Results 271 to 280 of about 481,445 (303)
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Radiochemistry, 2011
Samples of fuel-containing materials taken inside the CNPP Fourth Unit were analyzed by γ- and α-ray spectrometry. The isotope ratios for Cs, Eu, Pu, Am, and Cm were measured, and the fuel burn-up in the samples was determined. Inconsistencies in theoretical estimations on the production of all the radionuclides over 241Am were revealed.
V. A. Zheltonozhskii +5 more
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Samples of fuel-containing materials taken inside the CNPP Fourth Unit were analyzed by γ- and α-ray spectrometry. The isotope ratios for Cs, Eu, Pu, Am, and Cm were measured, and the fuel burn-up in the samples was determined. Inconsistencies in theoretical estimations on the production of all the radionuclides over 241Am were revealed.
V. A. Zheltonozhskii +5 more
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Radiochemistry, 2011
The neutron incident that happened in June 1990 in the 4th Unit of the Chernobyl NPP, destroyed in the accident, at the boundary of rooms 304/3 and 305/2 is analyzed. One of possible scenarios of the incident, consistently accounting for the dynamics and self-extinguishment of the detected neutron anomaly, is suggested.
E. D. Vysotskii +4 more
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The neutron incident that happened in June 1990 in the 4th Unit of the Chernobyl NPP, destroyed in the accident, at the boundary of rooms 304/3 and 305/2 is analyzed. One of possible scenarios of the incident, consistently accounting for the dynamics and self-extinguishment of the detected neutron anomaly, is suggested.
E. D. Vysotskii +4 more
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Ultrasonic Characterization of Candidate Nuclear used Fuel Container Weld Materials
1987Ultrasonic inspection of weld cylinders of candidate nuclear used fuel container materials (copper, titanium grades 2 and 12, stainless steel 316, Inconel 625, Hastelloy C-276) using immersion longitudinal waves showed that titanium grades 2 and 12 exhibited essentially isotropic behaviour (little beam skewing).
M. D. C. Moles, J. Imada, M. P. Dolbey
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Processes of vertical diffusion of radionuclides in a layer of a lava-like fuel-containing material
Journal of Mathematical Sciences, 2012Using a known model for the quantitative description of diffusion of radioactive impurities in fuel-containing materials and taking into account processes of electrolytic dissociation and electrodiffusion (in the case of charged impurities) in interrelation with thermal and electromagnetic processes, we investigate the vertical diffusion of particles ...
O. R. Hachkevych +3 more
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ECS Meeting Abstracts, 2020
The used fuel container is a key barrier to isolate and contain used nuclear fuel in a deep geological repository (DGR). We are probing the possibility that one container failure mode could arise from the presence of hydrogen that could lead to coating delamination at the interface of copper and steel.
Hadis Hayatdavoudi, Jamie Noel
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The used fuel container is a key barrier to isolate and contain used nuclear fuel in a deep geological repository (DGR). We are probing the possibility that one container failure mode could arise from the presence of hydrogen that could lead to coating delamination at the interface of copper and steel.
Hadis Hayatdavoudi, Jamie Noel
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Radiochemistry, 2014
During 2011–2013, the α-activity of dust that was accumulated on the sample surface of lava-like fuel-containing materials in room 304/3 of the Shelter Object of Chernobyl NPP over a period of 1–284 days was measured. The α-activity of the dust collected during the 823 days was 495.5 Bq, or 2.15 kBq m−2 per year, with the annual increment exceeding 3%.
V. P. Badovskii +4 more
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During 2011–2013, the α-activity of dust that was accumulated on the sample surface of lava-like fuel-containing materials in room 304/3 of the Shelter Object of Chernobyl NPP over a period of 1–284 days was measured. The α-activity of the dust collected during the 823 days was 495.5 Bq, or 2.15 kBq m−2 per year, with the annual increment exceeding 3%.
V. P. Badovskii +4 more
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Engineering for Rural Development
Nuclear power plants and research purposed reactors produce spent nuclear fuel, which leads to a need for safe spent fuel management and radiation protection. Traditionally, concrete with the addition of different aggregates has been the primary material for shielding against radiation and is used also for transport and storage of radioactive waste ...
Iryna Romanenko +5 more
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Nuclear power plants and research purposed reactors produce spent nuclear fuel, which leads to a need for safe spent fuel management and radiation protection. Traditionally, concrete with the addition of different aggregates has been the primary material for shielding against radiation and is used also for transport and storage of radioactive waste ...
Iryna Romanenko +5 more
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Atomic Energy, 2002
A substantiation is given for the choice of threshold values of the neutron flux density (threshold-1 – “Attention” and threshold-2 – “Danger”), and formulas are derived for calculating these values for systems which are being designed and are currently in operation for monitoring the state of fuel-containing materials in the object “Cover” at the ...
V. V. Avgustov +4 more
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A substantiation is given for the choice of threshold values of the neutron flux density (threshold-1 – “Attention” and threshold-2 – “Danger”), and formulas are derived for calculating these values for systems which are being designed and are currently in operation for monitoring the state of fuel-containing materials in the object “Cover” at the ...
V. V. Avgustov +4 more
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Radiochemistry, 2014
The impact of lava-like fuel-containing materials (LFCMs) of the Shelter object (SO) of the Chernobyl NPP on the environment components is evaluated. The evaluation is based on modern data on the surface area and dust-generating ability of SO LFCMs.
V. A. Krasnov +3 more
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The impact of lava-like fuel-containing materials (LFCMs) of the Shelter object (SO) of the Chernobyl NPP on the environment components is evaluated. The evaluation is based on modern data on the surface area and dust-generating ability of SO LFCMs.
V. A. Krasnov +3 more
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Forecasting changes in the neutron-physical characteristics of fuel-containing materials
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Borysenko, V.I. +2 more
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