Simulation of the Processes of Gamma-Radiation Transport through Shielding Containers for Radioactive Waste

2003 ◽  
Vol 46 (10) ◽  
pp. 1062-1065 ◽  
Author(s):  
V. I. Pavlenko ◽  
R. N. Yastrebinskii ◽  
V. M. Lipkanskii
Keyword(s):  
Radioactive Waste ◽  
Gamma Radiation ◽  
Radiation Transport

Effect of Gamma Radiation on Native Endolithic Microorganisms from a Radioactive Waste Deposit Site

1999 ◽  
Vol 152 (1) ◽  
pp. 64 ◽  
Author(s):  
Beth J. Pitonzo ◽  
Penny S. Amy ◽  
Mark Rudin
Keyword(s):  
Radioactive Waste ◽  
Gamma Radiation ◽  
Waste Deposit

scholarly journals VERIFYING NUCLEAR WASTE TILE-HOLES USING GAMMA RADIATION SCANNING

2019 ◽  
Vol 8 (1) ◽  
pp. 53-62
Author(s):  
James Johnston ◽  
Shuwei Yue ◽  
Jeremy Stewart
Keyword(s):  
Radioactive Waste ◽  
Gamma Radiation ◽  
Nuclear Waste ◽  
Isotope Production ◽  
Radiation Level ◽  
Low Level ◽  
Waste Storage ◽  
Below Ground ◽  
Radiation Sensors ◽  
Radiation Profile

Nuclear waste management facilities at Chalk River Laboratories (CRL) use below-ground “tile-holes” to store solid waste from various activities such as medical isotope production. After long periods of isotopic decay, some of the waste has decayed down to low activities and can be transferred to low-level waste storage facilities. This paper presents a method to verify the radiation level of the waste inside tile-holes by performing gamma radiation scans along the depth of waste storage tile-holes. Such measurements allow for noninvasive verification of tile-hole contents and provide input to the assessment of radiological risk associated with removal of the waste. Using the radiation profile system, the radiation level of the radioactive waste may be identified based on the radiation profile. This information will support planning for possible transfer of this waste to a licensed waste storage facility designed for low-level waste, thus freeing storage space for possible tile-hole re-use for more highly radioactive waste. CRL-developed small diode-based gamma radiation sensors have been used in these radiation scans. The diode sensors were deployed into verification tubes adjacent to the tile-holes to measure the radiation profile. Over 10 tile-holes have been scanned using this technique since 2009.

scholarly journals Investigation of the Influence of Gamma Radiation on Structural Transformations in Portlandcement Stone

2021 ◽  
pp. 60-66
Author(s):  
D. Anopko ◽  
O. Honchar ◽  
M. Kochevykh ◽  
L. Kushnierova
Keyword(s):  
Radioactive Waste ◽  
Gamma Radiation ◽  
Dose Rate ◽  
Radiation Resistance ◽  
Reference Sample ◽  
Radiation Energy ◽  
Structural Transformations ◽  
The Other ◽  
Radiation Equipment ◽  
High Level

The radiation resistance of concrete under the influence of large doses of gamma radiation was investigated. To study the behavior of concrete under the influence of gamma radiation, two series of samples were taken: оne was the reference sample, and the other was exposed to gamma radiation. The temperature of the irradiated samples during testing did not exceed 40 °C, the reference temperature was also accepted to be 40 °C. The dose of gamma radiation was 109 rad. Its value corresponds to the dose that concrete can receive when it comes into contact with high-level radioactive waste from the Shelter over 300 years. Characteristics of an industrial gamma radiation equipment are: radiation energy is 1.25 MeV and dose rate is 2 Mrad/h. The use of such equipment allows reaching a dose of 109 rad in less than a month, and 108 rad - in 4-5 days. Concretes that were 28 days old and stored under normal conditions were exposed to gamma radiation.

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.

