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Lemehov, S.; Suzuki, Motoe
JAERI-Data/Code 2001-025, 338 Pages, 2001/08
PLUTON is a three-group neutronic code analyzing, as functions of time and burnup, the change of radial profiles, together with average values, of power density, burnup, concentration of trans-uranium elements, plutonium buildup, depletion of fissile elements, and fission product generation in water reactor fuel rod with standard UO2, UO2-Gd2O3, inhomogeneous MOX, and UO2-ThO2. The PLUTON code, which has been designed to be run on Windows PC, has adopted a theoretical shape function of neutron attenuation in pellet, which enables users to perform a very fast and accurate calculation easily. The present code includes the irradiation conditions of the Halden Reactor which gives verification data for the code. The total list of trans-uranium elements included in the calculations consists of 92U233-239, 93Np237-239, 94Pu238-243, 95Am241-244 (including isomers), and 96Cm242-245. Verification has been performed up to 83 GWd/tU, and a satisfactory agreement has been obtained.
Yamane, Tsuyoshi; Yamashita, Kiyonobu; Fujimoto, Nozomu
New approaches to the nuclear fuel cycles and related disposal schemes, 1, p.267 - 277, 1998/00
no abstracts in English
Yamashita, Kiyonobu; *; Fujimoto, Nozomu
Nuclear Science and Engineering, 126(1), p.94 - 100, 1997/05
Times Cited Count:2 Percentile:23.04(Nuclear Science & Technology)no abstracts in English
Fujimoto, Nozomu; Yamashita, Kiyonobu
Proc. of Int. Conf. on Future Nuclear Systems (Global'97), 2, p.957 - 962, 1997/00
no abstracts in English