CHINESE JOURNAL OF COMPUTATIONAL PHYSICS ›› 1999, Vol. 16 ›› Issue (2): 177-182.
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Chen Wei1, Jiang Xinbiao1, Xie Zhongsheng1, Chen Da2
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Abstract: 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.
Key words: Pulsed reactor, nuclear safety parameter, power peaking factor, fuel negative temperature reactivity coefficient
CLC Number:
TL329
Chen Wei, Jiang Xinbiao, Xie Zhongsheng, Chen Da. Study of nuclear safety parameters of uranium zirconium hydride pulsed research reactor core[J]. CHINESE JOURNAL OF COMPUTATIONAL PHYSICS, 1999, 16(2): 177-182.
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http://www.cjcp.org.cn/EN/Y1999/V16/I2/177