Journal of Radiation Protection and Research
- Volume 1 Issue 1
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- Pages.1-9
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- 1976
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- 2508-1888(pISSN)
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- 2466-2461(eISSN)
Fast Neutron Dosimetry in Criticality Accidents
핵임계사고시(核臨界事故時)에 있어서 속중성자선량(速中性子線量)의 해석(解析)
- Ro, Seung-Gy (Korea Atomic Energy Research Institute) ;
- Yook, Chong-Chul (Dept. of Nuclear Engineering, Hanyang University)
- Published : 1976.03.25
Abstract
A suggestion has been made for neutron dosimetric techniques using activation and threshold detectors in criticality accidents. Neutron dosimetrical parameters, namely, the fission spectrum-averaged cross-sections of some threshold reactions and fluence-to-dose conversion factors have been calculated by the use of an electronic computer. It appears that detectors having comparatively high threshold energy give more fine information on spectral deformation in criticality accidents, while detectors with low threshold energy are of usefulness for measuring fast neutron fluence regardless of fissioning types. Unexpectedly it is found that the fission spectrum-averaged cross sections of the
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