioactive Wastes ◽  
Behavior Modeling ◽  
Spent Fuel ◽  
Waste Forms ◽  
Reducing Conditions ◽  
Geological Repository ◽  
Spent Fuel Reprocessing ◽  
Immobilization Techniques ◽  
Reprocessing Plant ◽  
Fuel Reprocessing

I-129 is a very long-lived radionuclide that is released to an off-gas stream when spent fuels are dissolved at a reprocessing plant. An iodine filter can capture I-129 in the form of AgI. However, because AgI is unstable under the reducing conditions of a geological repository and I-129 has a very long half-life, I-129 can migrate to the biosphere. These characteristics make I-129 a key radionuclide for the safety assessment of a geological disposal of radioactive wastes generated from a reprocessing plant (TRU wastes). To improve disposal safety, several new waste forms have been developed to confine I-129 for a very long period in order to reduce the leaching of I-129 from radioactive wastes. These new waste forms have technical objectives of solidifying more than 95% of I-129 into the waste form and achieving a leaching rate of less than 10-5/y. Several iodine immobilization techniques have been examined. This paper presents experimental results concerning the treatment process, leaching behavior, modeling, and related elements of these immobilization techniques.

Neptunium Decontamination in a Uranium Purification Cycle of a Spent Fuel Reprocessing Plant

1983 ◽  
Vol 18 (14-15) ◽  
pp. 1685-1698 ◽  
Author(s):  
W. Ochsenfeld ◽  
G. Petrich ◽  
H. J. Schmidt ◽  
A. H. Stollenwerk ◽  
H. Wiese
Keyword(s):  
Spent Fuel ◽  
Spent Fuel Reprocessing ◽  
Reprocessing Plant ◽  
Fuel Reprocessing

A review on UREX processes for nuclear spent fuel reprocessing

2020 ◽  
Vol 358 ◽  
pp. 110410 ◽  
Author(s):  
Indu Kumari ◽  
B.V.R. Kumar ◽  
Ashok Khanna
Keyword(s):  
Spent Fuel ◽  
Spent Fuel Reprocessing ◽  
Fuel Reprocessing
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