• 제목/요약/키워드: Monte-Carlo(MC)

검색결과 213건 처리시간 0.024초

Development of transient Monte Carlo in a fissile system with β-delayed emission from individual precursors using modified open source code OpenMC(TD)

  • J. Romero-Barrientos;F. Molina;J.I. Marquez Damian;M. Zambra;P. Aguilera;F. Lopez-Usquiano;S. Parra
    • Nuclear Engineering and Technology
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    • 제55권5호
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    • pp.1593-1603
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    • 2023
  • In deterministic and Monte Carlo transport codes, b-delayed emission is included using a group structure where all of the precursors are grouped together in 6 groups or families, but given the increase in computational power, nowadays there is no reason to keep this structure. Furthermore, there have been recent efforts to compile and evaluate all the available b-delayed neutron emission data and to measure new and improved data on individual precursors. In order to be able to perform a transient Monte Carlo simulation, data from individual precursors needs to be implemented in a transport code. This work is the first step towards the development of a tool to explore the effect of individual precursors in a fissile system. In concrete, individual precursor data is included by expanding the capabilities of the open source Monte Carlo code OpenMC. In the modified code - named Time Dependent OpenMC or OpenMC(TD)- time dependency related to β-delayed neutron emission was handled by using forced decay of precursors and combing of the particle population. The data for continuous energy neutron cross-sections was taken from JEFF-3.1.1 library. Regarding the data needed to include the individual precursors, cumulative yields were taken from JEFF-3.1.1 and delayed neutron emission probabilities and delayed neutron spectra were taken from ENDF-B/VIII.0. OpenMC(TD) was tested in a monoenergetic system, an energy dependent unmoderated system where the precursors were taken individually or in a group structure, and in a light-water moderated energy dependent system, using 6-groups, 50 and 40 individual precursors. Neutron flux as a function of time was obtained for each of the systems studied. These results show the potential of OpenMC(TD) as a tool to study the impact of individual precursor data on fissile systems, thus motivating further research to simulate more complex fissile systems.

이온빔 몬테 카를로 시물레이션 프로그램 개발 및 집속 이온빔 공정 해석 (Development of Ion Beam Monte Carlo Simulation and Analysis of Focused Ion Beam Processing)

  • 김흥배
    • 한국정밀공학회지
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    • 제29권4호
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    • pp.479-486
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    • 2012
  • Two of fundamental approaches that can be used to understand ion-solid interaction are Monte Carlo (MC) and Molecular Dynamic (MD) simulations. For the simplicity of simulation Monte Carlo simulation method is widely preferred. In this paper, basic consideration and algorithm of Monte Carlo simulation will be presented as well as simulation results. Sputtering caused by incident ion beam will be discussed with distribution of sputtered particles and their energy distributions. Redeposition of sputtered particles that are experienced refraction at the substrate-vacuum interface additionally presented. In addition, reflection of incident ions with reflection coefficient will be presented together with spatial and energy distributions. This Monte Carlo simulation will be useful in simulating and describing ion beam related processes such as Ion beam induced deposition/etching process, local nano-scale distribution of focused ion beam implanted ions, and ion microscope imaging process etc.

MC21/CTF and VERA multiphysics solutions to VERA core physics benchmark progression problems 6 and 7

  • Kelly, Daniel J. III;Kelly, Ann E.;Aviles, Brian N.;Godfrey, Andrew T.;Salko, Robert K.;Collins, Benjamin S.
    • Nuclear Engineering and Technology
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    • 제49권6호
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    • pp.1326-1338
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    • 2017
  • The continuous energy Monte Carlo neutron transport code, MC21, was coupled to the CTF subchannel thermal-hydraulics code using a combination of Consortium for Advanced Simulation of Light Water Reactors (CASL) tools and in-house Python scripts. An MC21/CTF solution for VERA Core Physics Benchmark Progression Problem 6 demonstrated good agreement with MC21/COBRA-IE and VERA solutions. The MC21/CTF solution for VERA Core Physics Benchmark Progression Problem 7, Watts Bar Unit 1 at beginning of cycle hot full power equilibrium xenon conditions, is the first published coupled Monte Carlo neutronics/subchannel T-H solution for this problem. MC21/CTF predicted a critical boron concentration of 854.5 ppm, yielding a critical eigenvalue of $0.99994{\pm}6.8E-6$ (95% confidence interval). Excellent agreement with a VERA solution of Problem 7 was also demonstrated for integral and local power and temperature parameters.

