2 edition of **On the variance reduction techniques in Monte Carlo solutions of neutron transport problems.** found in the catalog.

On the variance reduction techniques in Monte Carlo solutions of neutron transport problems.

Heikki Kalli

- 219 Want to read
- 39 Currently reading

Published
**1972**
by The Finnish Academy of Technical Sciences in Helsinki
.

Written in English

**Edition Notes**

Series | Acta Polytechnica Scandinavica : Physics including Nucleonics Series -- No. 89 |

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

Pagination | 23 p., ill |

Number of Pages | 23 |

ID Numbers | |

Open Library | OL21258912M |

ISBN 10 | 9516660118 |

The use of Monte Carlo variance reduction techniques is unavoidable on present day computers in obtaining numerical solutions in complex shielding, deep penetration or other radiation transport problems such as nuclear well logging and ex-core reactor core modeling etc. The left side of equation (2) is the uniform distribution between 0 and 1 and f(y) is the distribution needed. In this way any distribution can be made with a uniform distribution. Monte Carlo results are obtained by simulating particle histories and assigning a score x i to each particle history. The particle histories typically produce a range of score depending on the selected tally.

Among the various variance-reduction methods in Monte Carlo calculations, one of the most widely used techniques is the weight window method. The MCNP code provides a weight window generator (WWG) option. In WWG of MCNP, the importance of a cell is estimated by the virtual sampling method during normal Monte Carlo calculation. Get this from a library! Advanced Quadrature Selection for Monte Carlo Variance Reduction. [Kelly Rowland] -- Neutral particle radiation transport simulations are critical for radiation shielding and deep penetration applications. Arriving at a solution for a given response of interest can be computationally.

monte carlo methods for particle transport Posted By Corín Tellado Media Publishing TEXT ID ca30 Online PDF Ebook Epub Library simulation of radiation transport the history track of a particle is viewed as a random sequence of free flights the . The author derives a transformed transport problem that can be solved theoretically by analog Monte Carlo with zero variance. However, the Monte Carlo simulation of this transformed problem cannot be implemented in practice, so he develops a method for approximating it. The approximation to the zero variance method consists of replacing the continuous adjoint transport solution in the.

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The Los Alamos computer code Monte Carlo Neutron Photon (MCNP) has many useful variance reduction techniques to aid the Monte Carlo user. This report applies many of these techniques to a conceptually simple but computationally demanding neutron transport problem.

Key Words: Monte Carlo, general transform, weight window, hybrid, variance reduction, shielding 1. INTRODUCTION Accurate Monte Carlo simulations of neutron and gamma transport problems require that many Monte Carlo particles undergo the events.

A neutron coincidence counter intended for the verification of cans of PuO2 powder has been designed and optimised using the Monte Carlo radiation transport simulation code-pulse train analyser. Hybrid Monte Carlo – Deterministic Neutron Transport Methods Using Nonlinear Functionals by Emily R.

Wolters A dissertation submitted in partial fulfillment of the requirements for the degree of Doctor of Philosophy (Nuclear Engineering and Radiological Sciences) in.

Principles of analog simulation of MC neutron transport Analog simulation of MC neutron transport In analog Monte Carlo simulation, neutrons are simulated from \birth" (originating from the source) to \death" (absorption or leakage from the system).

The birth-to-death simulation is called a neutron. 1 Introduction to reducing variance in Monte Carlo simulations Antithetic variates method Let X But this is not important since our objective was only to reduce the variance, and we accomplished that. Antithetic normal rvs In many ﬁnance applications, the fundamental rvs needed to construct a desired output copy.

Abstract A new variationally-based Monte Carlo variance reduction (VVR) method is developed to improve the estimation of characteristic parameters for neutron shielding and criticality problems.

And it happens that mathematics again can help answering this question. This lead to an entire branch in Monte Carlo research focused on what's known as variance reduction methods.

How can we reduce variance by any other mean than just increasing N. It happens that importance sampling and quasi monte carlo are two such solutions. First, a brief overview of variance reduction for Monte Carlo radiation transport is described in Section Then,Section expands on the various e↵orts to automate variance reduction techniques in Monte Carlo.

Section follows with an introduction of the concept of importance and how that relates to variance reduction. Coverage of topics such as variance reduction, pseudo-random number generation, Markov chain Monte Carlo, inverse Monte Carlo, and linear operator equations will make the book.

monte carlo methods for particle transport Posted By Agatha Christie Publishing TEXT ID ca30 Online PDF Ebook Epub Library the history of neutron transport monte carlo methods i lux 7 haghighat a monte carlo methods for particle transport crc press taylor and francis group book. 2 Variance Reduction in Monte Carlo 15 Rubinstein, ).

Monte Carlo methods are currently used in a large and diverse number of ﬁelds. Statistical physics and molecular modelling make extensive -rays for radiation and biological studies or neutron transport for nuclear and reactor physics, the subject of this thesis.

Although the Monte Carlo method is considered to be the most accurate method available for solving radiation transport problems, its applicability is limited by its exorbitant computational expensive. The first half of the book presents an exposition of the fundamentals of Monte Carlo methods, examining discrete and continuous random walk processes and standard variance reduction techniques.

The second half of the text focuses directly on the methods of superposition and reciprocity, illustrating their applications to specific neutron Reviews: 2. First, we summarize variance reduction (VR) for Monte Carlo radiation transport and existing efforts to automate these techniques.

Relations among VR, importance, and the adjoint solution of the. Dynamic Monte Carlo (DMC) simulation of realistic nuclear reactors requires powerful variance reduction methods for even a few seconds of real time calculations. State-of-the-art numerical methods deal with the dynamic nature of the problem via successive Monte Carlo transport and TH (thermal-hydraulic) runs in a time step by time step manner.

MCNP is a very general Monte Carlo neutron-photon transport code with approximately person years of Group X-6 code development invested. MCNP contains state-of-the-art traditional and adaptive Monte Carlo techniques to be applied to the solution of an ever-increasing number of problems.

MCNP development will most probably include. This exposition examines fundamentals of Monte Carlo methods plus discrete and continuous random walk processes and standard variance reduction techniques.

It focuses on methods of superposition and reciprocity, illustrating applications that include computation of thermal neutron fluxes and the superposition principle in resonance escape computations.

edition. Several different stratified splitting techniques for sampling the distance to collision are compared with the standard (unstratified) weight window splitting used in MCNP. The results indicate that typical neutron penetration problems could be modestly more efficient using one of the stratified.

This work reviews the state of the art among such hybrid methods. First, we summarize variance reduction (VR) for Monte Carlo radiation transport and existing efforts to automate these techniques.

Relations among VR, importance, and the adjoint solution of the neutron transport. monte carlo codes including mcs mcn mcp and mcg variance reducation techniques or fixed source particles chapter 8 scoring tallying chapter 9 geometry and particle the application of the monte carlo method to particle transport problems with emphasis on neutron and photon transport for monte carlo particle transport methods monte carlo.Monte Carlo (MC) methods, which allow detailed and accurate modeling of the full geometry and energy details and are considered the 'gold standard' for radiation transport solutions, are playing an ever-increasing role in correcting and/or verifying the several-decade-old methodology used in current practice.For these problems, a Hybrid Monte Carlo method overcomes inherent Monte Carlo deficiencies, converges the fission source, and displays a much-reduced variance.