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Study of nuclear safety parameters of uranium zirconium hydride pulsed research reactor core
Chen Wei, Jiang Xinbiao, Xie Zhongsheng, Chen Da
CHINESE JOURNAL OF COMPUTATIONAL PHYSICS
1999, 16 (2):
177-182.
By using lattice calculation code WIMS-D/4,hexagonal nodal diffusion code SIXTUS and the WIMS-N1/N2 library which include the data of the nuclide H in ZrH,Er-166 and Er-167,nuclear safety parameters are analyzed of uranium zirconium hydride pulsed reactor core,power peaking factor and fuel temperature coefficient.
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