scholarly journals EFFICIENCY OF VARIOUS MATERIALS APPLICATION FOR RADIATION SHIELDING AT TRANSPORTATION AND STORAGE OF SPENT NUCLEAR FUEL BY DRY METHOD

2020 ◽  
pp. 64-70
Author(s):  
V.G. Rudychev ◽  
N.A. Azarenkov ◽  
I.O. Girka ◽  
Y.V. Rudychev
Keyword(s):  
Monte Carlo ◽  
Monte Carlo Method ◽  
Dose Rate ◽  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Radiation Shielding ◽  
Γ Radiation ◽  
The Monte Carlo Method ◽  
Radiation Shields ◽  
And Storage

A model of the transport container intended for transportation of spent nuclear fuel (SFN) is studied. The passage of γ-quanta from the major long-lived isotopes is examined. The radiation shields made of iron, lead and depleted uranium, which are equivalent in mass to the thickness of iron of 15 to 35 cm is considered. The calculations are carried out using the Monte Carlo method (in MCNP and PHITS packages). The change in the characteristics of γ-radiation beyond the shields, made of different materials and with different thicknesses, is determined. For SNF from WWER-1000 with the thicknesses up to ~ 21 cm, the shield made of lead and uranium is shown to be more effective. If the thickness of the shield exceeds ~ 21 cm, then the shield made of iron is more effective. Increasing the thickness of the shields above 25 cm is shown to be inefficient, since the shields mass increases but the dose rate decreases slightly in this case.

scholarly journals Environmental dose rate assessment of ITER using the Monte Carlo method

2014 ◽  
Vol 29 (1) ◽  
pp. 34-39
Author(s):  
Alireza Karimian ◽  
Amir Beheshti ◽  
Mohammadreza Abdi ◽  
Iraj Jabbari
Keyword(s):  
Monte Carlo ◽  
Monte Carlo Method ◽  
Dose Rate ◽  
Equivalent Dose ◽  
Photon Radiation ◽  
Normal Operation ◽  
Whole Body ◽  
Dose Rates ◽  
The Monte Carlo Method ◽  
Radiosensitive Organs

Exposure to radiation is one of the main sources of risk to staff employed in reactor facilities. The staff of a tokamak is exposed to a wide range of neutrons and photons around the tokamak hall. The International Thermonuclear Experimental Reactor (ITER) is a nuclear fusion engineering project and the most advanced experimental tokamak in the world. From the radiobiological point of view, ITER dose rates assessment is particularly important. The aim of this study is the assessment of the amount of radiation in ITER during its normal operation in a radial direction from the plasma chamber to the tokamak hall. To achieve this goal, the ITER system and its components were simulated by the Monte Carlo method using the MCNPX 2.6.0 code. Furthermore, the equivalent dose rates of some radiosensitive organs of the human body were calculated by using the medical internal radiation dose phantom. Our study is based on the deuterium-tritium plasma burning by 14.1 MeV neutron production and also photon radiation due to neutron activation. As our results show, the total equivalent dose rate on the outside of the bioshield wall of the tokamak hall is about 1 mSv per year, which is less than the annual occupational dose rate limit during the normal operation of ITER. Also, equivalent dose rates of radiosensitive organs have shown that the maximum dose rate belongs to the kidney. The data may help calculate how long the staff can stay in such an environment, before the equivalent dose rates reach the whole-body dose limits.

scholarly journals THE EFFICIENCY OF RADIATION SHIELDING MADE FROM MATERIALS WITH HIGH ATOMIC NUMBER AND LOW MASS DENSITY

2021 ◽  
pp. 74-79
Author(s):  
V.G. Rudychev ◽  
M.O. Azarenkov ◽  
I.O. Girka ◽  
Y.V. Rudychev
Keyword(s):  
Monte Carlo ◽  
Atomic Number ◽  
Spent Nuclear Fuel ◽  
Mass Density ◽  
Radiation Shielding ◽  
High Atomic Number ◽  
The Monte Carlo Method ◽  
Low Mass ◽  
High Burnup ◽  
Method Show

