4 edition of **A Monte Carlo calculation of thermal utilization** found in the catalog.

- 84 Want to read
- 14 Currently reading

Published
**1958**
by Courant Institute of Mathematical Sciences, New York University in New York
.

Written in English

**Edition Notes**

Statement | by A. Rotenberg et al. |

Contributions | Rotenberg, A. |

The Physical Object | |
---|---|

Pagination | 33 p. |

Number of Pages | 33 |

ID Numbers | |

Open Library | OL20424615M |

Neutron source utilization rate is low. In the present study, Monte Carlo calculation was carried out for the design of a Cf neutron source moderation setup for the analysis cement samples[7]. The model of Monte Carlo simulation was verified by experiment[8, 9].We improve the thermal neutron source yield rate of Cf neutron by. MONTE CARLO IN RADIATION THERAPY. The Monte Carlo techniques have been used in various branches of radiation therapy,[8,9] from simulation of radiation therapy equipments and sources to dose calculation in various geometries.[10–18] For simulation of the photon and electron particles one has to apply the physics of transport for modeling, which requires the knowledge of interactions of the.

After the introduction of the first principles treatment, tight-binding and classical potential methods are briefly introduced to indicate how one can increase the number of atoms in the system. In the second half of the book, Monte Carlo simulation is discussed in detail. Problems and solutions are provided to facilitate understanding. The analyses used the Monte Carlo program RCP01, with explicit three-dimensional geometry and detailed representation of cross sections. For the homogeneous criticals, calculated k{sub crit} values for large, thermal assemblies show good agreement with experiment. This supports the evaluated thermal criticality parameters for U{supmore».

Advances in Monte Carlo Criticality Calculations Forrest B. Brown & Russell D. Mosteller Diagnostics Applications Group (X-5), LANL This workshop will focus on recent advances in methods, codes, and data for Monte Carlo criticality calculations, including: improvements to MCNP5 kcode calculations, source entropy as a convergence. Monte Carlo Simulation analysis showed the percentages of interference are %, %, %, and % for N = 1, N = 3, N = 4, and N = 7 respectively. In terms of throughput per total bandwidth per a single site, N = 7 offers a spectrum utilization of 1/7 and N = 4 offers a spectrum utilization of 1/4.

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A Monte Carlo calculation of thermal utilization [Rotenberg, A, Rotenberg, A] on *FREE* shipping on qualifying offers.

A Monte Carlo calculation of thermal utilizationCited by: 1. An illustration of an open book. Books.

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A Monte Carlo calculation of thermal utilization Item Preview remove-circle Share or Embed This : The Neutron Transport Theory is accurate in reactor engineering analysis, but the calculation process is tedious and complicated. The objective of the present study obtains the thermal utilization factor f by Monte Carlo method.

The study establishes the pressurized water reactor model by MCNP program firstly, and calculates the dioxide pellets, zirconium alloy cladding and moderator’s Author: Bo Yang, He Xi Wu, Qiang Lin Wei, Yi Bao Liu. A Monte Carlo simulation and setup optimization of output efficiency to PGNAA thermal neutron using Cf neutrons Zhang Jinzhao1（张金钊）Tuo Xianguo1,2,3（庹先国） (1.

The Monte Carlo program MCNP-4B was used to simulate the vertical access of the thermal column of the Portuguese Research Reactor. The reactor core was included in the simulations and two models for the neutron source were studied. Measurements were done with activation : A. Fernandes, A. Vieira, I.

Gonçalves, A. Ramalho. The Department of Energy (DOE) has given the Spallation Neutron Source (SNS) project approval to begin Title I design of the proposed facility to be built at Oak Ridge National Laboratory (ORNL) and construction is scheduled to commence in FY The SNS initially will consist of an accelerator system capable of delivering an approximately microsecond pulse of 1 GeV protons, at a 60 Hz.

Johnson J.O. () Utilization of Monte Carlo Calculations in Radiation Transport Analyses to Support the Design of the U.S. Spallation Neutron Source (SNS). In: Kling A., Baräo F.J.C., Nakagawa M., Távora L., Vaz P. (eds) Advanced Monte Carlo for Radiation Physics, Particle Transport Simulation and Applications.

