Электронный каталог


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    Tech / Japan atomic energy research inst. 2003-021 : Extended calculations of OECD/NEA phase II-C burnup credit criticality benchmark problem for PWR spent fuel transport cask by using MCNP-4B2 code and JENDL-3.2 library / T.Kuroishi,A.T.Hoang,Y.Nomura,H.Okuno, 2003. - Текст : непосредственный.

    Лицевая сторона карточкиОбратная сторона карточки

    Лицевая сторона карточкиОбратная сторона карточки

    Designing of stereo-wire geometry for a long cylindrical drift chamber with small jet cells / N.Khalatyan,K.Fujii,H.Okuno и др., 1998. - 13 p. - Текст : непосредственный.

    revision of mutual, a computer code for analysing nuclear criticality safety on array system : Mfiche(1) / H.Okuno,Y.Naito,T.Kaneko,K.Kuribayashi, 1989. - 36 мкфш. - Текст : непосредственный.

    New trends in applied artificial intelligence : 20th International conference on industrial, engineering and other applications of applied intelligent systems, IEA/AIE 2007, Kyoto, Japan, June 26-29, 2007: proceedings / SpringerLink (Online service), 2007 r=on-line. - Текст : электронный.

    Okuno H. OECD/NEA Burnup credit criticality benchmarks phase IIIA: criticality calculations of BWR spent fuel assemblies in storage and transport / H.Okuno,Y.Naito,Y.Ando, 2000. - 179 p. - Текст : непосредственный.

    Tokano M. OECD/NEA burnup credit criticality benchmark :result of phase IIA / M.Tokano,H.Okuno, 1996. - 170 p. - Текст : непосредственный.

    Okuno H. Burnup calculations ofBWR fuel assemblies for storage and transport / H.Okuno,Y.Naito,K.Suyama, 2002. - IV, 181 p. 181 p. - Текст : непосредственный.

    Okuno H. Critical and subcritical masses of curium-245,-246 and -247 calculated with a combination of MCNP4A code and JENDL-3.2 library / H.Okuno,H.Kawasaki, 2000. - III,44 p. p. - Текст : непосредственный.

    Analyses of PWR spent fuel composition using SCALE and SWAT code systems to find correction factors for criticality safety applications adopting burnup credit / H.S.Shin,K.Suyama,H.Mochizuki и др., 2001. - IV,131 p. p. - Текст : непосредственный.

    Development of a new simulation code for evaluation of criticality transients involving fissile solution boiling / B.Basoglu,T.Yamamoto,H.Okuno,Y.Nomura, 1998. - V,89 p. p. - Текст : непосредственный.