Test Results of Variance Reduction Techniques Applied to Deep Penetration Problem

Author:

Bogdanova E. V.1ORCID,Tikhomirov G. V.1ORCID

Affiliation:

1. National Research Nuclear University (MEPhI)

Abstract

Nowadays, there is a problem of a lack of computer power to conduct high-precision reactor analysis. There are several factors that increase the excessive computational load and make it difficult to calculate nuclear reactor full-scale models using Monte Carlo method. Among them is the large neutron-flux attenuation, which is observed in deep penetration problems. Various reduction techniques are used to increase the efficiency of Monte Carlo calculations in such tasks. It allows to reduce the statistical uncertainty of the functional evaluation without increasing the number of neutron histories. This work is devoted to study and testing of variance reduction techniques in the deep penetration problem. To demonstrate the possibility of using non-analogue Monte Carlo modeling a test problem was formulated. To quantify the efficacy of applying the variance reduction methods, FOM characteristic is considered, which is a function of the relative error in a flux estimate and the computational time of the simulation. The article considers non-analogue techniques implemented in the MCU (Monte Carlo Univarsal) and OpenMC codes. As part of the study, a module of the OpenMC code was developed that allows to automatically generate weight windows. It is shown that variance reduction techniques increase the calculation efficiency by several times, particularly, the weight windows method in OpenMC make it possible to achieve a 7-fold increase in the efficiency of neutron flux estimation with the same number of simulated histories. The formulated recommendations can be used in the calculation of innovative nuclear reactors full-scale models.

Publisher

National Research Nuclear University MEPhI (Moscow Engineering Physics Institute)

Subject

General Earth and Planetary Sciences,General Engineering,General Environmental Science

Reference25 articles.

1. Edward W. Larsen (2006) An Overview of Neutron Transport Problems and Simulation Techniques. In: Graziani F. (eds) Computational Methods in Transport. Lecture Notes in Computational Science and Engineering, vol 48. Springer, Berlin, Heidelberg.

2. Paul Kollath Romano. Parallel Algorithms for Monte Carlo Particle TransportSimulation on Exascale Computing Architectures. Massachusetts Institute of Technology, - 2013.

3. Kord Smith, «Reactor Core Methods», Invited lecture at the M&C 2003 International Conference, April 6-10, 2003, Gatlinburg, TN, USA, 2003.

4. Chistyakov, V.P. Kurs teorii veroyatnostei / V.P. Chistyakov. - Moskva : Nauka, 1982.

5. W.R. MARTIN, «Advances in Monte Carlo Methods for Global Reactor Analysis», Proc. Joint International Topical Meeting on Mathematics & Computation and Supercomputing in Nuclear Applications, Monterey, California, April 15-19, 2007, Invited Lecture.

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