EDN: XTFIUV
Authors & Affiliations
Devkina E.V.
A.I. Leypunsky Institute of Physics and Power Engineering, Obninsk, Russia
 
Devkina E.V. – Researcher. Contact: 1, pl. Bondarenko, Obninsk, Kaluga region, 249033. Tel.: +7 (484) 399-42-16; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it.. 
Abstract
The paper is dedicated to the calculation of nuclear  hazardous areas (NHA) in the course of handling spent removable parts (SRP) of  liquid metal cooled reactors. The main principle of nuclear safety assurance is  elimination of self-sustaining chain reaction (SCR) initiation during normal  operation and in emergency. In the course of SRP handling, process flowsheets  and equipment are developed that meet the nuclear safety standards. Despite the  measures taken to ensure nuclear safety, the risk of SCR exists. Instantaneous  radiation in case of SCR is most hazardous for the personnel, therefore, it is  important to correctly determine the boundaries of the nuclear hazardous area  and the location of the self-sustaining chain reaction alarm system (SCR AS).  In the course of SCR AS designing, calculations of neutron and gamma radiation  fields are performed.
The dose distribution of neutrons and gamma  quanta should be obtained over a sufficiently extended area with a detailed  description of the geometry and strong attenuation of particles. Structural  materials attenuate the fluxes of gamma rays and neutrons by 10 and more orders  of magnitude. Variance reduction methods should be used in order to obtain  reliable data by the Monte Carlo method. Weight windows obtained by the MAGIC  (Method of Automatic Generation of Importances by Calculation) method were used  as a variance reduction method. The use of weight windows made it possible to  obtain calculated data with a reliable statistical error. Based on the  calculation results, the boundaries of nuclear hazardous areas and the SCR DU  location were determined. 
Keywords
nuclear hazardous area, spent removable part  of the reactor, self-sustaining chain  reaction, self-sustaining chain reaction alarm system, self-sustaining chain  reaction detection unit, Monte Carlo method, weight windows, MAGIC method,  relative error, absorbed dose
 Article Text (PDF, in Russian)
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UDC 621.039.7+519.245
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2024, no. 3, 3:5