Determination of the neutron flux in the reactor zones with the strong neutron absorption and leakage

Serbian Journal of Electrical Engineering

Milošević Miodrag 1¹  Ljubenov Vladan¹ 

[1] VINČA Institute of Nuclear Sciences, Center for Nuclear Technologies and Research "NTI-", Belgrade, Serbia and Montenegro;

关键词: nuclear reactor;    neutron flux;    cross-section;    resonant absorption;   

DOI  :  10.2298/SJEE0403099L

来源: DOAJ

【 摘 要 】

The procedures for the numerical and experimental determination of the neutron flux in the zones with the strong neutron absorption and leakage are described in this paper. Numerical procedure is based on the application of the SCALE-4.4a code system where the Dancoff factors are determined by the VEGA2DAN code. Two main parts of the experimental methodology are measurement of the activity of irradiated foils and determination of the averaged neutron absorption cross-section in the foils by the SCALE-4.4a calculation procedure. The proposed procedures have been applied for the determination of the neutron flux in the internal neutron converter used with the RB reactor core configuration number 114.

【 授权许可】

Unknown