ISSN 2079-3537      

 
 
 
                                                                                                                                                                                                                                                                                                                                                                                                                                                                             





Scientific Visualization, 2020, volume 12, number 3, pages 100 - 107, DOI: 10.26583/sv.12.3.09

Visualization of neutron characteristics distribution of debris particles

Authors: P.A. Pugachev1,A, E.V. Bogdanova2,A, I.S. Saldikov3,A, A.D. Smirnov4,A, M.Y. Ternovykh5,A, G.V. Tikhomirov6,A, H. Takezawa7,B, T. Muramoto8,C, J. Nishiyama9,C, T. Obara10,C

A Institute of Nuclear Physics and Engineering, National Research Nuclear University MEPhI

B Department of Nuclear Safety Engineering, Faculty of Science and Engineering, Tokyo City University

C Laboratory for Advanced Nuclear Energy, Institute of Innovative Research, Tokyo Institute of Technology

1 ORCID: 0000-0002-8175-3957, PAPugachev@mephi.ru

2 ORCID: 0000-0002-8184-2124, EVBogdanova@mephi.ru

3 ORCID: 0000-0002-8667-8706, ISSaldikov@mephi.ru

4 ORCID: 0000-0003-0401-2298, ADSmirnov@mephi.ru

5 ORCID: 0000-0002-9830-5501, MYTernovykh@mephi.ru

6 ORCID: 0000-0002-5332-7272, GVTikhomirov@mephi.ru

7 ORCID: 0000-0002-1192-0158, takezawa@tcu.ac.jp

8 ORCID: 0000-0003-2809-8540, muramoto.t.ab@m.titech.ac.jp

9 ORCID: 0000-0002-0977-127X, jun-nishiyama@lane.iir.titech.ac.jp

10 ORCID: 0000-0002-7624-4154, tobara@lane.iir.titech.ac.jp

 

Abstract

Accident at Fukushima Daiichi nuclear power plant led to increase of importance of safety justification for processes at post-accident facilities in nuclear industry. One of such processes is extraction of corium from reactors cavity. Recriticality of this process is defined by potential unacceptable accident. This paper introduces supporting code for neutron fluxes and reaction rates visualization in systems with complex geometry that can be used in modeling of corium removing works. Visualization code is based on Unreal Engine 4 game engine. Code allows observing neutronic functionals distribution in three dimensions. The reseach and provided implementation details help to understand the physical processes that take place as the accidents occur during corium removing works.

 

Keywords: fuel debris, Monte Carlo, criticality analysis, corium.