Simulation of the radiation fields from ionizing radiation sources inside the containment in an accident
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lation of the Radiation Fields from Ionizing Radiation Sources inside the Containment in an Accident M. A. Kalugin* Russian Research Center Kurchatov Institute, pl. Kurchatova 1, Moscow, 123182 Russia Received December 23, 2008
Abstract—In the present work, a set of codes used for simulations of the radiation fields from ionizing radi ation sources inside the containment in an accident is described. A method of evaluating the gamma dose rate from a space and energy distributed source is given. The dose rate is calculated by means of the design point kernel method and using buildup factors. The code MCUREA with the ORIMCU module is used for the burnup calculations. DOI: 10.1134/S1063778810130041
1. FORMULATION OF THE PROBLEM During an accident at a nuclear power plant (NPP) with a watermoderated reactor, there is a chance for radioactive nuclides to escape the core region and get into the accident localization system, within whose cells they create ionizing radiation fields. Under the influence of those fields, various radiationchemical reactions take place inside those cells, thus affecting the behavior of the iodine isotopes. To evaluate the gamma (photon) radiation dose rate inside the cells, which is required for simulations of radiationchemi cal reactions and behavior of iodine isotopes, the engi neering program PKD was developed [1]. The program PKD is part of the software package ORIPKD that lets one calculate radioactive nuclide buildup in the nuclear reactor fuel as a function of the radiation time, as well as the radiation characteristics (RCs) of the burned fuel as a function of the delay time and radiation fields created by the energy sources inside the containment in an accident. In this work, a functional description of the software package ORIPKD is given along with the method of calculat ing the dose characteristics and the results of PKD program verification, which was conducted by com paring the results of calculations obtained by the latter and other known programs [2]. 2. SCHEME FOR CALCULATING THE DOSE CHARACTERISTICS The software package ORIPKD is the next step in the development of the program MCUREA [3] with the module ORIMCU [4] that determines the radio active nuclide composition in the nuclear reactor fuel as a function of the radiation time. The module ORI4F is used to evaluate RCs of the burned fuel as a *Email: [email protected]
function of the delay time. The software package is modular with fixed interfaces. A user can use either standard libraries or perform more accurate calcula tions with the new libraries to be compiled by means of special modules. The program PKD is used to com pute the dose characteristics. The wellknown program ORIGENS [5] from the package SCALE4.3 [6] is exploited as a unit to calcu late isotope kinetics within a single time step in the modules ORIMCU and ORI4F. The program ORI GENS has been used as part of MCUREA at the Russian Research Center Kurchatov Institute since 1999, following an agreement with the Oak Ridge National Labo
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