채권 옵션의 가격결정을 위한 이자율 모형의 관계에 대한 알고리즘과 몬테 카르로 시뮬레이션 (The Monte Carlo Simulation and Algorithm on the Relationship Interest Rate Models for the Pricing of Bond Options)

  • 이광연;박기섭
    • 한국시뮬레이션학회논문지
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    • 제28권3호
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    • pp.49-56
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    • 2019
  • 본 논문에서는 선도이자율 모형과 리보이자율 모형 사이의 관계를 이용하여 채권 옵션의 해석적인 해(Analytic Solution; AS)와 몬테 카르로 시뮬레이션(Monte Carlo Simulation; MCS)을 이용한 가격 결정을 다룬다. AS를 이용한 채권 옵션가격 결정은 Ritchken and Sankarasubramanian (RS)의 제한 조건을 이용하여 할인된 채권 가격을 구하는 공식을 유도하고, 선도이자율과 리보이자율 모형의 변동함수 사이의 관계를 활용한다. MCS을 이용한 채권 옵션 가격 결정은 MCS을 이용하여 제시된 조건으로부터 여러 가지 예정된 전개의 시뮬레이션을 활용한다. AS와 MCS을 이용한 가격 결정 방법을 실행하여 얻은 가격을 비교하면 AS와 MCS의 상대오차(Relative Error; RE)를 구할 수 있다. 이때 본 연구의 결과로부터 RE가 약 3.9%가 됨을 확인할 수 있다. 이것은 AS뿐만 아니라 MCS을 이용해도 채권 옵션의 가격을 매우 정확하게 예측할 수 있음을 의미한다.

다층 리지스트 다층 기판 구조에서의 전자빔 리소그래피 공정을 위한 몬테카를로 시뮬레이터의 개발 (Development of a Monte Carlo Simulator for Electron Beam Lithography in Multi-Layer Resists and Multi-Layer Substrates)

  • 손명식;이진구;황호정
    • 대한전자공학회:학술대회논문집
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    • 대한전자공학회 2002년도 하계종합학술대회 논문집(2)
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    • pp.53-56
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    • 2002
  • We have developed a Monte Carlo (MC) simulator for electron beam lithography in multi-layer resists and multi-layer substrates in order to fabricate and develop high-speed PHEMT devices for millimeter- wave applications. For the deposited energy calculation to multi-layer resists by electron beam in MC simulation, we modeled newly for multi-layer resists and heterogeneous multi-layer substrates. Using this model, we simulated T-gate or r-gate fabrication process in PHEMT device and showed our results with SEM observations.

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Prediction of Chiral Discrimination by β-Cyclodextrins Using Grid-based Monte Carlo Docking Simulations

  • Choi, Young-Jin;Kim, Dong-Wook;Park, Hyung-Woo;Hwang, Sun-Tae;Jeong, Karp-Joo;Jung, Seun-Ho
    • Bulletin of the Korean Chemical Society
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    • 제26권5호
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    • pp.769-775
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    • 2005
  • An efficiency of Monte Carlo (MC) docking simulations was examined for the prediction of chiral discrimination by cyclodextrins. Docking simulations were performed with various computational parameters for the chiral discrimination of a series of 17 enantiomers by $\beta$-cyclodextrin ($\beta$-CD) or by 6-amino-6-deoxy-$\beta$-cyclodextrin (am-$\beta$-CD). A total of 30 sets of enantiomeric complexes were tested to find the optimal simulation parameters for accurate predictions. Rigid-body MC docking simulations gave more accurate predictions than flexible docking simulations. The accuracy was also affected by both the simulation temperature and the kind of force field. The prediction rate of chiral preference was improved by as much as 76.7% when rigid-body MC docking simulations were performed at low-temperatures (100 K) with a sugar22 parameter set in the CHARMM force field. Our approach for MC docking simulations suggested that the conformational rigidity of both the host and guest molecule, due to either the low-temperature or rigid-body docking condition, contributed greatly to the prediction of chiral discrimination.

