Evaluation Technique With MCNP for Temperature Dependent Problems

2010 ◽  
Author(s):  
Hiroyuki Fujime ◽  
Shinji Abe ◽  
Kazuya Yamaji ◽  
Daisuke Sato ◽  
Hideki Matsumoto
Keyword(s):  
Monte Carlo ◽  
Cross Sections ◽  
Monte Carlo Calculation ◽  
Design Codes ◽  
Design Code ◽  
Temperature Dependent ◽  
Validation And Verification ◽  
The World ◽  
Profile Changes ◽  
Complex Temperature

Monte Carlo calculation has come to be used as reference solutions instead of experiments in nuclear design code validation and verification (V&V), although comparisons with measurements are still indispensable for V&V in nuclear design. MCNP [1] is one of the most famous Monte Carlo codes widely used in the world. Many reference results are given for the analyses of critical experiments. When using the use MCNP calculations for validations of commercial design codes, we will face to a problem of lacking temperature dependent cross-sections. The cross-sections can be generated by the NJOY code [2]. However, if the model has complex temperature distribution, many NJOY calculations are necessary. Besides, if the temperature profile changes with fuel power and so on, many NJOY calculations have to be performed again and again. These back and forth procedures make us give up using MCNP for commercial LWR calculations. In order to solve this problem, we propose an easy approximation to solve the temperature problems using MCNP. Note that our technique does not require any code modifications.

The Generation of Few-Group Constants for Fast Reactor Analysis

2016 ◽  
Author(s):  
Xianan Du ◽  
Liangzhi Cao ◽  
Youqi Zheng
Keyword(s):  
Monte Carlo ◽  
Cross Section ◽  
Cross Sections ◽  
Fast Reactor ◽  
Monte Carlo Calculation ◽  
Anisotropic Scattering ◽  
Slowing Down ◽  
Nodal Method ◽  
Reactor Calculation ◽  
Broad Energy

A way to generate the few-group cross sections for fast reactor calculation is presented in this paper. It is based on the three steps computational scheme. In the first step, the ultrafine method is used to solve the slowing down equation based on the ultrafine group cross section generated by NJOY. Optional 0D or 1D calculation is used to collapse energy group into broad energy groups. In the second step, the 2D RZ calculation using SN method is performed to obtain the space dependent neutron spectra to collapse broad energy groups into few groups. The anisotropic scattering is well handled by the direct SN calculation. Finally, the full core calculation is performed by using the 3D SN nodal method. The results are compared with continuous energy Monte-Carlo calculation. Both the cross section generated in the first step and the final keff in the last step are compared. The results match well between the three steps calculation and Monte-Carlo calculation.

STOPPING CROSS SECTIONS IN CARBON FOR LOW-ENERGY ATOMS WITH

1963 ◽  
Vol 41 (9) ◽  
pp. 1424-1442 ◽  
Author(s):  
J. H. Ormrod ◽  
H. E. Duckworth
Keyword(s):  
Monte Carlo ◽  
Cross Section ◽  
Atomic Number ◽  
Cross Sections ◽  
Monte Carlo Calculation ◽  
Low Energy ◽  
Energy Interval ◽  
Nuclear Scattering

The electronic stopping cross sections in carbon for atomic projectiles with [Formula: see text] have been determined in the energy interval from 10 to 140 kev. In doing so a Monte Carlo calculation was used to subtract from each experimentally observed cross section the contribution which arises from nuclear scattering. The trend of the results thus obtained agrees well with theory. In addition, however, a periodic dependence of Sε on the atomic number of the projectile is observed.

scholarly journals New Technique to Reformat Multigroup Cross-Sections for Monte-Carlo Calculation

2012 ◽  
Vol 2012 (4) ◽  
pp. 5-12
Author(s):  
Igor’ Ryurikovich Suslov ◽  
Ivan Vladimirovich Tormyshev ◽  
K. G. Melnikov
Keyword(s):  
Monte Carlo ◽  
Cross Sections ◽  
Monte Carlo Calculation ◽  
New Technique

Application of Isolation to High-Rise Buildings: A Japanese Design Case Study through a U.S. Design Code Lens

2015 ◽  
Vol 31 (3) ◽  
pp. 1451-1470 ◽  
Author(s):  
Tracy C. Becker ◽  
Shunji Yamamoto ◽  
Hiroki Hamaguchi ◽  
Masahiko Higashino ◽  
Masayoshi Nakashima
Keyword(s):  
Base Isolation ◽  
Tall Buildings ◽  
Design Codes ◽  
Design Code ◽  
High Rise ◽  
The World ◽  
Design Case ◽  
Design Case Study ◽  
The U.S

Base isolation of high-rise buildings has been growing in popularity in Japan, yet it is uncommon in most of the world. While tall buildings already have long periods and thus lower input accelerations, the addition of isolation can decrease inter-story drifts and greatly decrease floor acceleration, protecting building content. By protecting building content, high-rises can be kept fully operational and occupiable after earthquakes. The Japanese design code has clearly outlined procedures for designing isolated high-rises, facilitating the implementation of isolation; however, other design codes—and specifically the U.S. code—make the adoption of isolation difficult for these buildings. Using a design representative of typical isolated high-rises in Japan, it is shown that while isolation is feasible under U.S. design levels, requirements are much more stringent, and some changes from the Japanese design would be required to make the design acceptable under the U.S. code.