The Monte Carlo N-Particle (MCNP6) code with integrated buildup depletion code (CINDER90) provides a high-fidelity tool that can be used to perform 3D, full core simulation to evaluate fissile material utilization, and nuclide inventory calculations as a function of burnup. We used the Monte Carlo program MCNP to calculate the neutron and gamma fluxes on a fast neutron irradiation facility being installed on the Portuguese Research Reactor (RPI).

The purpose of this facility is to provide a fast neutron beam for irradiation of electronic circuits. nature. This weakness can be fixed on the basis of Monte Carlo implementation to IRR and cash flow simulation (Raharjo, ).

This paper describes the usage and the results of the method. MONTE CARLO SIMULATION The Gaussian distribution is a collection of samples, where its distribution can be drawn as a normal bell-shape function.

SERPENT Monte Carlo code (Leppänen et al., ) is a good choice for MSR fuel cycle simulation, but it is only accessed by member institutes. This study focuses on the development of a direct calculation method for MSR fuel cycle simulation based on an open source Monte Carlo.

This book focusses on the state of the art of Monte Carlo methods in radiation physics and particle transport simulation and applications, the latter involving in particular, the use and development of electron--gamma, neutron--gamma and hadronic codes.

Besides the basic theory and the methods. Abstract— Monte Carlo (MC) simulation is extensively used for solving thermal radiation problems in high-temperature environments, such as combustion chambers and furnaces, and irregular-geometry enclosures containing participative media such as combustive gases.

The. Cite this chapter as: Golinelli P., Brunetti R., Varani L., Reggiani L., Rudan M. () Monte Carlo Calculation of Hot-Carrier Thermal Conductivity in Semiconductors. Monte Carlo simulation is applied to investigate phonon transport in single crystalline Si nanowires. Phonon-phonon normal (N) and Umklapp (U) scattering processes are modeled with a genetic algorithm to satisfy energy and momentum conservation.

The scattering rates of N and U scattering processes are found from first-order perturbation theory. Almazan, P.,“Accuracy Control in Monte Carlo Radiative Calculations,” Proc.

5th Annual Thermal and Fluids Analysis Workshop, NASA Lewis Research Center, pp. 47– 5. Ambirajan. Dynamic thermal rating (DTR) of transmission lines is related to wind speed, wind direction, ambient temperature, and so on. Among the environmental parameters, there is a difference between the obtained environmental parameters and the true value.

Therefore, only the deterministic values of environmental parameters and DTR are not accurate enough. Considering the environmental. Tutorial on Monte Carlo Techniques Gabriel A. Terejanu Department of Computer Science and Engineering University at Buﬀalo, Buﬀalo, NY [email protected] 1 Introduction Monte Carlo (MC) technique is a numerical method that makes use of random numbers to solve mathematical problems for which an analytical solution is not known.

The recently reported method for computing thermal desorption rates via a Monte Carlo evaluation of the appropriate transition state theory expression [J. Adams and J. Doll, J. Chem. Phys. 74, ()] is extended, by the use of importance sampling, so as to generate the complete temperature dependence in a single calculation.

We also describe a straightforward means of calculating. may be unnecessary to perform a Monte Carlo analysis when the costs of remediation are low. On the other hand, there may be a number of situations in which a Monte Carlo analysis may be useful.

For example, a Monte Carlo analysis may be useful when screening calculations using conservative point estimates fall above the levels of concern. Other. One approach that can produce a better understanding of the range of potential outcomes and help avoid the “flaw of averages” is a Monte Carlo simulation.

The rest of this article will describe how to use python with pandas and numpy to build a Monte Carlo simulation to predict the range of potential values for a sales compensation budget.Monte Carlo methods are increasingly being used for whole core reactor physics modelling.

We describe a number of recent developments to the MONK nuclear criticality and reactor physics code to implement parallel processing, mesh-dependent burn-up and coupling to both thermal .In the paper several application techniques of MonteCarlo (MC) method applied to thermal analysis of space vehicles are presented.

Although these methods are widely used in other engineering domains, their introduction to the thermal one is quite recent and not fully developed in the industrial practice.