Home / Publications / Journals / Nuclear Technology / Volume 93 / Number 2
Nuclear Technology / Volume 93 / Number 2 / February 1991 / Pages 123-130
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT91-A34498
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A model correlating the minimum critical power ratio (MCPR) of standardized boiling water reactors (BWRs) to a set of thermal-hydraulic variables in parameter space is developed. A statistical approach with fractional factorial sampling along with response surface methodology and orthogonal central composite design are employed. The COBRA-II computer code, after modifications to include MCPR calculation, is used to simulate the thermal hydraulics of the BWR/6. The sensitivity is obtained by differentiating a quadratic equation that represents the state of the system with respect to its constituent variables. Taking this correlation as a joint multivariable probability distribution function and using crude Monte Carlo integration techniques, the probability of boiling transition during normal operation in a standardized BWR/6 is estimated. The result agrees very well with data available in open literature.