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CORIUMSITY program code for the consequences analysis of a severe core melt accident
Author(s) -
Ivan Saldikov,
E. V. Bogdanova,
P. A. Pugachev,
S. N. Ryzhov,
A. D. Smirnov,
Mikhail Ternovykh,
Г. В. Тихомиров
Publication year - 2020
Publication title -
journal of physics. conference series
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.21
H-Index - 85
eISSN - 1742-6596
pISSN - 1742-6588
DOI - 10.1088/1742-6596/1689/1/012057
Subject(s) - burnup , computer science , nuclide , code (set theory) , nuclear engineering , nuclear reactor core , nuclear power plant , benchmark (surveying) , core model , boiling water reactor , core (optical fiber) , source code , engineering , mathematics , nuclear physics , physics , programming language , telecommunications , set (abstract data type) , mathematical analysis , geodesy , geography
As part of the tasks to improve the nuclear safety of nuclear power plants, a new program code was developed. The CORIUMSITY program code developed, considered in this work, is intended to analyze the scenario in which an accident at a nuclear power plant is simulated with the melting of the core and the formation of the so-called “corium” - a mixture of nuclear and structural materials of the nuclear reactor core, formed as a result of thermal and mechanical impact during an accident. The CORIUMSITY program code, is intended to analyze several scenarios of different accidents, include an accident with reactor core melting. The functions of this code can help in solving many urgent nuclear safety problems. One of the main methods of operation of the CORIUMSITY code algorithms is the matrix exponential method, which consists in using a matrix function of a square matrix, in which as values are used indicators corresponding to nuclides from the CORIUMSITY code database. The program implements an iterative Euler method for solving the system of levels of nuclear fuel burnup. The CORIUMSITY code was verified with benchmark data to assess the accuracy of the calculation.

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