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Assessment of occupational internal exposure to beta emitters from the nuclear reactor primary coolant circuit

机译：评估来自核反应堆初级冷却剂回路的β发射器职业内部暴露

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Tomasz Pliszczyński; Katarzyna Ciszewska; Małgorzata Dymecka; Jakub Ośko; Zbigniew Haratym;
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年度 2012
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5. Probabilistic risk assessment for a loss of coolant accident in McMaster Nuclear Reactor and application of reliability physics model for modeling human reliability. [D] . Ha, Taesung. 2007

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6. Development of an automatedchemistry control system forsecondary coolant circuits inCANDU nuclear power reactors [O] . J. R. Dean, R. B. Stewart 1979

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7. Figure 3 from: Beznosov AV, Bokov PA, Lvov AV, Bokova TA, Volkov NS, Marov AR (2020) Experimental studies into the performance of the lead coolant axial pump wet ends to justify main circulation pumps for the HMLC reactor plant circuits. Nuclear Energy and Technology 6(3): 143-147. https://doi.org/10.3897/nucet.6.57736 [O] . Aleksandr V. Beznosov, Pavel A. Bokov, Aleksandr V. Lvov, 2020

机译：图3来自：Beznosov AV，Bokov Pa，LVov AV，Bokova TA，Volkov NS，Marov AR（2020）对铅冷却液轴向泵湿端的性能进行实验研究，以证明HMLC反应器厂电路的主循环泵。核能和技术6（3）：143-147。 https://doi.org/10.3897/nucet.6.57736
8. COBRA/TRAC - A Thermal-Hydraulics Code for Transient Analysis of Nuclear Reactor Vessels and Primary Coolant Systems. Volume 4. Developmental Assessment and Data Comparisons. [R] . Thurgood, M. J., Guidotti, T. E., Sly, G. A., 1983

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Assessment of occupational internal exposure to beta emitters from the nuclear reactor primary coolant circuit

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