The radiation shielding from γ-quanta of the existing transport containers (TC) for transportation of spent nuclear fuel (SNF) is made of steel or steel plus Pb 25…30 cm thick and weighting ~ 60…80 t. The application of materials with high atomic number, dispersed (solids grinded to a powdery state) to the densities in the range 4 < ρ < 8 g/cm3, is investigated. Simulations based on the Monte Carlo method show that at the densities of dispersed depleted U larger than 5 g/cm3 and shielding thicknesses of more than 30 cm, the absorption of γ-quanta of SNF is greater than that of the shielding made of steel of the same thickness. The application of such materials, while the weight characteristics of the shields are not exceeded, provides radiation shielding for SNF with the high burnup rate and the smaller cooling time or larger amount of the transported SNF.

UGR CALCULATION BASED ON THE LUMINANCE SPATIAL-ANGULAR DISTRIBUTION

2020 ◽  
Vol 2020 (4) ◽  
pp. 25-32
Author(s):  
Viktor Zheltov ◽  
Viktor Chembaev
Keyword(s):  
Monte Carlo ◽  
Angular Distribution ◽  
Monte Carlo Method ◽  
Visual Task ◽  
New Method ◽  
Lighting System ◽  
Preliminary Assessment ◽  
System A ◽  
The Monte Carlo Method

The article has considered the calculation of the unified glare rating (UGR) based on the luminance spatial-angular distribution (LSAD). The method of local estimations of the Monte Carlo method is proposed as a method for modeling LSAD. On the basis of LSAD, it becomes possible to evaluate the quality of lighting by many criteria, including the generally accepted UGR. UGR allows preliminary assessment of the level of comfort for performing a visual task in a lighting system. A new method of "pixel-by-pixel" calculation of UGR based on LSAD is proposed.

PSHA software review based on the Monte Carlo method

2020 ◽  
pp. 14-24
Author(s):  
V.A. Mironov ◽  
S.A. Peretokin ◽  
K.V. Simonov
Keyword(s):  
Monte Carlo ◽  
Monte Carlo Method ◽  
Seismic Hazard ◽  
Hazard Analysis ◽  
Software Review ◽  
Seismic Hazard Analysis ◽  
Probabilistic Seismic Hazard ◽  
Test Calculation ◽  
Seismic Surveys ◽  
The Monte Carlo Method

The article is a continuation of the software research to perform probabilistic seismic hazard analysis (PSHA) as one of the main stages in engineering seismic surveys. The article provides an overview of modern software for PSHA based on the Monte Carlo method, describes in detail the work of foreign programs OpenQuake Engine and EqHaz. A test calculation of seismic hazard was carried out to compare the functionality of domestic and foreign software.

Application of the Monte Carlo Method for the Prediction of Behavior of Peptides

2019 ◽  
Vol 20 (12) ◽  
pp. 1151-1157 ◽  
Author(s):  
Alla P. Toropova ◽  
Andrey A. Toropov
Keyword(s):  
Monte Carlo ◽  
Monte Carlo Method ◽  
Natural Sciences ◽  
Monte Carlo Technique ◽  
Quantitative Structure ◽  
Structure Property ◽  
The Monte Carlo Method ◽  
Modern Natural

Prediction of physicochemical and biochemical behavior of peptides is an important and attractive task of the modern natural sciences, since these substances have a key role in life processes. The Monte Carlo technique is a possible way to solve the above task. The Monte Carlo method is a tool with different applications relative to the study of peptides: (i) analysis of the 3D configurations (conformers); (ii) establishment of quantitative structure – property / activity relationships (QSPRs/QSARs); and (iii) development of databases on the biopolymers. Current ideas related to application of the Monte Carlo technique for studying peptides and biopolymers have been discussed in this review.

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