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The human factor in licensing and operating the next generation of nuclear plants
As human factors specialists working at the intersection of human performance and nuclear operations, we are witnessing one of the nuclear sector’s most significant transitions in decades. The emergence of small modular reactors, microreactors, and other advanced designs is reshaping the industry’s landscape. Digital instrumentation and controls, passive safety systems, and increased automation are creating opportunities for greater safety margins and more flexible operation. These same features also fundamentally redefine what it means to “operate” a nuclear plant. Interactions among human roles, automation, and passive systems shape how people maintain awareness, exercise judgment, and intervene when necessary. These developments affect both operational realities and the regulatory foundations on which nuclear safety is built.
Jeffrey T. Dillingham, James H. Stuhmiller
Nuclear Technology | Volume 100 | Number 2 | November 1992 | Pages 260-270
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34747
Articles are hosted by Taylor and Francis Online.
Critical heat flux (CHF) in boiling water and pressurized water reactors is investigated using a three-pronged approach. First, a physically realistic and mathematically rigorous computational model is developed to describe and simulate the transitions between flow regimes. This is called the dynamic flow regime model (DFRM). Second, extensive reanalysis of the Columbia University CHF experimental data is performed to shed light on the processes at work. This analysis indicates that the mechanism for wall drying may not follow conventional wisdom. The DFRM has therefore been supplemented with a semiempirical liquid entrainment model, which accounts for the dynamics of bubble formation. The model produces CHF predictions that agree with the Columbia data slightly better than the Columbia correlation function. Third, to develop a mechanistic understanding of the empirical model, detailed microscale simulations of boiling are performed using the EITACC computer code. EITACC solves the Navier-Stokes equations for three-dimensional two-phase flow using a finite difference method. EITACC has been used to produce time-lapse images of bubble formation at a wall during subcooled boiling. These images provide insight into the mechanisms of bubble separation from the wall, bubble collapse due to condensation, wall drying, and liquid entrainment. This insight is used to improve and validate the DFRM.