Reliability Studies on Concrete Filled FRP Tube Columns Using Different Design Code Models

2013 ◽  
Vol 405-408 ◽  
pp. 735-739
Author(s):  
Ying Wu Zhou ◽  
Li Li Sui ◽  
Feng Xing
Keyword(s):  
Tensile Strength ◽  
Monte Carlo ◽  
Monte Carlo Method ◽  
Reliability Index ◽  
Concrete Strength ◽  
Design Codes ◽  
Design Code ◽  
Reliability Study ◽  
Simulation Results ◽  
Frp Tube

The paper presents an in-deep reliability study on concrete filled FRP tube columns using four well-known design codes which include the ACI 4402R-08, the CNR-DT200, UK code (TR55) , and the Chinese code. Monte Carlo method is utilized to calculate the reliability index of the column. The simulation results reveal that the reliability index depends heavily on the design code and the ACI 4402R-08 design code is found to be the most reliable one for the design of concrete filled FRP tube columns. The variation of the unconfined concrete strength has remarkable influences on the reliability of the column while the variation of the FRP tensile strength can hardly affect the reliability. Consequently, it is concluded that the partial safety factor for concrete or the FRP proposed in existing design codes may be suitably enhanced in order to make up the reliability loss due to the increment of the variation of concrete.

Electron Scattering in Solids

1990 ◽  
Vol 48 (2) ◽  
pp. 4-5
Author(s):  
Ryuichi Shimizu ◽  
Ze-Jun Ding
Keyword(s):  
Monte Carlo Simulation ◽  
Monte Carlo ◽  
Angular Distribution ◽  
Elastic Scattering ◽  
Electron Scattering ◽  
Cross Sections ◽  
Expansion Method ◽  
Electron Excitation ◽  
Partial Wave Expansion ◽  
Backscattered Electrons

Monte Carlo simulation has been becoming most powerful tool to describe the electron scattering in solids, leading to more comprehensive understanding of the complicated mechanism of generation of various types of signals for microbeam analysis.The present paper proposes a practical model for the Monte Carlo simulation of scattering processes of a penetrating electron and the generation of the slow secondaries in solids. The model is based on the combined use of Gryzinski’s inner-shell electron excitation function and the dielectric function for taking into account the valence electron contribution in inelastic scattering processes, while the cross-sections derived by partial wave expansion method are used for describing elastic scattering processes. An improvement of the use of this elastic scattering cross-section can be seen in the success to describe the anisotropy of angular distribution of elastically backscattered electrons from Au in low energy region, shown in Fig.l. Fig.l(a) shows the elastic cross-sections of 600 eV electron for single Au-atom, clearly indicating that the angular distribution is no more smooth as expected from Rutherford scattering formula, but has the socalled lobes appearing at the large scattering angle.

Monte Carlo calculation of the energy parameters and spatial distribution of the cathodic arc ions while passing through the macro-particles filters

2018 ◽  
Vol 1 (1) ◽  
pp. 30-34 ◽  
Author(s):  
Alexey Chernogor ◽  
Igor Blinkov ◽  
Alexey Volkhonskiy
Keyword(s):  
Magnetic Field ◽  
Mass Transfer ◽  
Monte Carlo ◽  
Monte Carlo Calculation ◽  
Inhomogeneous Magnetic Field ◽  
Flow Energy ◽  
Wide Range ◽  
Field Concentrator ◽  
Cathodic Arc ◽  
The Magnetic Field

The flow, energy distribution and concentrations profiles of Ti ions in cathodic arc are studied by test particle Monte Carlo simulations with considering the mass transfer through the macro-particles filters with inhomogeneous magnetic field. The loss of ions due to their deposition on filter walls was calculated as a function of electric current and number of turns in the coil. The magnetic field concentrator that arises in the bending region of the filters leads to increase the loss of the ions component of cathodic arc. The ions loss up to 80 % of their energy resulted by the paired elastic collisions which correspond to the experimental results. The ion fluxes arriving at the surface of the substrates during planetary rotating of them opposite the evaporators mounted to each other at an angle of 120° characterized by the wide range of mutual overlapping.

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