EDN: JLWAOZ
Authors & Affiliations
Tarasov A.Yu., Nikolaev A.A.
OKB “GIDROPRESS”, Podolsk, Russia
Tarasov A.Yu. – Design Engineer 1st category. Contacts: 21, Ordzhonikidze st., Podolsk, Moscow region, 142103. Tel.: +7 (495) 502-79-13; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Nikolaev A.A. – Deputy Head of Department, Dr. Sci. (Tech.).
Abstract
The paper considers the issues of radiation transport along inhomogeneities in the radiation shielding of a reactor plant with a lead-bismuth coolant using the DSN-method of discrete ordinates. In particular, a study was made of the scale of influence of the application of the most frequently used
ES16-quadratures in the calculation justification, as well as other higher-order ESN-quadratures, on the results of calculating the radiation fields above the reactor monoblock cover. One of the components of the radiation field formation above the reactor monoblock cover is the leakage of radiation along the gap between the pressure vessel and the safety casing of the reactor monoblock. Three dimensional variants of reactor plant models with lead-bismuth coolant with attenuation of the total neutron flux density along the forward direction from the core to the reactor-scale monoblock cover from 1010 to 1016 are considered. With increasing model dimensionality, the contribution of radiation leaking along inhomogeneities becomes significant and is poorly approximated by standard ESN-type quadratures, even of high order (ES64) – the difference reaches 300 %. This effect is dangerous because such a high SN approximation is considered standard by default. At the same time, the results obtained with its use can be misleading. The problem is quite simply solved using composite quadratures with local compaction of ordinate nodes.
Keywords
FRIGATE, DSN-method, fast reactor, lead-bismuth coolant, shielding calculations, ordinates splitting, ESN-quadratures
Article Text (PDF, in Russian)
References
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UDC 621.039.51
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2024, no. 4, 4:6
