All-Union Conference on Ionizing-Radiation Protection of Nuclear Engineering Facilities

Mashkovich, V. P.

doi:10.1007/bf01120365

Cited by 6 publications

(9 citation statements)

References 0 publications

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“…As for SCD, paragraph 5.3.1 of the Guidelines 2.6.1.016-99 [7] says: 'the monitored surface area is uniformly divided by a grid into rectangular cells whose dimensions are equal to the dimensions of the input window of the detector of the device used'. Therefore, for the SCD support is not higher than 100 cm 2 . In some cases, the surface contamination at the point of monitoring is determined as a SCD averaged by the five cells (the vertices of the square and the geometric centre), measured at the area of 1 m 2 (the envelope method).…”

Section: Scd and Ader As Spatially Distributed Datamentioning

confidence: 93%

“…In the case considered in this article SCD measurement means mainly the measurement in a monodirectional radiation field of beta particles penetrating through the detector window, and the detector should be placed almost directly against the contaminated surface. If the beta source is buried beneath the surface (which occurs over time due to meteorological and diffusion processes, as well as because of economic activity), then it may not contribute fully, or even at all, to the SCD 11 [2].…”

Section: Introductionmentioning

confidence: 99%

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The development and application of a method for assessing radionuclide surface contamination density based on measurements of ambient dose equivalent rate

Chizhov

Sneve

et al. 2019

J. Radiol. Prot.

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This article presents a method for assessing the radionuclide surface contamination density (SCD) on open sites and in premises of a radiation hazardous facility based on measurements of the ambient dose equivalent rate (ADER). The method is intended for use at the initial stage of the assessment of the radiation environment at facilities. The assessed SCD at a given location on the surface can differ from the directly measured SCD at that location, since sources located on the surface and distributed by the depth contribute to the ADER value. The method makes it possible to estimate SCD with reasonable accuracy without increasing the number of measurements, and thus avoid additional occupational exposure and the use of additional resources. SCD and ADER as spatial variables have different support of measurement data. For ADER, measured at a height of 1 m, the support of measurement data can be taken to be a circle in the centre of which a gamma-ray detector is located, with a radius of several tens of meters. In contrast, SCD has the support of measurement data, close to the overall dimensions of the beta detector (100 cm2). To solve the problem of SCD calculation on the basis of ADER measurements, the method of conversion coefficients (MCC) is usually applied, based on the use of conversion factors; however, this method provides an adequate estimate only under conditions of an SCD with low gradient over the surface. The method proposed in this article is applicable for an arbitrary distribution of SCD, and designed to deal with heterogeneous contamination patterns. The developed method is based on the numerical solution of the Fredholm equation of the first kind. The measurement data always contain an error, therefore, the task of the SCD calculation is an ill-posed problem, and the Tikhonov regularisation method (ridge regression) was used to solve it. The article presents the method developed and examples of use. Validation of the method was performed using 38 measurements of the radioactive contamination from 137Cs in soil. It is shown that the method proposed in the article demonstrates a significant superiority in comparison with the MCC method, because it allows more accurate localisation of areas contaminated with radionuclides and is applicable for an arbitrary distribution of SCD.

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Section: Scd and Ader As Spatially Distributed Datamentioning

confidence: 93%

Section: Introductionmentioning

confidence: 99%

The development and application of a method for assessing radionuclide surface contamination density based on measurements of ambient dose equivalent rate

Chizhov

Sneve

et al. 2019

J. Radiol. Prot.

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“…The main drawbacks of RP structures that have been used so far in nuclear power plants and radioactive waste deposits are their significant mass and size [18,19]. They make it difficult or even impossible, in many cases, to use known RP structures, for example, in spacecraft, airplanes, mobile power plants, and so on.…”

Section: Section For Production Of Laminated Compositesmentioning

confidence: 99%

Organization of Experimental Technological Complex for Serial Manufacturing and Testing of Products and Semi-Products Made of Diamond-Like and Laminated Composites for Leading Branches of Mechanical Engineering

Bilous¹

2014

Sci. innov.

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An experimental technological complex has been created. It consists of the sections for coating with diamond-like nanostructured composites; for manufacturing the radio-protective and other types of laminated metal composites; and for testing the radio-protective characteristics of materials. The technological equipment and the tester of radio-protective properties have been upgraded. On the basis of the developed experimental methods the batch of diamond-like coated ring seals of large diameter and samples of Al-Pb laminated composites have been made. The radio-protective effectiveness of composites has been experimentally established to be 30-40 % higher than that of aluminum. K e y w o r d s: vacuum-arc and vacuum rolling methods, accelerator and radioisotope techniques, diamond-like coating, and laminated composites.

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“…One of these properties is the so-called buildup factor which can be calculated using advanced engineering methods by the calculation of the scattered radiations. The information available in the literature for photon buildup factors for various protective materials [2]- [4] is limited especially for a point isotropic monoenergetic photon source in the energy range from 10 to 50 MeV.…”

Section: Introductionmentioning

confidence: 99%

Exposure Buildup Factors in Concrete, Lead for Point Isotropic and Unidirectional Photon Sources in the Energy Range from 10 to 50 MeV

Alhagaish,

Aqili

2024

Latvian Journal of Physics and Technical Sciences

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The exposure buildup factors in concrete and lead for a point isotropic and flat unidirectional photon source in the energy range from 10 to 50 MeV were determined using Monte Carlo simulation “FLUKA” software. The exposure buildup factors were also obtained for different material thickness up to 40 mpf. The calculations were done in a barrier geometry where the contributions of all photon-matter interactions were taken into account in the performed calculations. Amendments for the barrier-geometry effect for both materials under study were deduced. The results showed that barrier-effect amendments were independent of the material thickness, material type, and energy of the photon source

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All-Union Conference on Ionizing-Radiation Protection of Nuclear Engineering Facilities

Cited by 6 publications

References 0 publications

The development and application of a method for assessing radionuclide surface contamination density based on measurements of ambient dose equivalent rate

The development and application of a method for assessing radionuclide surface contamination density based on measurements of ambient dose equivalent rate

Organization of Experimental Technological Complex for Serial Manufacturing and Testing of Products and Semi-Products Made of Diamond-Like and Laminated Composites for Leading Branches of Mechanical Engineering

Exposure Buildup Factors in Concrete, Lead for Point Isotropic and Unidirectional Photon Sources in the Energy Range from 10 to 50 MeV

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