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TRACG Transient Analysis Code—Three-Dimensional Kinetics Model Implementation and Applicability for Space-Dependent Analysis

Yutaka Takeuchi, Yukio Takigawa, Hitoshi Uematsu, Shigeo Ebata, James C. Shaug, Bharat S. Shiralkar

Nuclear Technology / Volume 105 / Number 2 / February 1994 / Pages 162-183

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34920

Space- and time-dependent phenomena, mostly related to neutron flux oscillations, have been observed in several boiling water reactor plants, A time-dependent three-dimensional transient analysis code is indispensable for simulating such phenomena. In a joint effort between the General Electric Company and the Toshiba Corporation, a three-dimensional neutron kinetics model has been implemented into the best-estimate thermal-hydraulics code, TRACG. A neutronics model implementation and the applicability of the modified TRACG code for analyzing space-dependent phenomena are discussed. To verify the code, startup tests with selected rod insertions, where control rods are locally inserted, are simulated. Both corewide, spatially in-phase neutron flux oscillations and regional, spatially out-of-phase oscillations are modeled. The results show that the modified TRACG code has sufficient capability to simulate space-dependent transients and is also a useful tool for investigating the fundamental mechanisms behind such transients.