Radiation effects on the electrical activation processes in InSb under influence of nuclear reactor neutrons

2001 ◽  
Vol 307 (1-4) ◽  
pp. 258-264 ◽  
Author(s):  
N.G Kolin ◽  
D.I Merkurisov ◽  
S.P Solov’ev
2021 ◽  
Vol 1024 ◽  
pp. 127-133
Author(s):  
Matteo Ferrari ◽  
Aldo Zenoni ◽  
Yong Joong Lee ◽  
Alberto Andrighetto

Lubricants and O-rings are necessarily used for the construction of many accelerator-driven facilities as spallation sources or facilities for the production of radioactive isotopes. During operation, such component will absorb high doses of mixed neutron and gamma radiation, that can degrade their mechanical and structural properties. Experimental radiation damage tests of these components are mandatory for the construction of the facility. Methodologies for irradiation in nuclear reactor mixed fields and post-irradiation examination of lubricating oils, greases and O-rings were developed and are here presented. Samples were characterized with standard mechanical and physical-chemical tests. Parametric studies on the dose rate effects have been performed on O-rings. A case studies for a specific O-ring application in a gate valve has been developed. Some of the tested samples showed a dramatic change of their properties with dose, while others remain stable. Results were collected on nine commercial greases, on one oil and on four commercial elastomeric O-rings. The most radiation resistant among the selected products are now considered for application in facilities under construction. The main mechanisms of neutron and gamma radiation damage on these polymers were investigated at the mechanical and structural level.


2020 ◽  
Vol 225 ◽  
pp. 04034
Author(s):  
Klemen Ambrožič ◽  
Klaudia Malik ◽  
Barkara Obryk ◽  
Luka Snoj

A well characterized radiation field inside a research nuclear reactor irradiation facilities enables precise qualification of radiation effects to the irradiated samples such as nuclear heating or changes in their electrical or material properties. To support the increased utilization of the JSI TRIGA reactor irradiation facilities in the past few years mainly on account of testing novel detector designs, electronic components and material samples, we are working on increasing the neutron and gamma field characterization accuracy using various modeling and measurement techniques. In this paper we present the dose field measurements using thermo-luminescent detectors (TLD’s) with different sensitivities neutron and gamma sensitivities, along with multiple ionization and fission chamber. Experiment was performed in several steps from reactor start-up, steady operation and a rapid shutdown, during which the ionization and fission chamber signals were acquires continuously, while the TLD’s were being irradiated at different stages during reactor operation and after shutdown, to also capture response to delayed neutron and gamma field. The results presented in this paper serve for validation of JSI designed JSIR2S code for delayed radiation field determination, initial results of its application on the JSI TRIGA TLD measurements will also be presented.


1984 ◽  
Vol 6 (2) ◽  
pp. 339-367 ◽  
Author(s):  
P Rodriguez ◽  
R Krishnan ◽  
C V Sundaram

1981 ◽  
Vol 11 ◽  
Author(s):  
Yehuda Eyal

It has been proposed recently that high-level radioactive wastes from spent nuclear reactor fuels be converted into a crystalline phosphate form prior to their disposal in geological repositories. This approach is based on the known durability in nature of the mineral monazite, (Ce,La)P0, which contains appreciable concentrations of thorium and uranium. Of significance is the demonstrated resistance of monazite to excessive metamictization, in spite of the fact that the mineral has been subjected since its formation to radiation from the radioactive disintegration of U, Th and their many intermediate decay products. Nevertheless, radiation effects on the leaching behavior of the material in possible groundwater environments must be studied in the development and testing of monazite-like phases for the long-term disposal of fission product and actinide wastes.


2004 ◽  
Vol 15 (8) ◽  
pp. 1506-1511 ◽  
Author(s):  
A Fernandez Fernandez ◽  
A Gusarov ◽  
B Brichard ◽  
M Decréton ◽  
F Berghmans ◽  
...  

1983 ◽  
Vol 2 (1) ◽  
pp. 41-47
Author(s):  
J. K. Basson

The impending operation of South Africa’s first nuclear power station, Koeberg, necessitates a thorough analysis of nuclear safety under local conditions. More is known, worldwide, about radiation effects than about any other health hazard, and international norms have already been accepted since 1928. The widespread use of X-rays and radio-isotopes, the extraction and processing of uranium, visits by nuclear-powered ships and, especially, the nuclear-reactor operation in South Africa. Consequently, the pre-operational investigations of Koeberg could be completed thoroughly, with full confidence in its safe commissioning.


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