Domain decomposition for GPU-Based continuous energy Monte Carlo power reactor calculation

  • Choi, Namjae;Joo, Han Gyu
    • Nuclear Engineering and Technology
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    • 제52권11호
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    • pp.2667-2677
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    • 2020
  • A domain decomposition (DD) scheme for GPU-based Monte Carlo (MC) calculation which is essential for whole-core depletion is introduced within the framework of the modified history-based tracking algorithm. Since GPU-offloaded MC calculations suffer from limited memory capacity, employing DDMC is inevitable for the simulation of depleted cores which require large storage to save hundreds of newly generated isotopes. First, an automated domain decomposition algorithm named wheel clustering is devised such that each subdomain contains nearly the same number of fuel assemblies. Second, an innerouter iteration algorithm allowing overlapped computation and communication is introduced which enables boundary neutron transactions during the tracking of interior neutrons. Third, a bank update scheme which is to include the boundary sources in a way to be adequate to the peculiar data structures of the GPU-based neutron tracking algorithm is presented. The verification and demonstration of the DDMC method are done for 3D full-core problems: APR1400 fresh core and a mock-up depleted core. It is confirmed that the DDMC method performs comparably with the standard MC method, and that the domain decomposition scheme is essential to carry out full 3D MC depletion calculations with limited GPU memory capacities.

Investigation of Lithium Transference Number in PMMA Composite Polymer Electrolytes Using Monte Carlo (MC) Simulation and Recurrence Relation

  • Koh, Renwei Eric;Sun, Cha Chee;Yap, Yee Ling;Cheang, Pei Ling;You, Ah Heng
    • Journal of Electrochemical Science and Technology
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    • 제12권2호
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    • pp.217-224
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    • 2021
  • In this study, Monte Carlo (MC) simulation is conducted with recurrence relation to study the effect of SiO2 with different particle size and their roles in enhancing the ionic conductivity and lithium transference number of PMMA composite polymer electrolytes (CPEs). The MC simulated ionic conductivity is verified with the measurements from Electrochemical Impedance Spectroscopy (EIS). Then, the lithium transference number of CPEs is calculated using recurrence relation with the MC simulated current density and the reference transference number obtained. Incorporation of micron-size SiO2 (≤10 ㎛) fillers into the mixture improves the ionic conductivity from 8.60×10-5 S/cm to 2.35×10-4 S/cm. The improvement is also observed on the lithium transference number, where it increases from 0.088 to 0.3757. Furthermore, the addition of nano-sized SiO2 (≤12 nm) fillers further increases the ionic conductivity up towards 3.79×10-4 S/cm and lithium transference number of 0.4105. The large effective surface area of SiO2 fillers is responsible for the improvement in ionic conductivity and the transference number in PMMA composite polymer electrolytes.

A top-down iteration algorithm for Monte Carlo method for probability estimation of a fault tree with circular logic

  • Han, Sang Hoon
    • Nuclear Engineering and Technology
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    • 제50권6호
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    • pp.854-859
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    • 2018
  • Calculating minimal cut sets is a typical quantification method used to evaluate the top event probability for a fault tree. If minimal cut sets cannot be calculated or if the accuracy of the quantification result is in doubt, the Monte Carlo method can provide an alternative for fault tree quantification. The Monte Carlo method for fault tree quantification tends to take a long time because it repeats the calculation for a large number of samples. Herein, proposal is made to improve the quantification algorithm of a fault tree with circular logic. We developed a top-down iteration algorithm that combines the characteristics of the top-down approach and the iteration approach, thereby reducing the computation time of the Monte Carlo method.

Asymptotic Comparison of Latin Hypercube Sampling and Its Stratified Version

  • Lee, Jooho
    • Journal of the Korean Statistical Society
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    • 제28권2호
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    • pp.135-150
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    • 1999
  • Latin hypercube sampling(LHS) introduced by McKay et al. (1979) is a widely used method for Monte Carlo integration. Stratified Latin hypercube sampling(SLHS) proposed by Choi and Lee(1993) improves LHS by combining it with stratified sampling. In this article it is shown that SLHS yields an asymptotically more accurate than both stratified sampling and LHS.

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