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Thermal neutron flux distribution and flux trap effect in the active core of the UA-RR-I reactor

Распределение потока тепловях нейтронов и эффект ловушки потока в активной зоне реактора UA-RR-I

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Acta Physica Academiae Scientiarum Hungaricae

Abstract

The thermal neutron flux distribution at various points of the active core and irradiation channels of the UAR water-water reactor, was measured by the neutron activation method of copper and gold foils. An increase in the thermal neutron flux in the active core is achieved by creating a water cavity of 7 cm2 section. The thermal neutron flux in the cavity is increased 2.3 and 2.6 times compared with that in the active core and the irradiation channels, respectively.

Резюме

Распределение потока тепловых нейтронов в разных точках активной зоны и канала облучения водно-водяного реактора UAR измерялось нейтронно-активационным методом при помощи латунной и золотой фольги. В активной зоне достигалось заметное увеличение потока тепловых нейтронов созданием водной полости поперечного сечения в 7 cm2. Поток тепловых нейтронов в полости увеличился в 2,3 и 2,6 раза по сравнению со значением в активной зоне и в канале облучения соответственно.

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Saad, E.A., Bartchouk, I., Eissa, N.A. et al. Thermal neutron flux distribution and flux trap effect in the active core of the UA-RR-I reactor. Acta Physica 23, 327–340 (1967). https://doi.org/10.1007/BF03156773

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  • DOI: https://doi.org/10.1007/BF03156773

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