Measurement of integral thermal neutron flux in a high flux reactor by the Co activation method
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Measurement of integral thermal neutron flux in a high flux reactor by the Co activation method
Nuclear TechniquesVol. 11, Issue 12, (1988)
作者机构:
中国科学院上海原子核研究所
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Received:24 September 1987,
Published:1988-12
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Luona Chen, Borong Bao, Yanfei Li, et al. Measurement of integral thermal neutron flux in a high flux reactor by the Co activation method[J]. Nuclear techniques, 1988, 11(12): 33-35.
DOI:
Luona Chen, Borong Bao, Yanfei Li, et al. Measurement of integral thermal neutron flux in a high flux reactor by the Co activation method[J]. Nuclear techniques, 1988, 11(12): 33-35.DOI:
Measurement of integral thermal neutron flux in a high flux reactor by the Co activation method
A method is presented for the measurement of integrated thermal neutron flux in a high flux reactor by a Co-activation method. The measured value of integrated thermal neutron flux was compared with the calculated value. The method is very useful for the determination of a higher integral thermal neutron flux in a high flux reactor for a long period of irradiation time.
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references
张家骅 等 , 核科学与工程 , 6 ( 1986 ), 2 : 192 。
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IAHA-TECDOC-412, Thorium-based nuclear fuel: Current states and perspectiues. IAEA , Vienna , 1987 .