DAREUS Software Package for Modeling the Dynamics of Solution Reactors Using the Monte Carlo Method
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US Software Package for Modeling the Dynamics of Solution Reactors Using the Monte Carlo Method E. A. Gomina, V. D. Davidenkoa,*, O. V. Davidenkoa, A. A. Kovalishina, M. N. Laletina, and A. K. Pavlova,** aNational
Research Center Kurchatov Institute, pl. Kurchatova 1, Moscow, 123182 Russia *e-mail: [email protected] **e-mail: [email protected] Received September 14, 2017
Abstract—The DAREUS software package designed for modeling dynamic processes in the cores of experimental solution reactors is described. The KIR program based on the Monte Carlo method is used in the package to compute the necessary kinetic parameters. The results of the calculations of some test cases are given. Keywords: computation, dynamics, kinetics, solution reactor, Monte Carlo method, supercomputer DOI: 10.1134/S1063778818080100
INTRODUCTION The DAREUS software package is designed for computer simulation of dynamic processes in the cores of solution reactors and is used at the Kurchatov Institute for the computational support and computational modeling of the development of emergency modes for the Gidra [1, 2] and Argus [1, 2] research solution reactors. The Gidra pulsed research reactor (PRR) was developed and commissioned at the Kurchatov Institute of Atomic Energy (IAE) (now the National Research Center Kurchatov Institute) in 1972. It belongs to the class of self-quenching pulsed reactors, the power pulse in which is quenched mainly owing to the negative reactivity effect associated with the formation of radiolytic gas fission fragments along the tracks. The release of radiolytic gas from the fuel solution is accompanied by a rapid radiolytic boiling with a sharp decrease in the fuel density (void reactivity coefficient). The reactor is designed to study the nature of radiation defects in various materials in high-intensity fields of reactor radiation, carry out activation analysis of short-lived radionuclides, and also conduct ampoule dynamic tests of fuel rods of various reactors in the event of an accident with increasing reactivity. The Argus research reactor (RR) was developed and commissioned at the IAE in 1981. The reactor operates at a steady-state power and is designed to find the best physical and technical solutions for the development of nuclear physics methods of analysis and control and for the production of radionuclides for
medical purposes. Neutron activation analysis and neutron radiography are performed at the Argus reactor. To date, the nuclear safety of these reactors has been validated using software tools that make it possible to calculate the effects and coefficients of reactivity, other key reactivity characteristics, and the efficiency of the control and protection system (CPS) using the Monte Carlo method. The DAREUS software package is the first one that implements interconnected neutronic, thermohydraulic, and thermomechanical calculations of the dynamics of solution reactors. 1. DAREUS SOFTWARE PACKAGE The DAREUS software package includes the KIR neutronic calculation code [3], the GARD thermohydrau
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