Speed-up of cross-section collapsing with weight-window for subcritical burnup calculation

2009 ◽  
Vol 84 (7-11) ◽  
pp. 1281-1284 ◽  
Author(s):  
Masayuki Matsunaka ◽  
Masayuki Ohta ◽  
Keitaro Kondo ◽  
Hiroyuki Miyamaru ◽  
Isao Murata
Keyword(s):  
Cross Section ◽  
Weight Window ◽  
Speed Up ◽  
Burnup Calculation

scholarly journals Study on mechanical properties of a new type of prefabricated GRC mold shell

2019 ◽  
Vol 136 ◽  
pp. 02030
Author(s):  
Chen Dong ◽  
Chen Ming ◽  
Cai Ouyang ◽  
Li Pengkun
Keyword(s):  
Mechanical Properties ◽  
Production Process ◽  
Cross Section ◽  
Stress System ◽  
Research Results ◽  
Floor Space ◽  
Section Size ◽  
Speed Up ◽  
New Type ◽  
Prefabricated Building

The GRC formwork structural column adopts the factory-based vertical prefabrication production process, which can reduce the floor space, reduce the formwork loss, speed up the construction progress, promote the full decoration of the prefabricated building, and improve the efficiency of the assembly construction. major. In order to optimize the production process of prefabricated GRC formwork column, the overall stress system of GRC formwork structure is analyzed in the concrete pouring process, and the thickness of GRC formwork, the number of steel hoops and the GRC mode are considered. The influence of the shell cross-section size on the mechanical properties. The research results can provide reference for the optimization and design of prefabricated GRC formwork column production process.

Cross Section and Fission Yields Induced Uncertainty in the Vver-440 Burnup Calculation

2021 ◽  
Author(s):  
Branislav Vrban ◽  
Stefan Cerba ◽  
Jakub Luley ◽  
Filip Osuský ◽  
Vladimir Necas
Keyword(s):  
Cross Section ◽  
Neutron Cross Section ◽  
Nuclear Data ◽  
Reactor Operation ◽  
Precise Estimation ◽  
Stochastic Techniques ◽  
Core Characteristics ◽  
Fission Yields ◽  
Operational Data ◽  
Burnup Calculation

Abstract The properties of nuclear fuel depend on the actual isotopic composition which develops during a reactor operation. In practice, the prediction accuracy of burnup calculations serves as the basis for the future precise estimation of a core lifetime and other safety-based core characteristics. The present study quantifies nuclear data induced uncertainties of nuclide concentrations and multiplication factors in VVER-440 fuel depletion analysis. The well-known SCALE system and the TRITON sequence are used with the NEWT deterministic solver in the SAMPLER module that implements stochastic techniques to assess the uncertainty in computed results. The propagation of uncertainties in neutron cross section and fission yields is studied through the depletion calculation of 2D heterogeneous VVER-440 fuel assembly with an average enrichment of 4.87 wt % of 235U and six gadolinium rods with 3.35 % of Gd2O3. In the paper, fixed nominal depletion conditions are based on the real operational data of the Slovak NPP Bohunice unit 4 during cycle 30. In total 250 cases with uncertain parameters are computed and the results are evaluated by an auxiliary tool.

Research on Coupling Scheme of Monte Carlo Burnup Calculation in RMC

2018 ◽  
Author(s):  
Wanlin Li ◽  
Kan Wang ◽  
Ganglin Yu ◽  
Yaodong Li
Keyword(s):  
Monte Carlo ◽  
Neutron Flux ◽  
Cross Section ◽  
Neutron Transport ◽  
Effective Cross Section ◽  
High Order ◽  
Step Method ◽  
Step Approximation ◽  
Predictor Corrector ◽  
Burnup Calculation

Monte Carlo (MC) burnup calculation method, implemented through coupling neutron transport and point depletion solvers, is widely used in design and analysis of nuclear reactor. Burnup calculation is generally solved by dividing reactor lifetime into steps and modeling geometry into numbers of burnup areas where neutron flux and one group effective cross sections are treated as constant during each burnup step. Such constant approximation for neutron flux and effective cross section will lead to obvious error unless using fairly short step. To yield accuracy and efficiency improvement, coupling schemes have been researched in series of MC codes. In this study, four coupling schemes, beginning of step approximation, predictor-corrector methods by correcting nuclide density and flux-cross section as well as high order predictor-corrector with sub-step method were researched and implemented in RMC. Verification and comparison were performed by adopting assembly problem from VERA international benchmark. Results illustrate that high order coupled with sub-step method is with notable accuracy compared to beginning of step approximation and traditional predictor-corrector, especially for calculation in which step length is fairly long.

scholarly journals MPACT VERIFICATION WITH MAGNOX REACTOR NEUTRONICS PROGRESSION PROBLEMS

2021 ◽  
Vol 247 ◽  
pp. 10031
Author(s):  
Nicholas P. Luciano ◽  
Brian J. Ade ◽  
Kang Seog Kim ◽  
Andrew J. Conant
Keyword(s):  
Cross Section ◽  
Neutron Transport ◽  
Three Dimensional ◽  
Light Water Reactors ◽  
Pressurized Water Reactor ◽  
Reactor Physics ◽  
Pressurized Water ◽  
Water Reactors ◽  
Improved Performance ◽  
Burnup Calculation

