Surface-harmonic calculation of the RBMK-reactor polycells and fuel assemblies

Atomic Energy ◽  
1993 ◽  
Vol 74 (6) ◽  
pp. 440-448 ◽  
Author(s):  
N. I. Laletin ◽  
N. V. Sultanov ◽  
V. A. Lyul'ka
Keyword(s):  
Rbmk Reactor ◽  
Fuel Assemblies ◽  
Surface Harmonic

Validation of HELIOS Neutron Cross-Section Library for RBMK Reactors Against the Data From the Critical Facility Experiments

2002 ◽  
Author(s):  
Audrius Jasiulevicius ◽  
Bal Raj Sehgal
Keyword(s):  
Neutron Flux ◽  
Cross Section ◽  
Cross Sections ◽  
Measurement Errors ◽  
Reactor Core ◽  
Rbmk Reactor ◽  
Cross Section Data ◽  
Section Data ◽  
Fuel Assemblies ◽  
Calculation Results

The RBMK reactors are channel type, water-cooled and graphite moderated reactors. The first RBMK type electricity production reactor was put on-line in 1973. Currently there are 13 operating reactors of this type. Two of the RBMK-1500 reactors are at the Ignalina NPP in Lithuania. Experimental Critical Facility for RBMK reactors, located at Kurchiatov Institute, Moscow was designed to carry out critical reactivity experiments on assemblies, which imitate parts of the RBMK reactor core. The facility is composed of Control and Protection Rods (CPR’s), fuel assemblies with different enrichment in U-235 and other elements, typical for RBMK reactor core loadings, e.g. additional absorber assemblies, CPR imitators, etc. A simulation of a set of the experiments, performed at the Experimental Critical Facility, was carried out at the Royal Institute of Technology (RIT), Nuclear Power Safety Division, using CORETRAN 3-D neutron dynamics code. The neutron cross sections for assemblies were calculated using HELIOS code. The aim of this work was to evaluate capabilities of the HELIOS code to provide correct cross section data for the RBMK reactor. The calculation results were compared to the similar CORETRAN calculations, when employing WIMS-D4 code generated cross section data. For some of the experiments, where calculation results with CASMO-4 code generated cross sections are available, the comparison is also performed against CASMO-4 results. Eleven different experiments were simulated. Experiments differ in size of the facility core (number of assemblies loaded): from simple core loadings, composed only of a few fuel assemblies, to complicated configurations, which represent a part of the RBMK reactor core. Diverse types of measurements were carried out during these experiments: reactivity, neutron flux distributions (both axial and radial), rod reactivity worth and the voiding effects. Results of the reactivity measurements and relative neutron flux distributions were given in the Experiment report [1] as parameters, to be obtained using static calculations, i.e. the reported results were already processed numerically using the facility equipment, e.g. the reactimeter. The reported measurement errors consist only of instrumentation errors, i.e. measurement method errors and the influence from the space–time effects were not included in the error evaluation.

Detection and mapping of interactions between chromatin and the nuclear envelope in drosophila embryos

1995 ◽  
Vol 53 ◽  
pp. 764-765
Author(s):  
W.F. Marshall ◽  
A.F. Dernburg ◽  
B. Harmon ◽  
J.W. Sedat
Keyword(s):  
Nuclear Envelope ◽  
Chromatin Condensation ◽  
Three Dimensional ◽  
Physiological Role ◽  
Nuclear Surface ◽  
Intact Cells ◽  
Molecular Determinants ◽  
Surface Harmonic ◽  
Drosophila Embryos

Interactions between chromatin and nuclear envelope (NE) have been implicated in chromatin condensation, gene regulation, nuclear reassembly, and organization of chromosomes within the nucleus. To further investigate the physiological role played by such interactions, it will be necessary to determine which loci specifically interact with the nuclear envelope. This will not only facilitate identification of the molecular determinants of this interaction, but will also allow manipulation of the pattern of chromatin-NE interactions to probe possible functions. We have developed a microscopic approach to detect and map chromatin-NE interactions inside intact cells.Fluorescence in situ hybridization (FISH) is used to localize specific chromosomal regions within the nucleus of Drosophila embryos and anti-lamin immunofluorescence is used to detect the nuclear envelope. Widefield deconvolution microscopy is then used to obtain a three-dimensional image of the sample (Fig. 1). The nuclear surface is represented by a surface-harmonic expansion (Fig 2). A statistical test for association of the FISH spot with the surface is then performed.

