Author:
Chang G. S.,Ambrosek R. G.
Publisher
Oxford University Press (OUP)
Subject
Public Health, Environmental and Occupational Health,Radiology, Nuclear Medicine and imaging,General Medicine,Radiation,Radiological and Ultrasound Technology
Reference11 articles.
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3. Croff, A. G. ORIGEN2: a versatile computer code for calculating the nuclide compositions and characteristics of nuclear materials. Nucl. Technol.62, 335–352 (1983).
4. Chang, G. S. and Ryskamp, J. M. Depletion analysis of mixed oxide fuel pins in light water reactors and the advanced test reactor. Nucl. Technol.129(3), 326–337 (2000).
5. Chang, G. S. Monte Carlo analysis of burnup-dependent plutonium concentration profiles in UO2 and MOX fuel pins. Trans. Am. Nucl. Soc.78, 246 (1998).
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