MPACT is a state-of-the-art core simulator designed to perform high-fidelity analysis using whole-core, three-dimensional, pin-resolved neutron transport calculations on modern parallel computing hardware. MPACT was originally developed to model light water reactors, and its capabilities are being extended to simulate gas-cooled, graphite-moderated cores such as Magnox reactors. To verify MPACT’s performance in this new application, the code is being formally benchmarked using representative problems. Progression problems are a series of example models that increase in complexity designed to test a code’s performance. The progression problems include both beginning-of-cycle and depletion calculations. Reference solutions for each progression problem have been generated using Serpent 2, a continuous-energy Monte Carlo reactor physics burnup calculation code. Using the neutron multiplication eigenvalue ke_ as a metric, MPACT’s performance is assessed on each of the progression problems. Initial results showed that MPACT’s multigroup cross section libraries, originally developed for pressurized water reactor problems, were not sufficient to accurately solve Magnox problems. MPACT’s improved performance on the progression problems is demonstrated using this new optimized cross section library.

scholarly journals A New Approach to Make Collapsed Cross Section for Burnup Calculation of Subcritical System

2008 ◽  
Vol 45 (sup5) ◽  
pp. 86-88 ◽  
Author(s):  
Masayuki Matsunaka ◽  
Keitaro Kondo ◽  
Hiroyuki Miyamaru ◽  
Isao Murata
Keyword(s):  
Cross Section ◽  
New Approach ◽  
Subcritical System ◽  
Burnup Calculation

scholarly journals Application of Frequency-Resonance Methods of Satellite Images Processing for Hydrogen and Living Water Accumulations Searching Within Local Areas in Europe

2021 ◽  
Vol 906 (1) ◽  
pp. 012080
Author(s):  
Mykola Yakymchuk ◽  
Ignat Korchagin ◽  
Arzu Javadova
Keyword(s):  
Cross Section ◽  
Satellite Images ◽  
Deep Structure ◽  
Low Cost ◽  
Exploration Process ◽  
Frequency Resonance ◽  
Basaltic Volcanoes ◽  
Speed Up ◽  
The Cross ◽  
Images Processing

Abstract The results of the application of mobile direct-prospecting technology of frequency-resonance processing and interpretation of satellite images and photo images at the sites hydrogen degassing in various regions are presented. Experimental reconnaissance studies were carried out to study the features of deep structure of the hydrogen degassing areas. The materials of instrumental measurements indicate that in regions of basalt volcano’s location with roots at different depths, signals at hydrogen frequencies are almost always recorded. When scanning the cross-section, responses from hydrogen are recorded from the upper edges of basaltic volcanoes to their roots. It can be assumed that basaltic volcanoes are a kind of channels through which hydrogen migrates to the upper horizons of the cross-section and further into the atmosphere. Within many basaltic volcanoes at a depth of 68 km, deep (living) water is synthesized. Hydrogen-rich water is curative and can be used for wellness purposes. All surveyed zones of longevity on Earth are located within basalt volcanoes, in which water synthesized at a depth of 68 km migrates to the surface and is used for water supply. Hydrogen deposits can be formed by basaltic volcanoes in adjacent sealed reservoirs. Within some survey areas, responses at hydrogen frequencies from limestones, dolomites and marls were recorded at shallow depths. Direct-prospecting technology can be used to study reservoirs in crystalline rocks (basalts including). Detailed studies and wells drilling in promising areas can be planned and carried out for hydrogen and living water at the same time. The result of investigation indicates the advisability of using direct-prospecting methods of frequency-resonance processing of satellite images to detect zones of hydrogen accumulation in areas of basalt volcano’s location, as well as in areas of hydrogen degassing. The use of mobile and low-cost technology will significantly speed up the exploration process for hydrogen, as well as reduce the financial costs for its implementation.

scholarly journals Diameter Estimation of Fallopian Tubes Using Visual Sensing

Biosensors ◽  
2021 ◽  
Vol 11 (4) ◽  
pp. 100
Author(s):  
Amir M. Hajiyavand ◽  
Matthew J. Graham ◽  
Karl D. Dearn
Keyword(s):  
Cross Section ◽  
Diagnostic Procedures ◽  
Fallopian Tubes ◽  
Precise Information ◽  
Visual Sensing ◽  
Automated Algorithm ◽  
Wide Range ◽  
Speed Up ◽  
2D Images ◽  
Biomedical Fields

Calculating an accurate diameter of arbitrary vessel-like shapes from 2D images is of great use in various applications within medical and biomedical fields. Understanding the changes in morphological dimensioning of the biological vessels provides a better understanding of their properties and functionality. Estimating the diameter of the tubes is very challenging as the dimensions change continuously along its length. This paper describes a novel algorithm that estimates the diameter of biological tubes with a continuously changing cross-section. The algorithm, evaluated using various controlled images, provides an automated diameter estimation with higher and better accuracy than manual measurements and provides precise information about the diametrical changes along the tube. It is demonstrated that the automated algorithm provides more accurate results in a much shorter time. This methodology has the potential to speed up diagnostic procedures in a wide range of medical fields.

XUV Absorption Spectra of Carbon Ions

1988 ◽  
Vol 102 ◽  
pp. 71-73
Author(s):  
E. Jannitti ◽  
P. Nicolosi ◽  
G. Tondello
Keyword(s):  
Absorption Spectra ◽  
Cross Section ◽  
Theoretical Calculations ◽  
Photoionization Cross Section ◽  
Carbon Ions

AbstractThe photoabsorption spectra of the carbon ions have been obtained by using two laser-produced plasmas. The photoionization cross-section of the CV has been absolutely measured and the value at threshold, σ=(4.7±0.5) × 10−19cm2, as well as its behaviour at higher energies agrees quite well with the theoretical calculations.

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