scholarly journals Polymeric seal degradation in nuclear power plants: Effect of gamma radiation on sealing properties

2016 ◽  
Vol 134 (12) ◽  
Author(s):  
Christopher P. Porter ◽  
Ruth Edge ◽  
Mark D. Ogden
Keyword(s):  
Gamma Radiation ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants

The Effect of Elevated Temperatures and Nuclear Radiation on the Properties of Biological Shielding Concrete

2016 ◽  
Vol 677 ◽  
pp. 8-16 ◽  
Author(s):  
Jaroslava Koťátková ◽  
Jan Zatloukal ◽  
Pavel Reiterman ◽  
Jan Patera ◽  
Zbyněk Hlaváč ◽  
...  
Keyword(s):  
Gamma Radiation ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Elevated Temperatures ◽  
Nuclear Radiation ◽  
Containment Vessel ◽  
Negative Impacts

The paper reviews the so far known information about the properties of biological shielding concrete used in the containment vessel of nuclear power plants (NPP) and its behaviour when exposed to radiation. The damage of concrete caused by neutron and gamma radiation as well as by the accompanying generation of heat is described. However, there is not enough data for the proper evaluation of the negative impacts and further research is needed.

scholarly journals Investigation of the characteristics of the container for storage of radioactive waste of nuclear power plants with uranium-graphite reactors

2018 ◽  
Vol 245 ◽  
pp. 07016
Author(s):  
Aleksey Ivshin ◽  
Alexandr Kalyutik ◽  
Anatolii Blagoveshchenskii
Keyword(s):  
Radioactive Waste ◽  
Gamma Radiation ◽  
Energy Range ◽  
Attenuation Coefficient ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Radiation Safety ◽  
Radiation Characteristic ◽  
Calculation Error

The article presents the results of the study of neutron-physical characteristics of the container for storage of radioactive waste of nuclear power plants with uranium-graphite reactors. The interaction of gamma quanta (in the energy range from 0.1 to 2 MeV) with the structural materials of the container is simulated. The numerical values of the parameters determining the radiation characteristic of the container with the estimation of the calculation error are obtained. The following main characteristics of the container are determined: the attenuation coefficient of the equivalent dose, the numerical factor of gamma radiation accumulation. These characteristics can be used to justify the radiation safety of the container, in particular when selecting protection materials, as well as when building additional heterogeneous protection barriers.

scholarly journals A FTIR/chemometrics approach to characterize the gamma radiation effects on iodine/epoxy-paint interactions in Nuclear Power Plants

2017 ◽  
Vol 960 ◽  
pp. 53-62 ◽  
Author(s):  
Juliette Colombani ◽  
Elodie Chauvet ◽  
Sandrine Amat ◽  
Nathalie Dupuy ◽  
Didier Gigmes
Keyword(s):  
Gamma Radiation ◽  
Nuclear Power ◽  
Power Plants ◽  
Radiation Effects ◽  
Nuclear Power Plants ◽  
Epoxy Paint
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