00915cam a2200253 7i4500 0000015318 20180315090000.0 20180315103723.0 180315 ja BI NM M 91 093 Iwamura, Takamichi Effects of radial core power profile on core thermo-hydraulic behavior during reflood phase in SCTF CORE-I forced feed tests Takamichi Iwamura ... [et al.]. Tokai-mura, Naka-gun, Ibaraki-ken: Japan Atomic Energy Research Institute, 1991. vi, 89 p.: ill.; 30 cm.. Includes bibliographical references PWR type reactors Reflood Osakabe, Masahiro Sobajima, Makoto Sudo, Yukio Japan Atomic Energy Research Institute NM RP00017856 Book JAERI - Open Shelf HQ Library