Experimental Benchmark of a Lift Force Model for PWR Fuel Assemblies

2010 ◽  
pp. 50-56
Author(s):  
Pablo R. Rubiolo ◽  
Guy Chaigne ◽  
Pierre Peturand ◽  
Jérôme Bigot ◽  
Jean-François Desseignes ◽  
...  
Keyword(s):  
Lift Force ◽  
Force Model ◽  
Fuel Assemblies

Use CFD Model of WWER-1200 Reactor for Prediction of Fuel Assemblies Vibrations

2019 ◽  
Vol 12 (4) ◽  
pp. 62-70
Author(s):  
K.N. Proskuryakov ◽  
A.V. Anikeev ◽  
E. Afshar ◽  
D.A. Pisareva
Keyword(s):  
Cfd Model ◽  
Fuel Assemblies

Optimization of power microfield distribution in JA profiles RK3+ fuel assemblies with 4.68% average enrichment for VVER-440 prospective fuel cycles

Kerntechnik ◽  
2020 ◽  
Vol 85 (4) ◽  
pp. 213-225
Author(s):  
A. A. Gagarinskiy ◽  
Zh. Yu. Liventseva ◽  
D. R. Kireeva ◽  
D. A. Oleksyuk ◽  
Yu. P. Kalinin ◽  
...  
Keyword(s):  
Fuel Cycles ◽  
Fuel Assemblies

Advantages of VVER-440 fuel cycles with new fuel assemblies

Kerntechnik ◽  
2018 ◽  
Vol 83 (4) ◽  
pp. 307-313 ◽  
Author(s):  
A. Gagarinskiy ◽  
E. Osipova ◽  
Yu. Kalinin
Keyword(s):  
Fuel Cycles ◽  
Fuel Assemblies

scholarly journals Analysis of the Accelerator-Driven System Fuel Assembly during the Steam Generator Tube Rupture Accident

Materials ◽  
2021 ◽  
Vol 14 (8) ◽  
pp. 1818
Author(s):  
Di-Si Wang ◽  
Bo Liu ◽  
Sheng Yang ◽  
Bin Xi ◽  
Long Gu ◽  
...  
Keyword(s):  
Fuel Assembly ◽  
Steam Generator ◽  
Metal Flow ◽  
Maximum Temperature ◽  
Steam Generator Tube ◽  
Driven System ◽  
Fuel Assemblies ◽  
Accelerator Driven System ◽  
The Impact ◽  
Steam Bubble

China is developing an ADS (Accelerator-Driven System) research device named the China initiative accelerator-driven system (CiADS). When performing a safety analysis of this new proposed design, the core behavior during the steam generator tube rupture (SGTR) accident has to be investigated. The purpose of our research in this paper is to investigate the impact from different heating conditions and inlet steam contents on steam bubble and coolant temperature distributions in ADS fuel assemblies during a postulated SGTR accident by performing necessary computational fluid dynamics (CFD) simulations. In this research, the open source CFD calculation software OpenFOAM, together with the two-phase VOF (Volume of Fluid) model were used to simulate the steam bubble behavior in heavy liquid metal flow. The model was validated with experimental results published in the open literature. Based on our simulation results, it can be noticed that steam bubbles will accumulate at the periphery region of fuel assemblies, and the maximum temperature in fuel assembly will not overwhelm its working limit during the postulated SGTR accident when the steam content at assembly inlet is less than 15%.

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