THE TOTAL MANAGEMENT OF NORM IN THE OFFSHORE PETROLEUM INDUSTRY

1998 ◽  
Vol 38 (2) ◽  
pp. 151
Author(s):  
J. Kvasnicka
Keyword(s):  
Radioactive Waste ◽  
Gamma Radiation ◽  
Radiation Protection ◽  
Waste Disposal ◽  
Petroleum Industry ◽  
Radiation Monitoring ◽  
Radioactive Waste Disposal ◽  
Radioactive Isotopes ◽  
Radiation Doses ◽  
Offshore Petroleum

Naturally Occurring Radioactive Materials (NORMs) in the offshore petroleum industry are generally associated with the formation of scale in pipes and vessels. As scale and sludge contain radioactive isotopes of radium they are in the category of Low Specific Activity (LSA) NORMs. Handling of NORMs creates issues involving occupational health and safety, environmental protection and radioactive waste management and waste disposal. Barium(Radium)Sulfate scale is highly insoluble and can create serious production problems by clogging pipes and valves.The paper discusses the external gamma radiation monitoring at the external surfaces of well and oil production pipes which assists in establishing the scale thickness patterns in pipes and in identifying the optimum location of a scale inhibitor injection point.To minimise radiation doses received by workers special NORM handling Work Procedures and Instructions supported by radiation protection training need to be developed. If facility personnel are trained in radiation protection and Work Procedures and Instructions are adopted it is possible to effectively manage personal radiation exposures below the public limit of 1 millisievert per year. Under such conditions no personal radiation monitoring during routine operations is required and the assessment of routine annual external radiation doses may be carried out through yearly external gamma radiation surveys of of fshore petroleum production facilities.The NORM waste cannot be disposed of onshore within the same disposal sites used for general non-radioactive waste. In Australia only the NORM waste generated in Western Australia can be disposed of onshore in an official low level radioactive waste disposal facility. It is important that Governments of other States and Territories address the onshore NORM waste disposal option. Regulations should also address a screening method for scrap metal contaminated by NORMs to be released for smelting.

Assessment of the Influence of the Underlying Surface Composition on the Results of Aerial Radiation Reconnaissance

ANRI ◽  
2021 ◽  
Vol 0 (1) ◽  
pp. 63-70
Author(s):  
Dmitriy Kozhevnikov ◽  
Igor' Novikov
Keyword(s):  
Gamma Radiation ◽  
Software Package ◽  
Surface Composition ◽  
Radiation Transport ◽  
Exposure Dose ◽  
Underlying Surface ◽  
Exposure Dose Rate ◽  
Specialized Software ◽  
Radiation Control ◽  
Contaminated Area

The influence of the composition of the underlying surface on the results of aerial radiation reconnaissance of contaminated areas is considered. The analysis of the probability of the presence of various compositions of the underlying surfaces in Russia. The values of the exposure dose rate over the contaminated area were calculated depending on the height and type of the underlying surface using a specialized software package for mathematical simulation of gamma radiation transport and registration processes for the design of spectrometric systems for aviation radiation control.

Novovoronezh NPP Experience in Applying the Methodology for Measurement the Activity, Radionuclide Composition of Radioactive Waste in the NZK type Containers Using the «Satellite» Software

ANRI ◽  
2021 ◽  
Vol 0 (3) ◽  
pp. 36-47
Author(s):  
Vladimir Povarov ◽  
Andrey Merem'yanin ◽  
Nickolay Stepin ◽  
Sergey Rosnovsky ◽  
Eduard Mel'nikov ◽  
...  
Keyword(s):  
Experimental Study ◽  
Radioactive Waste ◽  
Energy Distribution ◽  
Gamma Radiation ◽  
Measurement Method ◽  
Activity Measurement ◽  
Radionuclide Composition

The article analyses the results of application of the radioactive waste activity measurement method based on measuring the energy distribution of gamma radiation near the container at the Novovoronezh NPP. The proposed method is applied to homogeneous radioactive waste and provides a reduction of the characterization costs. The results of an experimental study of the method and proposals for its improvement are presented.

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