The use of the neutronic calculation code CORNER for evaluating the protection of fast neutron reactor and CNFC equipment

International Conference for Young Scientists, Specialists, and Postgraduates on Nuclear Reactor Physics 2016

Shekhanova, M.E.^1,2

National Research Nuclear University, MEPhI, 31, Kashirskoe Shosse, Moscow

115409, Russia^1

Nuclear Safety Institute of the Russia Academy of Sciences, 52, B.Tulskaya st., Moscow

115119, Russia^2

关键词: Benchmark experiments;    Fast neutron reactors;    Fuel cycle;    Hexagonal geometry;    Kinetic equations;    Liquid metal coolants;    Neutronic calculations;    Safety analysis;   

Others  :  https://iopscience.iop.org/article/10.1088/1742-6596/781/1/012042/pdf
DOI  :  10.1088/1742-6596/781/1/012042

来源: IOP

【 摘 要 】

In this paper we propose a method of using neutronic calculation code CORNER to the analysis of experiments on the protection of fast neutron reactor and CNFC equipment. An example of Winfrith Graphite Benchmark experiment calculation using this approach is presented. This task can be considered as one step in the general theme of the safety analysis of FR with liquid metal coolant, their fuel cycles and related equipment. CORNER implement a solution of the kinetic equation with a source in the three-dimensional hexagonal geometry based on Sn-method. The purpose of this paper is a demonstration of the application of CORNER's possibilities for the analysis of the actual reactor problems.